From 42285d775e6996b0c74d42fcd1e35a16453ad1d8 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 5 Mar 2016 09:26:23 -0500 Subject: [PATCH 001/147] Made scattdata % energy sparse as a test bed (and where speedup benefit occurs from) --- src/scattdata_header.F90 | 213 ++++++++++++++++++++++++++++++++------- 1 file changed, 177 insertions(+), 36 deletions(-) diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index f8fddbc6b..8dc64a653 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -8,6 +8,49 @@ module scattdata_header implicit none + +!=============================================================================== +! JAGGED1D and JAGGED2D is a type which allows for jagged 1-D or 2-D array. +!=============================================================================== + + type :: Jagged2D + real(8), allocatable :: data(:,:) + end type Jagged2D + + type :: Jagged1D + real(8), allocatable :: data(:) + end type Jagged1D + + +!=============================================================================== +! OUTGOINGTRANSFER contains sparse outgoing scattering matrices for a single +! incoming group +!=============================================================================== + + type OutgoingTransfer + real(8), allocatable :: data(:,:) ! Outgoing transfer probabilities + ! Dimension of (moments, gmin:gmax) + integer :: gmin + integer :: gmax + contains + ! Initialize OutgoingTransfer given a dense (GoutxL) matrix + procedure:: init => outgoingtransfer_init + end type OutgoingTransfer + + +!=============================================================================== +! GROUPTRANSFER contains sparse outgoing scattering matrices for all +! incoming groups +!=============================================================================== + + type GroupTransfer + type(OutgoingTransfer), allocatable :: outgoing(:) ! Outgoing transfer probabilities + contains + ! Initialize GroupTransfer given a dense (GinxGoutxL) matrix + procedure:: init => grouptransfer_init + end type GroupTransfer + + !=============================================================================== ! SCATTDATA contains all the data to describe the scattering energy and ! angular distribution @@ -15,9 +58,11 @@ module scattdata_header type, abstract :: ScattData ! p0 matrix on its own for sampling energy - real(8), allocatable :: energy(:,:) ! (Gout x Gin) + type(Jagged1D), allocatable :: energy(:) ! (Gin % data(Gout)) real(8), allocatable :: mult(:,:) ! (Gout x Gin) real(8), allocatable :: data(:,:,:) ! (Order/Nmu x Gout x Gin) + integer, allocatable :: gmin(:) ! Minimum outgoing group + integer, allocatable :: gmax(:) ! Maximum outgoing group contains procedure(scattdata_init_), deferred :: init ! Initializes ScattData @@ -93,22 +138,109 @@ module scattdata_header contains +!=============================================================================== +! GROUPTRANSFER_INIT builds the OutgoingTransfer object given a dense scattering +! matrix of (GoutxL) dimensionality. +!=============================================================================== + + subroutine grouptransfer_init(this, dense) + class(GroupTransfer), intent(inout) :: this ! Object to Initialize + real(8), intent(in) :: dense(:,:,:) ! Source Dense Matrix of + ! (GinxGoutxL) dims. + + integer :: gin, groups + + groups = size(dense,dim=1) + allocate(this % outgoing(groups)) + do gin = 1, groups + call this % outgoing(gin) % init(dense(gin,:,:),gin) + end do + + end subroutine grouptransfer_init + + +!=============================================================================== +! OUTGOINGTRANSFER_INIT builds the OutgoingTransfer object given a dense scattering +! matrix of (GoutxL) dimensionality. +!=============================================================================== + + subroutine outgoingtransfer_init(this, dense, gin) + class(OutgoingTransfer), intent(inout) :: this ! Object to Initialize + real(8), intent(in) :: dense(:,:) ! Source Dense Matrix of + ! (GoutxL) dims. + integer, intent(in) :: gin ! Incoming group + + integer :: groups, order, gmin, gmax, gout, l + + groups = size(dense,dim=1) + order = size(dense,dim=2) + + ! Find gmin by checking the P0 moment + do gmin = 1, groups + if (dense(gmin,1) > ZERO) exit + end do + ! Find gmax by checking the P0 moment + do gmax = groups, 1, -1 + if (dense(gmax,1) > ZERO) exit + end do + ! Treat the case of all zeros + if (gmin > gmax) then + gmin = gin + gmax = gin + end if + + ! Now we can allocate our OutgoingTransfer object and place data + allocate(this % data(order, gmin:gmax)) + do gout = gmin, gmax + do l = 1, order + this % data(l,gout) = dense(gout,l) + end do + end do + this % gmin = gmin + this % gmax = gmax + + end subroutine outgoingtransfer_init + !=============================================================================== ! SCATTDATA_INIT builds the scattdata object !=============================================================================== subroutine scattdata_init(this, order, energy, mult) class(ScattData), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + integer, intent(in) :: order ! Data Order + real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix + real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - integer :: groups + integer :: groups, gmin, gmax, gin groups = size(energy, dim=1) - allocate(this % energy(groups, groups)) - this % energy = energy + allocate(this % gmin(groups)) + allocate(this % gmax(groups)) + allocate(this % energy(groups)) + ! Use energy to find the gmin and gmax values + ! Also set energy values when doing it + do gin = 1, groups + ! Find gmin by checking the P0 moment + do gmin = 1, groups + if (energy(gmin,gin) > ZERO) exit + end do + ! Find gmax by checking the P0 moment + do gmax = groups, 1, -1 + if (energy(gmax,gin) > ZERO) exit + end do + ! Treat the case of all zeros + if (gmin > gmax) then + gmin = gin + gmax = gin + ! By not changing energy(gin) here we are leaving it as zero + end if + allocate(this % energy(gin) % data(gmin:gmax)) + this % energy(gin) % data(gmin:gmax) = energy(gmin:gmax,gin) + this % gmin(gin) = gmin + this % gmax(gin) = gmax + end do + allocate(this % mult(groups, groups)) this % mult = mult allocate(this % data(order, groups, groups)) @@ -117,11 +249,11 @@ contains end subroutine scattdata_init subroutine scattdatalegendre_init(this, order, energy, mult, coeffs) - class(ScattDataLegendre), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + class(ScattDataLegendre), intent(inout) :: this ! Object to work on + integer, intent(in) :: order ! Data Order + real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix + real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use real(8) :: dmu, mu, f integer :: imu, Nmu, gout, gin, groups @@ -285,10 +417,10 @@ contains pure function scattdatalegendre_calc_f(this, gin, gout, mu) result(f) class(ScattDataLegendre), intent(in) :: this ! The ScattData to evaluate - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8) :: f ! Return value of f(mu) + integer, intent(in) :: gin ! Incoming Energy Group + integer, intent(in) :: gout ! Outgoing Energy Group + real(8), intent(in) :: mu ! Angle of interest + real(8) :: f ! Return value of f(mu) ! Plug mu in to the legendre expansion and go from there f = evaluate_legendre(this % data(:, gout, gin), mu) @@ -297,10 +429,10 @@ contains pure function scattdatahistogram_calc_f(this, gin, gout, mu) result(f) class(ScattDataHistogram), intent(in) :: this ! The ScattData to evaluate - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8) :: f ! Return value of f(mu) + integer, intent(in) :: gin ! Incoming Energy Group + integer, intent(in) :: gout ! Outgoing Energy Group + real(8), intent(in) :: mu ! Angle of interest + real(8) :: f ! Return value of f(mu) integer :: imu @@ -318,10 +450,10 @@ contains pure function scattdatatabular_calc_f(this, gin, gout, mu) result(f) class(ScattDataTabular), intent(in) :: this ! The ScattData to evaluate - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8) :: f ! Return value of f(mu) + integer, intent(in) :: gin ! Incoming Energy Group + integer, intent(in) :: gout ! Outgoing Energy Group + real(8), intent(in) :: mu ! Angle of interest + real(8) :: f ! Return value of f(mu) integer :: imu real(8) :: r @@ -357,12 +489,15 @@ contains integer :: samples xi = prn() - prob = ZERO - gout = 0 + ! Assuming highest group will be closest to the highest probability of + ! transfer (not always true, but generally so for few to multi-group + ! scenarios in all but water), so start there and go down in energy + gout = this % gmax(gin) + prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout + 1 - prob = prob + this % energy(gout,gin) + gout = gout - 1 + prob = prob + this % energy(gin) % data(gout) end do ! Now we can sample mu using the legendre representation of the thisering @@ -403,12 +538,15 @@ contains integer :: imu xi = prn() - prob = ZERO - gout = 0 + ! Assuming highest group will be closest to the highest probability of + ! transfer (not always true, but generally so for few to multi-group + ! scenarios in all but water), so start there and go down in energy + gout = this % gmax(gin) + prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout + 1 - prob = prob + this % energy(gout,gin) + gout = gout - 1 + prob = prob + this % energy(gin) % data(gout) end do xi = prn() @@ -440,12 +578,15 @@ contains integer :: k, NP xi = prn() - prob = ZERO - gout = 0 + ! Assuming highest group will be closest to the highest probability of + ! transfer (not always true, but generally so for few to multi-group + ! scenarios in all but water), so start there and go down in energy + gout = this % gmax(gin) + prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout + 1 - prob = prob + this % energy(gout,gin) + gout = gout - 1 + prob = prob + this % energy(gin) % data(gout) end do ! determine outgoing cosine bin From d1baa3bae7f5ede66e14ce655521baea4e896f31 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 5 Mar 2016 09:41:15 -0500 Subject: [PATCH 002/147] Removed GroupTransfer and OutgoingTransfer code as I no longer need it. Changed outgoing energy pdf checking from top-down to bottom-up counting. --- src/scattdata_header.F90 | 113 +++------------------------------------ 1 file changed, 6 insertions(+), 107 deletions(-) diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 8dc64a653..14e049f7f 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -22,35 +22,6 @@ module scattdata_header end type Jagged1D -!=============================================================================== -! OUTGOINGTRANSFER contains sparse outgoing scattering matrices for a single -! incoming group -!=============================================================================== - - type OutgoingTransfer - real(8), allocatable :: data(:,:) ! Outgoing transfer probabilities - ! Dimension of (moments, gmin:gmax) - integer :: gmin - integer :: gmax - contains - ! Initialize OutgoingTransfer given a dense (GoutxL) matrix - procedure:: init => outgoingtransfer_init - end type OutgoingTransfer - - -!=============================================================================== -! GROUPTRANSFER contains sparse outgoing scattering matrices for all -! incoming groups -!=============================================================================== - - type GroupTransfer - type(OutgoingTransfer), allocatable :: outgoing(:) ! Outgoing transfer probabilities - contains - ! Initialize GroupTransfer given a dense (GinxGoutxL) matrix - procedure:: init => grouptransfer_init - end type GroupTransfer - - !=============================================================================== ! SCATTDATA contains all the data to describe the scattering energy and ! angular distribution @@ -138,69 +109,6 @@ module scattdata_header contains -!=============================================================================== -! GROUPTRANSFER_INIT builds the OutgoingTransfer object given a dense scattering -! matrix of (GoutxL) dimensionality. -!=============================================================================== - - subroutine grouptransfer_init(this, dense) - class(GroupTransfer), intent(inout) :: this ! Object to Initialize - real(8), intent(in) :: dense(:,:,:) ! Source Dense Matrix of - ! (GinxGoutxL) dims. - - integer :: gin, groups - - groups = size(dense,dim=1) - allocate(this % outgoing(groups)) - do gin = 1, groups - call this % outgoing(gin) % init(dense(gin,:,:),gin) - end do - - end subroutine grouptransfer_init - - -!=============================================================================== -! OUTGOINGTRANSFER_INIT builds the OutgoingTransfer object given a dense scattering -! matrix of (GoutxL) dimensionality. -!=============================================================================== - - subroutine outgoingtransfer_init(this, dense, gin) - class(OutgoingTransfer), intent(inout) :: this ! Object to Initialize - real(8), intent(in) :: dense(:,:) ! Source Dense Matrix of - ! (GoutxL) dims. - integer, intent(in) :: gin ! Incoming group - - integer :: groups, order, gmin, gmax, gout, l - - groups = size(dense,dim=1) - order = size(dense,dim=2) - - ! Find gmin by checking the P0 moment - do gmin = 1, groups - if (dense(gmin,1) > ZERO) exit - end do - ! Find gmax by checking the P0 moment - do gmax = groups, 1, -1 - if (dense(gmax,1) > ZERO) exit - end do - ! Treat the case of all zeros - if (gmin > gmax) then - gmin = gin - gmax = gin - end if - - ! Now we can allocate our OutgoingTransfer object and place data - allocate(this % data(order, gmin:gmax)) - do gout = gmin, gmax - do l = 1, order - this % data(l,gout) = dense(gout,l) - end do - end do - this % gmin = gmin - this % gmax = gmax - - end subroutine outgoingtransfer_init - !=============================================================================== ! SCATTDATA_INIT builds the scattdata object !=============================================================================== @@ -489,14 +397,11 @@ contains integer :: samples xi = prn() - ! Assuming highest group will be closest to the highest probability of - ! transfer (not always true, but generally so for few to multi-group - ! scenarios in all but water), so start there and go down in energy - gout = this % gmax(gin) + gout = this % gmin(gin) prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout - 1 + gout = gout + 1 prob = prob + this % energy(gin) % data(gout) end do @@ -538,14 +443,11 @@ contains integer :: imu xi = prn() - ! Assuming highest group will be closest to the highest probability of - ! transfer (not always true, but generally so for few to multi-group - ! scenarios in all but water), so start there and go down in energy - gout = this % gmax(gin) + gout = this % gmin(gin) prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout - 1 + gout = gout + 1 prob = prob + this % energy(gin) % data(gout) end do @@ -578,14 +480,11 @@ contains integer :: k, NP xi = prn() - ! Assuming highest group will be closest to the highest probability of - ! transfer (not always true, but generally so for few to multi-group - ! scenarios in all but water), so start there and go down in energy - gout = this % gmax(gin) + gout = this % gmin(gin) prob = this % energy(gin) % data(gout) do while (prob < xi) - gout = gout - 1 + gout = gout + 1 prob = prob + this % energy(gin) % data(gout) end do From 812153a11416943c2f1a62eb5857df17030e01eb Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 5 Mar 2016 10:26:40 -0500 Subject: [PATCH 003/147] Revised all relevant data within scattdata classes to utilize a sparse format. Testing in progress --- src/macroxs_header.F90 | 8 +- src/scattdata_header.F90 | 218 +++++++++++++++++++++------------------ 2 files changed, 120 insertions(+), 106 deletions(-) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index 2a1234510..233832d6f 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -701,9 +701,9 @@ contains xs = this % scattxs(g) case('mult') if (present(gout)) then - xs = this % scatter % mult(gout,g) + xs = this % scatter % mult(g) % data(gout) else - xs = sum(this % scatter % mult(:,g)) + xs = sum(this % scatter % mult(g) % data(:)) end if end select @@ -736,9 +736,9 @@ contains xs = this % scattxs(g,iazi,ipol) case('mult') if (present(gout)) then - xs = this % scatter(iazi,ipol) % obj % mult(gout,g) + xs = this % scatter(iazi,ipol) % obj % mult(g) % data(gout) else - xs = sum(this % scatter(iazi,ipol) % obj % mult(:,g)) + xs = sum(this % scatter(iazi,ipol) % obj % mult(g) % data(:)) end if end select end if diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 14e049f7f..54b9e14f1 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -28,10 +28,12 @@ module scattdata_header !=============================================================================== type, abstract :: ScattData - ! p0 matrix on its own for sampling energy + ! normalized p0 matrix on its own for sampling energy type(Jagged1D), allocatable :: energy(:) ! (Gin % data(Gout)) - real(8), allocatable :: mult(:,:) ! (Gout x Gin) - real(8), allocatable :: data(:,:,:) ! (Order/Nmu x Gout x Gin) + ! nu-scatter multiplication (i.e. nu-scatt/scatt) + type(Jagged1D), allocatable :: mult(:) ! (Gin % data(Gout)) + ! Angular distribution + type(Jagged2D), allocatable :: dist(:) ! (Gin % data(Order/Nmu x Gout) integer, allocatable :: gmin(:) ! Minimum outgoing group integer, allocatable :: gmax(:) ! Maximum outgoing group @@ -73,7 +75,7 @@ module scattdata_header type, extends(ScattData) :: ScattDataLegendre ! Maximal value for rejection sampling from rectangle - real(8), allocatable :: max_val(:,:) + type(Jagged1D), allocatable :: max_val(:) ! (Gin % data(Gout)) contains procedure :: init => scattdatalegendre_init procedure :: calc_f => scattdatalegendre_calc_f @@ -90,9 +92,10 @@ module scattdata_header end type ScattDataHistogram type, extends(ScattData) :: ScattDataTabular - real(8), allocatable :: mu(:) ! Mu bins - real(8) :: dmu ! Mu spacing - real(8), allocatable :: fmu(:,:,:) ! PDF of f(mu) + real(8), allocatable :: mu(:) ! Mu bins + real(8) :: dmu ! Mu spacing + ! PDF of f(mu) + type(Jagged2D), allocatable :: fmu(:) ! (Gin % data(Order/Nmu x Gout) contains procedure :: init => scattdatatabular_init procedure :: calc_f => scattdatatabular_calc_f @@ -126,6 +129,8 @@ contains allocate(this % gmin(groups)) allocate(this % gmax(groups)) allocate(this % energy(groups)) + allocate(this % mult(groups)) + allocate(this % dist(groups)) ! Use energy to find the gmin and gmax values ! Also set energy values when doing it do gin = 1, groups @@ -145,15 +150,14 @@ contains end if allocate(this % energy(gin) % data(gmin:gmax)) this % energy(gin) % data(gmin:gmax) = energy(gmin:gmax,gin) + allocate(this % mult(gin) % data(gmin:gmax)) + this % mult(gin) % data(gmin:gmax) = mult(gmin:gmax,gin) + allocate(this % dist(gin) % data(order,gmin:gmax)) + this % dist(gin) % data = ZERO this % gmin(gin) = gmin this % gmax(gin) = gmax end do - allocate(this % mult(groups, groups)) - this % mult = mult - allocate(this % data(order, groups, groups)) - this % data = ZERO - end subroutine scattdata_init subroutine scattdatalegendre_init(this, order, energy, mult, coeffs) @@ -168,37 +172,43 @@ contains call scattdata_init(this, order, energy, mult) - this % data = coeffs - groups = size(this % energy,dim=1) - allocate(this % max_val(groups, groups)) - this % max_val = ZERO + allocate(this % max_val(groups)) + ! Set dist values from coeffs and initialize max_val + do gin = 1, groups + this % dist(gin) % data(:,this % gmin(gin):this % gmax(gin)) = & + coeffs(:,this % gmin(gin):this % gmax(gin),gin) + allocate(this % max_val(gin) % data(this % gmin(gin):this % gmax(gin))) + this % max_val(gin) % data = ZERO + end do + ! Step through the polynomial with fixed number of points to identify ! the maximal value. Nmu = 1001 dmu = TWO / real(Nmu,8) - do imu = 1, Nmu - ! Update mu. Do first and last seperate to avoid float errors - if (imu == 1) then - mu = -ONE - else if (imu == Nmu) then - mu = ONE - end if - mu = -ONE + real(imu - 1,8) * dmu - do gin = 1, groups - do gout = 1, groups + do gin = 1, groups + do gout = this % gmin(gin), this % gmax(gin) + do imu = 1, Nmu + ! Update mu. Do first and last seperate to avoid float errors + if (imu == 1) then + mu = -ONE + else if (imu == Nmu) then + mu = ONE + else + mu = -ONE + real(imu - 1,8) * dmu + end if ! Calculate probability f = this % calc_f(gin,gout,mu) ! If this is a new max, store it. - if (f > this % max_val(gout,gin)) this % max_val(gout,gin) = f + if (f > this % max_val(gin) % data(gout)) & + this % max_val(gin) % data(gout) = f end do end do + ! Finally, since we may not have caught the exact max, add 10% margin + this % max_val(gin) % data = this % max_val(gin) % data * 1.1_8 end do - ! Finally, since we may not have caught the exact max, add 10% margin - this % max_val = this % max_val * 1.1_8 - end subroutine scattdatalegendre_init subroutine scattdatahistogram_init(this, order, energy, mult, coeffs) @@ -224,19 +234,18 @@ contains ! Best to integrate this histogram so we can avoid rejection sampling do gin = 1, groups - do gout = 1, groups - if (energy(gout,gin) > ZERO) then - ! Integrate the histogram - this % data(1,gout,gin) = this % dmu * coeffs(1,gout,gin) - do imu = 2, order - this % data(imu,gout,gin) = this % dmu * coeffs(imu,gout,gin) + & - this % data(imu-1,gout,gin) - end do - ! Now make sure integral norms to zero - norm = this % data(order,gout,gin) - if (norm > ZERO) then - this % data(:,gout,gin) = this % data(:,gout,gin) / norm - end if + do gout = this % gmin(gin), this % gmax(gin) + ! Integrate the histogram + this % dist(gin) % data(1,gout) = this % dmu * coeffs(1,gout,gin) + do imu = 2, order + this % dist(gin) % data(imu,gout) = this % dmu * coeffs(imu,gout,gin) + & + this % dist(gin) % data(imu - 1,gout) + end do + ! Now make sure integral norms to zero + norm = this % dist(gin) % data(order,gout) + if (norm > ZERO) then + this % dist(gin) % data(:,gout) = & + this % dist(gin) % data(:,gout) / norm end if end do end do @@ -274,46 +283,51 @@ contains end do this % mu(this_order) = ONE - ! Best to integrate this histogram so we can avoid rejection sampling - allocate(this % fmu(this_order,groups,groups)) + ! Calculate f(mu) and integrate it so we can avoid rejection sampling + allocate(this % fmu(groups)) do gin = 1, groups - do gout = 1, groups - if (energy(gout,gin) > ZERO) then - if (legendre_flag) then - ! Coeffs are legendre coeffs. Need to build f(mu) then integrate - ! and store the integral in this % data - ! Ensure the coeffs are normalized - norm = ONE / coeffs(1,gout,gin) - do imu = 1, this_order - this % fmu(imu,gout,gin) = evaluate_legendre(norm * coeffs(:,gout,gin), this % mu(imu)) - ! Force positivity - if (this % fmu(imu,gout,gin) < ZERO) then - this % fmu(imu,gout,gin) = ZERO - end if - end do - else - ! Coeffs contain f(mu), put in f(mu) to save duplicate. - this % fmu(:,gout,gin) = this % data(:,gout,gin) - end if - - ! Re-normalize fmu for numerical integration issues and in case - ! the negative fix-up introduced un-normalized data - norm = ZERO - do imu = 2, this_order - norm = norm + HALF * this % dmu * (this % fmu(imu-1,gout,gin) + this % fmu(imu,gout,gin)) + do gout = this % gmin(gin), this % gmax(gin) + allocate(this % fmu(gin) % data(this_order,& + this % gmin(gin):this % gmax(gin))) + if (legendre_flag) then + ! Coeffs are legendre coeffs. Need to build f(mu) then integrate + ! and store the integral in this % dist + ! Ensure the coeffs are normalized + norm = ONE / coeffs(1,gout,gin) + do imu = 1, this_order + this % fmu(gin) % data(imu,gout) = evaluate_legendre(norm * coeffs(:,gout,gin), this % mu(imu)) + ! Force positivity + if (this % fmu(gin) % data(imu,gout) < ZERO) then + this % fmu(gin) % data(imu,gout) = ZERO + end if end do - if (norm > ZERO) then - this % fmu(:,gout,gin) = this % fmu(:,gout,gin) / norm - end if - - ! Now create CDF from fmu with trapezoidal rule - this % data(1,gout,gin) = ZERO - do imu = 2, this_order - 1 - this % data(imu,gout,gin) = this % data(imu-1,gout,gin) + & - HALF * this % dmu * (this % fmu(imu-1,gout,gin) + this % fmu(imu,gout,gin)) - end do - this % data(this_order,gout,gin) = ONE + else + ! Coeffs contain f(mu), put in f(mu) as that is where the + ! PDF lives + this % fmu(gin) % data(:,gout) = this % dist(gin) % data(:,gout) end if + + ! Re-normalize fmu for numerical integration issues and in case + ! the negative fix-up introduced un-normalized data + norm = ZERO + do imu = 2, this_order + norm = norm + HALF * this % dmu * & + (this % fmu(gin) % data(imu - 1,gout) + & + this % fmu(gin) % data(imu,gout)) + end do + if (norm > ZERO) then + this % fmu(gin) % data(:,gout) = this % fmu(gin) % data(:,gout) / norm + end if + + ! Now create CDF from fmu with trapezoidal rule + this % dist(gin) % data(1,gout) = ZERO + do imu = 2, this_order - 1 + this % dist(gin) % data(imu,gout) = & + this % dist(gin) % data(imu - 1,gout) + & + HALF * this % dmu * (this % fmu(gin) % data(imu - 1,gout) + & + this % fmu(gin) % data(imu,gout)) + end do + this % dist(gin) % data(this_order,gout) = ONE end do end do @@ -331,7 +345,7 @@ contains real(8) :: f ! Return value of f(mu) ! Plug mu in to the legendre expansion and go from there - f = evaluate_legendre(this % data(:, gout, gin), mu) + f = evaluate_legendre(this % dist(gin) % data(:,gout),mu) end function scattdatalegendre_calc_f @@ -347,12 +361,12 @@ contains ! Find mu bin imu = floor((mu + ONE)/ this % dmu + ONE) ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % data, dim=1)) then + if (imu == size(this % dist, dim=1)) then imu = imu - 1 end if ! Use histogram interpolation to find f(mu) - f = this % data(imu, gout, gin) + f = this % dist(gin) % data(imu,gout) end function scattdatahistogram_calc_f @@ -369,14 +383,14 @@ contains ! Find mu bin imu = floor((mu + ONE)/ this % dmu + ONE) ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % data, dim=1)) then + if (imu == size(this % dist, dim=1)) then imu = imu - 1 end if - ! ! Now interpolate to find f(mu) + ! Now interpolate to find f(mu) r = (mu - this % mu(imu)) / (this % mu(imu + 1) - this % mu(imu)) - f = (ONE - r) * this % data(imu, gout, gin) + & - r * this % data(imu + 1, gout, gin) + f = (ONE - r) * this % dist(gin) % data(imu,gout) + & + r * this % dist(gin) % data(imu + 1,gout) end function scattdatatabular_calc_f @@ -405,12 +419,12 @@ contains prob = prob + this % energy(gin) % data(gout) end do - ! Now we can sample mu using the legendre representation of the thisering + ! Now we can sample mu using the legendre representation of the scattering ! kernel in data(1:this % order) ! Do with rejection sampling ! Set maximal value - M = this % max_val(gout,gin) + M = this % max_val(gin) % data(gout) samples = 0 do mu = TWO * prn() - ONE @@ -427,7 +441,7 @@ contains end if end do - wgt = wgt * this % mult(gout,gin) + wgt = wgt * this % mult(gin) % data(gout) end subroutine scattdatalegendre_sample @@ -452,17 +466,17 @@ contains end do xi = prn() - if (xi < this % data(1,gout,gin)) then + if (xi < this % dist(gin) % data(1,gout)) then imu = 1 else - imu = binary_search(this % data(:,gout,gin), & - size(this % data(:,gout,gin)), xi) + imu = binary_search(this % dist(gin) % data(:,gout), & + size(this % dist(gin) % data(:,gout)), xi) end if ! Randomly select a mu in this bin. mu = prn() * this % dmu + this % mu(imu) - wgt = wgt * this % mult(gout,gin) + wgt = wgt * this % mult(gin) % data(gout) end subroutine scattdatahistogram_sample @@ -489,12 +503,12 @@ contains end do ! determine outgoing cosine bin - NP = size(this % data(:,gout,gin)) + NP = size(this % dist(gin) % data(:,gout)) xi = prn() - c_k = this % data(1,gout,gin) + c_k = this % dist(gin) % data(1,gout) do k = 1, NP - 1 - c_k1 = this % data(k+1,gout,gin) + c_k1 = this % dist(gin) % data(k + 1,gout) if (xi < c_k1) exit c_k = c_k1 end do @@ -502,18 +516,18 @@ contains ! check to make sure k is <= NP - 1 k = min(k, NP - 1) - p0 = this % fmu(k,gout,gin) + p0 = this % fmu(gin) % data(k,gout) mu0 = this % mu(k) ! Linear-linear interpolation to find mu value w/in bin. - p1 = this % fmu(k+1,gout,gin) - mu1 = this % mu(k+1) + p0 = this % fmu(gin) % data(k + 1,gout) + mu1 = this % mu(k + 1) frac = (p1 - p0)/(mu1 - mu0) if (frac == ZERO) then mu = mu0 + (xi - c_k)/p0 else - mu = mu0 + (sqrt(max(ZERO, p0*p0 + TWO*frac*(xi - c_k))) - p0)/frac + mu = mu0 + (sqrt(max(ZERO, p0 * p0 + TWO * frac * (xi - c_k))) - p0) / frac end if if (mu <= -ONE) then @@ -522,7 +536,7 @@ contains mu = ONE end if - wgt = wgt * this % mult(gout,gin) + wgt = wgt * this % mult(gin) % data(gout) end subroutine scattdatatabular_sample From 1705e0c7df68a9f284a5ed56928ce1c8fd098c60 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 5 Mar 2016 13:09:56 -0500 Subject: [PATCH 004/147] Bug fixes after testing --- src/scattdata_header.F90 | 26 ++++++++++++++++---------- 1 file changed, 16 insertions(+), 10 deletions(-) diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 54b9e14f1..46b1de826 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -21,7 +21,6 @@ module scattdata_header real(8), allocatable :: data(:) end type Jagged1D - !=============================================================================== ! SCATTDATA contains all the data to describe the scattering energy and ! angular distribution @@ -177,8 +176,9 @@ contains allocate(this % max_val(groups)) ! Set dist values from coeffs and initialize max_val do gin = 1, groups - this % dist(gin) % data(:,this % gmin(gin):this % gmax(gin)) = & - coeffs(:,this % gmin(gin):this % gmax(gin),gin) + do gout = this % gmin(gin), this % gmax(gin) + this % dist(gin) % data(:,gout) = coeffs(:,gout,gin) + end do allocate(this % max_val(gin) % data(this % gmin(gin):this % gmax(gin))) this % max_val(gin) % data = ZERO end do @@ -278,7 +278,8 @@ contains allocate(this % mu(this_order)) this % dmu = TWO / real(this_order - 1) - do imu = 1, this_order - 1 + this % mu = -ONE + do imu = 2, this_order - 1 this % mu(imu) = -ONE + real(imu - 1) * this % dmu end do this % mu(this_order) = ONE @@ -286,16 +287,21 @@ contains ! Calculate f(mu) and integrate it so we can avoid rejection sampling allocate(this % fmu(groups)) do gin = 1, groups - do gout = this % gmin(gin), this % gmax(gin) - allocate(this % fmu(gin) % data(this_order,& + allocate(this % fmu(gin) % data(this_order,& this % gmin(gin):this % gmax(gin))) + do gout = this % gmin(gin), this % gmax(gin) if (legendre_flag) then ! Coeffs are legendre coeffs. Need to build f(mu) then integrate ! and store the integral in this % dist ! Ensure the coeffs are normalized - norm = ONE / coeffs(1,gout,gin) + if (coeffs(1,gout,gin) /= ZERO) then + norm = ONE / coeffs(1,gout,gin) + else + norm = ONE + end if do imu = 1, this_order - this % fmu(gin) % data(imu,gout) = evaluate_legendre(norm * coeffs(:,gout,gin), this % mu(imu)) + this % fmu(gin) % data(imu,gout) = & + evaluate_legendre(norm * coeffs(:,gout,gin), this % mu(imu)) ! Force positivity if (this % fmu(gin) % data(imu,gout) < ZERO) then this % fmu(gin) % data(imu,gout) = ZERO @@ -422,7 +428,7 @@ contains ! Now we can sample mu using the legendre representation of the scattering ! kernel in data(1:this % order) - ! Do with rejection sampling + ! Do with rejection sampling from a rectangular bounding box ! Set maximal value M = this % max_val(gin) % data(gout) samples = 0 @@ -519,7 +525,7 @@ contains p0 = this % fmu(gin) % data(k,gout) mu0 = this % mu(k) ! Linear-linear interpolation to find mu value w/in bin. - p0 = this % fmu(gin) % data(k + 1,gout) + p1 = this % fmu(gin) % data(k + 1,gout) mu1 = this % mu(k + 1) frac = (p1 - p0)/(mu1 - mu0) From 92e1794b43152cd31a60b156cffe12cb7a30921b Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 5 Mar 2016 13:50:34 -0500 Subject: [PATCH 005/147] Ok, all bug fixes incorporated, now this method matches what was in the original (after fixing a minor bug in the original which was of no statistical consequence --- src/scattdata_header.F90 | 5 +++-- 1 file changed, 3 insertions(+), 2 deletions(-) diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 46b1de826..949bd8707 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -204,9 +204,10 @@ contains if (f > this % max_val(gin) % data(gout)) & this % max_val(gin) % data(gout) = f end do + ! Finally, since we may not have caught the exact max, add 10% margin + this % max_val(gin) % data(gout) = & + this % max_val(gin) % data(gout) * 1.1_8 end do - ! Finally, since we may not have caught the exact max, add 10% margin - this % max_val(gin) % data = this % max_val(gin) % data * 1.1_8 end do end subroutine scattdatalegendre_init From 3f3a1aa125c7696681dbc29e57c0591b3709fae1 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Mon, 7 Mar 2016 12:29:36 -0500 Subject: [PATCH 006/147] Cleaning up of code so that nuclide and macroxs use scattdata and use it efficiently and sensically. Also found a few trivially small bugs along the way (mu values being off slightly in calculation of f(mu), for example --- src/input_xml.F90 | 2 +- src/macroxs_header.F90 | 351 ++++++++-------------- src/mgxs_data.F90 | 12 +- src/nuclide_header.F90 | 622 ++++++++++++++++++++------------------- src/scattdata_header.F90 | 291 ++++++++++++------ 5 files changed, 633 insertions(+), 645 deletions(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 03ef8dcbc..b89b8807f 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -170,7 +170,7 @@ contains call get_node_value(doc, "max_order", max_order) else ! Set to default of largest int, which means to use whatever is contained in library - max_order = huge(0) + max_order = huge(0) - 1 end if else max_order = 0 diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index 233832d6f..d32cde96e 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -1,6 +1,7 @@ module macroxs_header use constants, only: MAX_FILE_LEN, ZERO, ONE, TWO, PI + use error, only: fatal_error use list_header, only: ListInt use material_header, only: material use math, only: calc_pn, calc_rn, expand_harmonic, find_angle @@ -32,8 +33,7 @@ module macroxs_header abstract interface subroutine macroxs_init_(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type, legendre_mu_points, & - error_code, error_text) + max_order, scatt_type) import MacroXS, Material, NuclideMGContainer, MAX_LINE_LEN class(MacroXS), intent(inout) :: this ! The MacroXS to initialize type(Material), pointer, intent(in) :: mat ! base material @@ -43,9 +43,6 @@ module macroxs_header logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? - integer, intent(in) :: legendre_mu_points ! Treat as Leg or Tabular? - integer, intent(inout) :: error_code ! Code signifying error - character(MAX_LINE_LEN), intent(inout) :: error_text ! Error message to print end subroutine macroxs_init_ function macroxs_get_xs_(this, g, xstype, gout, uvw) result(xs) @@ -94,7 +91,6 @@ module macroxs_header real(8), allocatable :: nu_fission(:) ! nu-fission real(8), allocatable :: k_fission(:) ! kappa-fission real(8), allocatable :: fission(:) ! fission x/s - real(8), allocatable :: scattxs(:) ! scattering xs real(8), allocatable :: chi(:,:) ! fission spectra contains @@ -114,7 +110,6 @@ module macroxs_header real(8), allocatable :: k_fission(:,:,:) ! kappa-fission real(8), allocatable :: fission(:,:,:) ! fission x/s real(8), allocatable :: chi(:,:,:,:) ! fission spectra - real(8), allocatable :: scattxs(:,:,:) ! scattering xs real(8), allocatable :: polar(:) ! polar angles real(8), allocatable :: azimuthal(:) ! azimuthal angles @@ -141,7 +136,7 @@ contains !=============================================================================== subroutine macroxsiso_init(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type, legendre_mu_points, error_code, error_text) + max_order, scatt_type) class(MacroXSIso), intent(inout) :: this ! The MacroXS to initialize type(Material), pointer, intent(in) :: mat ! base material type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from @@ -150,9 +145,6 @@ contains logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! How is data presented - integer, intent(in) :: legendre_mu_points ! Treat as Leg or Tabular? - integer, intent(inout) :: error_code ! Code signifying error - character(MAX_LINE_LEN), intent(inout) :: error_text ! Error message to print integer :: i ! loop index over nuclides integer :: gin, gout ! group indices @@ -161,22 +153,15 @@ contains real(8) :: norm integer :: mat_max_order, order, l real(8), allocatable :: temp_mult(:,:) - real(8), allocatable :: temp_energy(:,:) real(8), allocatable :: scatt_coeffs(:,:,:) - ! Initialize error data - error_code = 0 - error_text = '' - ! If we have tabular only data, then make sure all datasets have same size if (scatt_type == ANGLE_HISTOGRAM) then ! Check all scattering data of same size order = nuclides(mat % nuclide(1)) % obj % order do i = 2, mat % n_nuclides if (order /= nuclides(mat % nuclide(i)) % obj % order) then - error_code = 1 - error_text = "All Histogram Scattering Entries Must Be Same Length!" - return + call fatal_error("All Histogram Scattering Entries Must Be Same Length!") end if end do ! Ok, got our order, store it @@ -192,8 +177,7 @@ contains order = nuclides(mat % nuclide(1)) % obj % order do i = 2, mat % n_nuclides if (order /= nuclides(mat % nuclide(i)) % obj % order) then - error_code = 1 - error_text = "All Tabular Scattering Entries Must Be Same Length!" + call fatal_error("All Tabular Scattering Entries Must Be Same Length!") return end if end do @@ -201,7 +185,7 @@ contains this % order = order ! Allocate stuff for later - allocate(scatt_coeffs(order, groups, groups)) + allocate(scatt_coeffs(this % order, groups, groups)) scatt_coeffs = ZERO allocate(ScattDataTabular :: this % scatter) @@ -217,17 +201,13 @@ contains ! Now need to compare this material maximum scattering order with ! the problem wide max scatt order and use whichever is lower - order = min(mat_max_order, max_order) - this % order = order + 1 + order = min(mat_max_order, max_order) + 1 + this % order = order ! Now we can allocate our scatt_coeffs object accordingly - allocate(scatt_coeffs(order + 1, groups, groups)) + allocate(scatt_coeffs(this % order, groups, groups)) scatt_coeffs = ZERO - if (legendre_mu_points == 1) then - allocate(ScattDataLegendre :: this % scatter) - else - allocate(ScattDataTabular :: this % scatter) - end if + allocate(ScattDataLegendre :: this % scatter) end if ! Allocate and initialize data within macro_xs(i_mat) object @@ -247,11 +227,8 @@ contains this % nu_fission = ZERO allocate(this % chi(groups, groups)) this % chi = ZERO - allocate(temp_energy(groups, groups)) - temp_energy = ZERO allocate(temp_mult(groups, groups)) temp_mult = ZERO - allocate(this % scattxs(groups)) ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -261,7 +238,6 @@ contains ! Perform our operations which depend upon the type select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (NuclideIso) - ! Add contributions to total, absorption, and fission data (if necessary) this % total = this % total + atom_density * nuc % total this % absorption = this % absorption + & @@ -291,81 +267,25 @@ contains end if end if - ! Now time to do the scattering + ! Get the multiplication matrix do gin = 1, groups - do gout = 1, groups - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - ! Transfer matrix - temp_energy(gout,gin) = temp_energy(gout,gin) + atom_density * & - sum(nuc % scatter(gout,gin,:)) - - ! Determine the angular distribution - do imu = 1, order - scatt_coeffs(imu, gout, gin) = scatt_coeffs(imu, gout, gin) + & - nuc % scatter(gout,gin,imu) * & - atom_density - end do - - else if (scatt_type == ANGLE_LEGENDRE) then - ! Transfer matrix - temp_energy(gout,gin) = temp_energy(gout,gin) + atom_density * & - nuc % scatter(gout,gin,1) - - ! Determine the angular distribution coefficients so we can later - ! expand do the complete distribution - do l = 1, min(nuc % order, order) + 1 - scatt_coeffs(l, gout, gin) = scatt_coeffs(l, gout, gin) + & - nuc % scatter(gout,gin,l) * & - atom_density - end do - - end if - - ! Multiplicity matrix + do gout = nuc % scatter % gmin(gin), nuc % scatter % gmax(gin) temp_mult(gout,gin) = temp_mult(gout,gin) + atom_density * & - nuc % mult(gout,gin) + nuc % scatter % mult(gin) % data(gout) end do end do + + ! Get the complete scattering matrix + scatt_coeffs(1:min(nuc % order, order),:,:) = scatt_coeffs + & + atom_density * & + nuc % scatter % get_matrix(min(nuc % order, order)) + type is (NuclideAngle) - error_code = 1 - error_text = "Invalid Passing of NuclideAngle to MacroXSIso Object" - return + call fatal_error("Invalid Passing of NuclideAngle to MacroXSIso Object") end select end do - ! Store the scattering xs - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - this % scattxs(:) = sum(sum(scatt_coeffs(:,:,:),dim=1),dim=1) - else if (scatt_type == ANGLE_LEGENDRE) then - this % scattxs(:) = sum(scatt_coeffs(1,:,:),dim=1) - end if - - ! Normalize the scatt_coeffs - do gin = 1, groups - do gout = 1, groups - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - norm = sum(scatt_coeffs(:,gout,gin)) - else if (scatt_type == ANGLE_LEGENDRE) then - norm = scatt_coeffs(1,gout,gin) - end if - if (norm /= ZERO) then - scatt_coeffs(:, gout, gin) = scatt_coeffs(:, gout,gin) / norm - end if - end do - ! Now normalize temp_energy (outgoing scattering energy probabilities) - norm = sum(temp_energy(:,gin)) - if (norm > ZERO) then - temp_energy(:,gin) = temp_energy(:,gin) / norm - end if - end do - - if (scatt_type == ANGLE_LEGENDRE .and. legendre_mu_points /= 1) then - call this % scatter % init(legendre_mu_points, temp_energy, temp_mult, & - scatt_coeffs) - else - call this % scatter % init(this % order, temp_energy, temp_mult, & - scatt_coeffs) - end if + call this % scatter % init(temp_mult,scatt_coeffs) ! Now normalize chi if (mat % fissionable) then @@ -379,12 +299,12 @@ contains end if ! Deallocate temporaries for the next material - deallocate(scatt_coeffs, temp_energy, temp_mult) + deallocate(scatt_coeffs, temp_mult) end subroutine macroxsiso_init subroutine macroxsangle_init(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type, legendre_mu_points, error_code, error_text) + max_order, scatt_type) class(MacroXSAngle), intent(inout) :: this ! The MacroXS to initialize type(Material), pointer, intent(in) :: mat ! base material type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from @@ -393,43 +313,34 @@ contains logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? - integer, intent(in) :: legendre_mu_points ! Treat as Leg or Tabular? - integer, intent(inout) :: error_code ! Code signifying error - character(MAX_LINE_LEN), intent(inout) :: error_text ! Error message to print integer :: i ! loop index over nuclides integer :: gin, gout ! group indices real(8) :: atom_density ! atom density of a nuclide - integer :: ipol, iazi, npol, nazi + integer :: ipol, iazi, n_pol, n_azi integer :: imu real(8) :: norm integer :: mat_max_order, order, l real(8), allocatable :: temp_mult(:,:,:,:) - real(8), allocatable :: temp_energy(:,:,:,:) real(8), allocatable :: scatt_coeffs(:,:,:,:,:) - ! Initialize error data - error_code = 0 - error_text = '' - ! Get the number of each polar and azi angles and make sure all the ! NuclideAngle types have the same number of these angles - npol = -1 - nazi = -1 + n_pol = -1 + n_azi = -1 do i = 1, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (NuclideAngle) - if (npol == -1) then - npol = nuc % n_pol - nazi = nuc % n_azi - allocate(this % polar(npol)) + if (n_pol == -1) then + n_pol = nuc % n_pol + n_azi = nuc % n_azi + allocate(this % polar(n_pol)) this % polar = nuc % polar - allocate(this % azimuthal(nazi)) + allocate(this % azimuthal(n_azi)) this % azimuthal = nuc % azimuthal else - if ((npol /= nuc % n_pol) .or. (nazi /= nuc % n_azi)) then - error_code = 1 - error_text = "All Angular Data Must Be Same Length!" + if ((n_pol /= nuc % n_pol) .or. (n_azi /= nuc % n_azi)) then + call fatal_error("All Angular Data Must Be Same Length!") end if end if end select @@ -441,20 +352,18 @@ contains order = nuclides(mat % nuclide(1)) % obj % order do i = 2, mat % n_nuclides if (order /= nuclides(mat % nuclide(i)) % obj % order) then - error_code = 1 - error_text = "All Histogram Scattering Entries Must Be Same Length!" - return + call fatal_error("All Histogram Scattering Entries Must Be Same Length!") end if end do ! Ok, got our order, store it this % order = order ! Allocate stuff for later - allocate(scatt_coeffs(order, groups, groups, nazi, npol)) + allocate(scatt_coeffs(this % order,groups,groups,n_azi,n_pol)) scatt_coeffs = ZERO - allocate(this % scatter(nazi, npol)) - do ipol = 1, npol - do iazi = 1, nazi + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi allocate(ScattDataHistogram :: this % scatter(iazi, ipol) % obj) end do end do @@ -464,20 +373,18 @@ contains order = nuclides(mat % nuclide(1)) % obj % order do i = 2, mat % n_nuclides if (order /= nuclides(mat % nuclide(i)) % obj % order) then - error_code = 1 - error_text = "All Tabular Scattering Entries Must Be Same Length!" - return + call fatal_error("All Tabular Scattering Entries Must Be Same Length!") end if end do ! Ok, got our order, store it this % order = order ! Allocate stuff for later - allocate(scatt_coeffs(order, groups, groups, nazi, npol)) + allocate(scatt_coeffs(this % order, groups, groups, n_azi, n_pol)) scatt_coeffs = ZERO - allocate(this % scatter(nazi, npol)) - do ipol = 1, npol - do iazi = 1, nazi + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi allocate(ScattDataTabular :: this % scatter(iazi, ipol) % obj) end do end do @@ -498,42 +405,35 @@ contains this % order = order + 1 ! Now we can allocate our scatt_coeffs object accordingly - allocate(scatt_coeffs(order + 1, groups, groups, nazi, npol)) + allocate(scatt_coeffs(this % order, groups, groups, n_azi, n_pol)) scatt_coeffs = ZERO - allocate(this % scatter(nazi, npol)) - do ipol = 1, npol - do iazi = 1, nazi - if (legendre_mu_points == 1) then - allocate(ScattDataLegendre :: this % scatter(iazi, ipol) % obj) - else - allocate(ScattDataTabular :: this % scatter(iazi, ipol) % obj) - end if + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi + allocate(ScattDataLegendre :: this % scatter(iazi, ipol) % obj) end do end do end if ! Allocate and initialize data within macro_xs(i_mat) object - allocate(this % total(groups,nazi,npol)) + allocate(this % total(groups,n_azi,n_pol)) this % total = ZERO - allocate(this % absorption(groups,nazi,npol)) + allocate(this % absorption(groups,n_azi,n_pol)) this % absorption = ZERO if (get_fiss) then - allocate(this % fission(groups,nazi,npol)) + allocate(this % fission(groups,n_azi,n_pol)) this % fission = ZERO end if if (get_kfiss) then - allocate(this % k_fission(groups,nazi,npol)) + allocate(this % k_fission(groups,n_azi,n_pol)) this % k_fission = ZERO end if - allocate(this % nu_fission(groups,nazi,npol)) + allocate(this % nu_fission(groups,n_azi,n_pol)) this % nu_fission = ZERO - allocate(this % chi(groups, groups, nazi, npol)) + allocate(this % chi(groups, groups, n_azi, n_pol)) this % chi = ZERO - allocate(temp_energy(groups,groups,nazi,npol)) - temp_energy = ZERO - allocate(temp_mult(groups,groups,nazi,npol)) + allocate(temp_mult(groups,groups,n_azi,n_pol)) temp_mult = ZERO - allocate(this % scattxs(groups,nazi,npol)) ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -543,9 +443,7 @@ contains ! Perform our operations which depend upon the type select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (NuclideIso) - error_code = 1 - error_text = "Invalid Passing of NuclideIso to MacroXSAngle Object" - return + call fatal_error("Invalid Passing of NuclideIso to MacroXSAngle Object") type is (NuclideAngle) ! Add contributions to total, absorption, and fission data (if necessary) this % total = this % total + atom_density * nuc % total @@ -577,87 +475,70 @@ contains end if ! Now time to do the scattering - do gin = 1, groups - do gout = 1, groups - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - ! Transfer matrix - temp_energy(gout,gin,:,:) = temp_energy(gout,gin,:,:) + atom_density * & - sum(nuc % scatter(gout,gin,:,:,:),dim=1) + do ipol = 1, n_pol + do iazi = 1, n_azi + do gin = 1, groups +!!! Needs to be updated to match iso!!! +! this % scattxs(gin,iazi,ipol) = this % scattxs(gin,iazi,ipol) + & +! atom_density * nuc % scattxs(gin,iazi,ipol) + do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & + nuc % scatter(iazi,ipol) % obj % gmax(gin) - ! Determine the angular distribution - do imu = 1, order - scatt_coeffs(imu,gout,gin,:,:) = scatt_coeffs(imu,gout,gin,:,:) + & - nuc % scatter(gout,gin,imu,:,:) * & - atom_density + ! Multiplicity matrix + temp_mult(gout,gin,iazi,ipol) = & + temp_mult(gout,gin,iazi,ipol) + atom_density * & + nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + + if (scatt_type == ANGLE_HISTOGRAM) then + ! Determine the angular distribution + do imu = 1, order + scatt_coeffs(imu,gout,gin,iazi,ipol) = & + scatt_coeffs(imu,gout,gin,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % dist(gin) % data(imu,gout) + end do + else if (scatt_type == ANGLE_TABULAR) then + select type(scatt =>nuc % scatter(iazi,ipol) % obj) + type is (ScattDataTabular) + do imu = 1, order + scatt_coeffs(imu,gout,gin,iazi,ipol) = & + scatt_coeffs(imu,gout,gin,iazi,ipol) + & + atom_density * scatt % fmu(gin) % data(imu,gout) + end do + end select + else if (scatt_type == ANGLE_LEGENDRE) then + ! Determine the angular distribution coefficients so we can later + ! expand do the complete distribution + do l = 1, min(nuc % order, order) + 1 + scatt_coeffs(l,gout,gin,iazi,ipol) = & + scatt_coeffs(l,gout,gin,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % dist(gin) % data(l,gout) + end do + end if + ! Incorporate outgoing energy PDF information + scatt_coeffs(:,gout,gin,iazi,ipol) = & + scatt_coeffs(:,gout,gin,iazi,ipol) * & + nuc % scatter(iazi,ipol) % obj % energy(gin) % data(gout) end do - else if (scatt_type == ANGLE_LEGENDRE) then - ! Transfer matrix - temp_energy(gout,gin,:,:) = temp_energy(gout,gin,:,:) + atom_density * & - nuc % scatter(gout,gin,1,:,:) - - ! Determine the angular distribution coefficients so we can later - ! expand do the complete distribution - do l = 1, min(nuc % order, order) + 1 - scatt_coeffs(l, gout, gin,:,:) = scatt_coeffs(l, gout, gin,:,:) + & - nuc % scatter(gout,gin,l,:,:) * & - atom_density - end do - end if - - ! Multiplicity matrix - temp_mult(gout,gin,:,:) = temp_mult(gout,gin,:,:) + atom_density * & - nuc % mult(gout,gin,:,:) + end do end do end do end select end do - ! Store the scattering xs - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - this % scattxs(:,:,:) = sum(sum(scatt_coeffs(:,:,:,:,:),dim=1),dim=1) - else if (scatt_type == ANGLE_LEGENDRE) then - this % scattxs(:,:,:) = sum(scatt_coeffs(1,:,:,:,:),dim=1) - end if - - ! Normalize the scatt_coeffs - do ipol = 1, npol - do iazi = 1, nazi - do gin = 1, groups - do gout = 1, groups - if (scatt_type == ANGLE_HISTOGRAM .or. scatt_type == ANGLE_TABULAR) then - norm = sum(scatt_coeffs(:,gout,gin,iazi,ipol)) - else if (scatt_type == ANGLE_LEGENDRE) then - norm = scatt_coeffs(1,gout,gin,iazi,ipol) - end if - if (norm /= ZERO) then - scatt_coeffs(:,gout,gin,iazi,ipol) = & - scatt_coeffs(:,gout,gin,iazi,ipol) / norm - end if - end do - ! Now normalize temp_energy (outgoing scattering energy probabilities) - norm = sum(temp_energy(:,gin,iazi,ipol)) - if (norm > ZERO) then - temp_energy(:,gin,iazi,ipol) = temp_energy(:,gin,iazi,ipol) / norm - end if - end do - - if (scatt_type == ANGLE_LEGENDRE .and. legendre_mu_points /= 1) then - call this % scatter(iazi, ipol) % obj % init(legendre_mu_points, & - temp_energy(:,:,iazi,ipol), temp_mult(:,:,iazi,ipol), & - scatt_coeffs(:,:,:,iazi,ipol)) - else - call this % scatter(iazi, ipol) % obj % init(this % order, & - temp_energy(:,:,iazi,ipol), temp_mult(:,:,iazi,ipol), & - scatt_coeffs(:,:,:,iazi,ipol)) - end if - + ! Initialize the scattering data + do ipol = 1, n_pol + do iazi = 1, n_azi + call this % scatter(iazi, ipol) % obj % init( & + temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) end do end do ! Now go through and normalize chi if (mat % fissionable) then - do ipol = 1, npol - do iazi = 1, nazi + do ipol = 1, n_pol + do iazi = 1, n_azi do gin = 1, groups ! Normalize Chi norm = sum(this % chi(:,gin,iazi,ipol)) @@ -670,7 +551,7 @@ contains end if ! Deallocate temporaries for the next material - deallocate(scatt_coeffs, temp_energy, temp_mult) + deallocate(scatt_coeffs, temp_mult) end subroutine macroxsangle_init @@ -698,7 +579,7 @@ contains case('nu_fission') xs = this % nu_fission(g) case('scatter') - xs = this % scattxs(g) + xs = this % scatter % scattxs(g) case('mult') if (present(gout)) then xs = this % scatter % mult(g) % data(gout) @@ -733,7 +614,7 @@ contains case('nu_fission') xs = this % nu_fission(g,iazi,ipol) case('scatter') - xs = this % scattxs(g,iazi,ipol) + xs = this % scatter(iazi,ipol) % obj % scattxs(g) case('mult') if (present(gout)) then xs = this % scatter(iazi,ipol) % obj % mult(g) % data(gout) @@ -835,7 +716,7 @@ contains type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data xs % total = this % total(gin) - xs % elastic = this % scattxs(gin) + xs % elastic = this % scatter % scattxs(gin) xs % absorption = this % absorption(gin) xs % nu_fission = this % nu_fission(gin) @@ -850,10 +731,10 @@ contains integer :: iazi, ipol call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - xs % total = this % total(gin, iazi, ipol) - xs % elastic = this % scattxs(gin, iazi, ipol) - xs % absorption = this % absorption(gin, iazi, ipol) - xs % nu_fission = this % nu_fission(gin, iazi, ipol) + xs % total = this % total(gin,iazi,ipol) + xs % elastic = this % scatter(iazi,ipol) % obj % scattxs(gin) + xs % absorption = this % absorption(gin,iazi,ipol) + xs % nu_fission = this % nu_fission(gin,iazi,ipol) end subroutine macroxsangle_calculate_xs diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index 796269151..b998a96d6 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -125,7 +125,7 @@ contains ! Now read in the data specific to the type we just declared call nuclides_MG(i_nuclide) % obj % init(node_xsdata, energy_groups, & - get_kfiss, get_fiss) + get_kfiss, get_fiss, max_order) ! Keep track of what listing is associated with this nuclide nuclides_MG(i_nuclide) % obj % listing = i_listing @@ -193,10 +193,7 @@ contains integer :: l ! Loop over score bins type(Material), pointer :: mat ! current material logical :: get_kfiss, get_fiss - integer :: error_code - character(MAX_LINE_LEN) :: error_text integer :: scatt_type - integer :: legendre_mu_points ! Find out if we need fission & kappa fission ! (i.e., are there any SCORE_FISSION or SCORE_KAPPA_FISSION tallies?) @@ -225,7 +222,6 @@ contains ! Therefore type(nuclides(mat % nuclide(1)) % obj) dictates type(macroxs) ! At the same time, we will find the scattering type, as that will dictate ! how we allocate the scatter object within macroxs - legendre_mu_points = nuclides_MG(mat % nuclide(1)) % obj % legendre_mu_points scatt_type = nuclides_MG(mat % nuclide(1)) % obj % scatt_type select type(nuc => nuclides_MG(mat % nuclide(1)) % obj) type is (NuclideIso) @@ -233,13 +229,9 @@ contains type is (NuclideAngle) allocate(MacroXSAngle :: macro_xs(i_mat) % obj) end select - call macro_xs(i_mat) % obj % init(mat, nuclides_MG, energy_groups, & get_kfiss, get_fiss, max_order, & - scatt_type, legendre_mu_points, & - error_code, error_text) - ! Handle any errors - if (error_code /= 0) call fatal_error(trim(error_text)) + scatt_type) end do end subroutine create_macro_xs diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index 43fea77b6..88d7ce0ea 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -8,6 +8,7 @@ module nuclide_header use error, only: fatal_error use list_header, only: ListInt use math, only: evaluate_legendre, find_angle + use scattdata_header use string use xml_interface @@ -110,24 +111,22 @@ module nuclide_header integer :: order ! Order of data (Scattering for NuclideIso, ! Number of angles for all in NuclideAngle) integer :: scatt_type ! either legendre, histogram, or tabular. - integer :: legendre_mu_points ! Number of tabular points to use to represent - ! Legendre distribs, -1 if sample with the - ! Legendres themselves contains procedure(nuclidemg_init_), deferred :: init ! Initialize the data procedure(nuclidemg_get_xs_), deferred :: get_xs ! Get the requested xs - procedure(nuclidemg_calc_f_), deferred :: calc_f ! Calculates f, given mu end type NuclideMG abstract interface - subroutine nuclidemg_init_(this, node_xsdata, groups, get_kfiss, get_fiss) + subroutine nuclidemg_init_(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order) import NuclideMG, Node class(NuclideMG), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order end subroutine nuclidemg_init_ function nuclidemg_get_xs_(this, g, xstype, gout, uvw, mu, i_azi, i_pol) & @@ -168,18 +167,16 @@ module nuclide_header ! Microscopic cross sections real(8), allocatable :: total(:) ! total cross section real(8), allocatable :: absorption(:) ! absorption cross section - real(8), allocatable :: scatter(:,:,:) ! scattering information + class(ScattData), allocatable :: scatter ! scattering information real(8), allocatable :: nu_fission(:,:) ! fission matrix (Gout x Gin) real(8), allocatable :: k_fission(:) ! kappa-fission real(8), allocatable :: fission(:) ! neutron production real(8), allocatable :: chi(:) ! Fission Spectra - real(8), allocatable :: mult(:,:) ! Scatter multiplicity (Gout x Gin) contains procedure :: init => nuclideiso_init ! Initialize Nuclidic MGXS Data procedure :: print => nuclideiso_print ! Writes nuclide info procedure :: get_xs => nuclideiso_get_xs ! Gets Size of Data w/in Object - procedure :: calc_f => nuclideiso_calc_f ! Calcs f given mu end type NuclideIso !=============================================================================== @@ -192,7 +189,7 @@ module nuclide_header ! Microscopic cross sections. Dimensions are: (n_pol, n_azi, Nl, Ng, Ng) real(8), allocatable :: total(:,:,:) ! total cross section real(8), allocatable :: absorption(:,:,:) ! absorption cross section - real(8), allocatable :: scatter(:,:,:,:,:) ! scattering information + type(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information real(8), allocatable :: nu_fission(:,:,:,:) ! fission matrix (Gout x Gin) real(8), allocatable :: k_fission(:,:,:) ! kappa-fission real(8), allocatable :: fission(:,:,:) ! neutron production @@ -209,7 +206,6 @@ module nuclide_header procedure :: init => nuclideangle_init ! Initialize Nuclidic MGXS Data procedure :: print => nuclideangle_print ! Gets Size of Data w/in Object procedure :: get_xs => nuclideangle_get_xs ! Gets Size of Data w/in Object - procedure :: calc_f => nuclideangle_calc_f ! Calcs f given mu end type NuclideAngle !=============================================================================== @@ -303,9 +299,7 @@ module nuclide_header class(NuclideMG), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml - type(Node), pointer :: node_legendre_mu character(MAX_LINE_LEN) :: temp_str - logical :: enable_leg_mu ! Load the data call get_node_value(node_xsdata, "name", this % name) @@ -342,37 +336,6 @@ module nuclide_header call fatal_error("Order Must Be Provided!") end if - ! Get scattering treatment - if (check_for_node(node_xsdata, "tabular_legendre")) then - call get_node_ptr(node_xsdata, "tabular_legendre", node_legendre_mu) - if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu, "enable", temp_str) - temp_str = trim(to_lower(temp_str)) - if (temp_str == 'true' .or. temp_str == '1') then - enable_leg_mu = .true. - elseif (temp_str == 'false' .or. temp_str == '0') then - enable_leg_mu = .false. - this % legendre_mu_points = 1 - else - call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) - end if - else - enable_leg_mu = .true. - this % legendre_mu_points = 33 - end if - if (enable_leg_mu .and. & - check_for_node(node_legendre_mu, "num_points")) then - call get_node_value(node_legendre_mu, "num_points", & - this % legendre_mu_points) - if (this % legendre_mu_points <= 0) then - call fatal_error("num_points element must be positive and non-zero!") - end if - this % legendre_mu_points = -1 * this % legendre_mu_points - end if - else - this % legendre_mu_points = 1 - end if - if (check_for_node(node_xsdata, "fissionable")) then call get_node_value(node_xsdata, "fissionable", temp_str) temp_str = to_lower(temp_str) @@ -387,16 +350,26 @@ module nuclide_header end subroutine nuclidemg_init - subroutine nuclideiso_init(this, node_xsdata, groups, get_kfiss, get_fiss) + subroutine nuclideiso_init(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order) class(NuclideIso), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Need fiss data? + integer, intent(in) :: max_order ! Maximum requested order - real(8), allocatable :: temp_arr(:) - integer :: arr_len - integer :: order_dim + type(Node), pointer :: node_legendre_mu + character(MAX_LINE_LEN) :: temp_str + logical :: enable_leg_mu + real(8), allocatable :: temp_arr(:) + real(8), allocatable :: temp_mult(:,:) + real(8), allocatable :: scatt_coeffs(:,:,:) + real(8), allocatable :: input_scatt(:,:,:) + real(8), allocatable :: temp_scatt(:,:,:) + real(8) :: dmu, mu, norm + integer :: order_dim, gin, gout, l, arr_len + integer :: legendre_mu_points, imu ! Call generic data gathering routine call nuclidemg_init(this, node_xsdata) @@ -460,6 +433,33 @@ module nuclide_header call fatal_error("Must provide absorption!") end if + ! Get scattering treatment + if (check_for_node(node_xsdata, "tabular_legendre")) then + call get_node_ptr(node_xsdata, "tabular_legendre", node_legendre_mu) + if (check_for_node(node_legendre_mu, "enable")) then + call get_node_value(node_legendre_mu, "enable", temp_str) + temp_str = trim(to_lower(temp_str)) + if (temp_str == 'true' .or. temp_str == '1') then + enable_leg_mu = .true. + elseif (temp_str == 'false' .or. temp_str == '0') then + enable_leg_mu = .false. + else + call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + end if + else + enable_leg_mu = .true. + legendre_mu_points = 33 + end if + if (enable_leg_mu .and. & + check_for_node(node_legendre_mu, "num_points")) then + call get_node_value(node_legendre_mu, "num_points", & + legendre_mu_points) + if (legendre_mu_points <= 0) then + call fatal_error("num_points element must be positive and non-zero!") + end if + end if + end if + if (this % scatt_type == ANGLE_LEGENDRE) then order_dim = this % order + 1 else if (this % scatt_type == ANGLE_HISTOGRAM) then @@ -468,33 +468,94 @@ module nuclide_header order_dim = this % order end if - allocate(this % scatter(groups, groups, order_dim)) + allocate(input_scatt(groups, groups, order_dim)) if (check_for_node(node_xsdata, "scatter")) then allocate(temp_arr(groups * groups * order_dim)) call get_node_array(node_xsdata, "scatter", temp_arr) - this % scatter = reshape(temp_arr, (/groups, groups, order_dim/)) + input_scatt = reshape(temp_arr, (/groups, groups, order_dim/)) deallocate(temp_arr) + + ! Compare the number of orders given with the maximum order of the + ! problem. Strip off the supefluous orders if needed. + if (this % scatt_type == ANGLE_LEGENDRE) then + order_dim = min(order_dim, max_order + 1) + this % order = order_dim + end if + allocate(temp_scatt(groups, groups, order_dim)) + do gin = 1, groups + do gout = 1, groups + do l = 1, order_dim + temp_scatt(gout,gin,l) = input_scatt(gout,gin,l) + end do + end do + end do + + ! Take input format (groups, groups, order) and convert to + ! the more useful format needed for scattdata: (order, groups, groups) + ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was + ! provided as Legendre coefficients), and the user requested that + ! these legendres be converted to tabular form (note this is also + ! the default behavior), convert that now. + if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then + ! Convert input parameters to what we need for the rest. + this % scatt_type = ANGLE_TABULAR + order_dim = legendre_mu_points + this % order = order_dim + dmu = TWO / real(this % order - 1,8) + + allocate(scatt_coeffs(order_dim, groups, groups)) + do gin = 1, groups + do gout = 1, groups + norm = ZERO + do imu = 1, order_dim + if (imu == 1) then + mu = -ONE + else if (imu == order_dim) then + mu = ONE + else + mu = -ONE + real(imu - 1,8) * dmu + end if + scatt_coeffs(imu,gout,gin) = & + evaluate_legendre(temp_scatt(gout,gin,:),mu) + if (scatt_coeffs(imu,gout,gin) < ZERO) & + scatt_coeffs(imu,gout,gin) = ZERO + if (imu > 1) then + norm = norm + HALF * dmu * (scatt_coeffs(imu-1,gout,gin) + & + scatt_coeffs(imu,gout,gin)) + end if + end do + if (norm > ZERO) then + scatt_coeffs(:,gout,gin) = scatt_coeffs(:,gout,gin) * & + temp_scatt(gout,gin,1) / norm + end if + end do + end do + else + ! Sticking with current representation, carry forward but change + ! the array ordering + allocate(scatt_coeffs(order_dim, groups, groups)) + do gin = 1, groups + do gout = 1, groups + do l = 1, order_dim + scatt_coeffs(l,gout,gin) = temp_scatt(gout,gin,l) + end do + end do + end do + end if + deallocate(temp_scatt) else call fatal_error("Must provide scatter!") return end if - - allocate(this % total(groups)) - if (check_for_node(node_xsdata, "total")) then - call get_node_array(node_xsdata, "total", this % total) - else - this % total = this % absorption + sum(this%scatter(:,:,1),dim=1) - end if - ! Get Mult Data - allocate(this % mult(groups, groups)) + allocate(temp_mult(groups, groups)) if (check_for_node(node_xsdata, "multiplicity")) then arr_len = get_arraysize_double(node_xsdata, "multiplicity") if (arr_len == groups * groups) then allocate(temp_arr(arr_len)) call get_node_array(node_xsdata, "multiplicity", temp_arr) - this % mult = reshape(temp_arr, (/groups, groups/)) + temp_mult = reshape(temp_arr, (/groups, groups/)) deallocate(temp_arr) else call fatal_error("Multiplicity length not same as number of groups& @@ -502,17 +563,42 @@ module nuclide_header return end if else - this % mult = ONE + temp_mult = ONE end if + ! Allocate and initialize our ScattData Object.. + if (this % scatt_type == ANGLE_HISTOGRAM) then + allocate(ScattDataHistogram :: this % scatter) + else if (this % scatt_type == ANGLE_TABULAR) then + allocate(ScattDataTabular :: this % scatter) + else if (this % scatt_type == ANGLE_LEGENDRE) then + allocate(ScattDataLegendre :: this % scatter) + end if + + ! Initialize the ScattData Object + call this % scatter % init(temp_mult, scatt_coeffs(:,:,:)) + + ! Get, or infer, total xs data. + allocate(this % total(groups)) + if (check_for_node(node_xsdata, "total")) then + call get_node_array(node_xsdata, "total", this % total) + else + this % total = this % absorption + this % scatter % scattxs + end if + + ! Deallocate temporaries for the next material + deallocate(scatt_coeffs, temp_mult) + end subroutine nuclideiso_init - subroutine nuclideangle_init(this, node_xsdata, groups, get_kfiss, get_fiss) + subroutine nuclideangle_init(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order) class(NuclideAngle), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order real(8), allocatable :: temp_arr(:) integer :: arr_len @@ -531,151 +617,151 @@ module nuclide_header order_dim = this % order end if - if (check_for_node(node_xsdata, "num_polar")) then - call get_node_value(node_xsdata, "num_polar", this % n_pol) - else - call fatal_error("num_polar Must Be Provided!") - end if + ! if (check_for_node(node_xsdata, "num_polar")) then + ! call get_node_value(node_xsdata, "num_polar", this % n_pol) + ! else + ! call fatal_error("num_polar Must Be Provided!") + ! end if - if (check_for_node(node_xsdata, "num_azimuthal")) then - call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) - else - call fatal_error("num_azimuthal Must Be Provided!") - end if + ! if (check_for_node(node_xsdata, "num_azimuthal")) then + ! call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) + ! else + ! call fatal_error("num_azimuthal Must Be Provided!") + ! end if - ! Load angle data, if present (else equally spaced) - allocate(this % polar(this % n_pol)) - allocate(this % azimuthal(this % n_azi)) - if (check_for_node(node_xsdata, "polar")) then - call fatal_error("User-Specified polar angle bins not yet supported!") - ! When this feature is supported, this line will be activated - call get_node_array(node_xsdata, "polar", this % polar) - else - dangle = PI / real(this % n_pol,8) - do iangle = 1, this % n_pol - this % polar(iangle) = (real(iangle,8) - HALF) * dangle - end do - end if - if (check_for_node(node_xsdata, "azimuthal")) then - call fatal_error("User-Specified azimuthal angle bins not yet supported!") - ! When this feature is supported, this line will be activated - call get_node_array(node_xsdata, "azimuthal", this % azimuthal) - else - dangle = TWO * PI / real(this % n_azi,8) - do iangle = 1, this % n_azi - this % azimuthal(iangle) = -PI + (real(iangle,8) - HALF) * dangle - end do - end if + ! ! Load angle data, if present (else equally spaced) + ! allocate(this % polar(this % n_pol)) + ! allocate(this % azimuthal(this % n_azi)) + ! if (check_for_node(node_xsdata, "polar")) then + ! call fatal_error("User-Specified polar angle bins not yet supported!") + ! ! When this feature is supported, this line will be activated + ! call get_node_array(node_xsdata, "polar", this % polar) + ! else + ! dangle = PI / real(this % n_pol,8) + ! do iangle = 1, this % n_pol + ! this % polar(iangle) = (real(iangle,8) - HALF) * dangle + ! end do + ! end if + ! if (check_for_node(node_xsdata, "azimuthal")) then + ! call fatal_error("User-Specified azimuthal angle bins not yet supported!") + ! ! When this feature is supported, this line will be activated + ! call get_node_array(node_xsdata, "azimuthal", this % azimuthal) + ! else + ! dangle = TWO * PI / real(this % n_azi,8) + ! do iangle = 1, this % n_azi + ! this % azimuthal(iangle) = -PI + (real(iangle,8) - HALF) * dangle + ! end do + ! end if - ! Load the more specific data - if (this % fissionable) then + ! ! Load the more specific data + ! if (this % fissionable) then - if (check_for_node(node_xsdata, "chi")) then - ! Get chi - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "chi", temp_arr) - allocate(this % chi(groups, this % n_azi, this % n_pol)) - this % chi = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) + ! if (check_for_node(node_xsdata, "chi")) then + ! ! Get chi + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "chi", temp_arr) + ! allocate(this % chi(groups, this % n_azi, this % n_pol)) + ! this % chi = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) - ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata, "nu_fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "nu_fission", temp_arr) - allocate(this % nu_fission(groups, 1, this % n_azi, this % n_pol)) - this % nu_fission = reshape(temp_arr, (/groups, 1, this % n_azi, & - this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if + ! ! Get nu_fission (as a vector) + ! if (check_for_node(node_xsdata, "nu_fission")) then + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "nu_fission", temp_arr) + ! allocate(this % nu_fission(groups, 1, this % n_azi, this % n_pol)) + ! this % nu_fission = reshape(temp_arr, (/groups, 1, this % n_azi, & + ! this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("If fissionable, must provide nu_fission!") + ! end if - else - ! Get nu_fission (as a matrix) - if (check_for_node(node_xsdata, "nu_fission")) then + ! else + ! ! Get nu_fission (as a matrix) + ! if (check_for_node(node_xsdata, "nu_fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "nu_fission", temp_arr) - allocate(this % nu_fission(groups, groups, this % n_azi, this % n_pol)) - this % nu_fission = reshape(temp_arr, (/groups, groups, & - this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if - end if - if (get_fiss) then - if (check_for_node(node_xsdata, "fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "fission", temp_arr) - allocate(this % fission(groups, this % n_azi, this % n_pol)) - this % fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Fission data missing, required due to fission& - & tallies in tallies.xml file!") - end if - end if - if (get_kfiss) then - if (check_for_node(node_xsdata, "kappa_fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "kappa_fission", temp_arr) - allocate(this % k_fission(groups, this % n_azi, this % n_pol)) - this % k_fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("kappa_fission data missing, required due to & - &kappa-fission tallies in tallies.xml file!") - end if - end if - end if + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "nu_fission", temp_arr) + ! allocate(this % nu_fission(groups, groups, this % n_azi, this % n_pol)) + ! this % nu_fission = reshape(temp_arr, (/groups, groups, & + ! this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("If fissionable, must provide nu_fission!") + ! end if + ! end if + ! if (get_fiss) then + ! if (check_for_node(node_xsdata, "fission")) then + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "fission", temp_arr) + ! allocate(this % fission(groups, this % n_azi, this % n_pol)) + ! this % fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("Fission data missing, required due to fission& + ! & tallies in tallies.xml file!") + ! end if + ! end if + ! if (get_kfiss) then + ! if (check_for_node(node_xsdata, "kappa_fission")) then + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "kappa_fission", temp_arr) + ! allocate(this % k_fission(groups, this % n_azi, this % n_pol)) + ! this % k_fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("kappa_fission data missing, required due to & + ! &kappa-fission tallies in tallies.xml file!") + ! end if + ! end if + ! end if - if (check_for_node(node_xsdata, "absorption")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "absorption", temp_arr) - allocate(this % absorption(groups, this % n_azi, this % n_pol)) - this % absorption = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Must provide absorption!") - end if + ! if (check_for_node(node_xsdata, "absorption")) then + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "absorption", temp_arr) + ! allocate(this % absorption(groups, this % n_azi, this % n_pol)) + ! this % absorption = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("Must provide absorption!") + ! end if - allocate(this % scatter(groups, groups, order_dim, this % n_azi, this % n_pol)) - if (check_for_node(node_xsdata, "scatter")) then - allocate(temp_arr(groups * groups * order_dim * this % n_azi * this%n_pol)) - call get_node_array(node_xsdata, "scatter", temp_arr) - this % scatter = reshape(temp_arr, (/groups, groups, order_dim, & - this%n_azi,this%n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Must provide scatter!") - end if + ! allocate(this % scatter(groups, groups, order_dim, this % n_azi, this % n_pol)) + ! if (check_for_node(node_xsdata, "scatter")) then + ! allocate(temp_arr(groups * groups * order_dim * this % n_azi * this%n_pol)) + ! call get_node_array(node_xsdata, "scatter", temp_arr) + ! this % scatter = reshape(temp_arr, (/groups, groups, order_dim, & + ! this%n_azi,this%n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("Must provide scatter!") + ! end if - if (check_for_node(node_xsdata, "total")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata, "total", temp_arr) - allocate(this % total(groups, this % n_azi, this % n_pol)) - this % total = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - this % total = this % absorption + sum(this%scatter(:,:,1,:,:),dim=1) - end if + ! if (check_for_node(node_xsdata, "total")) then + ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) + ! call get_node_array(node_xsdata, "total", temp_arr) + ! allocate(this % total(groups, this % n_azi, this % n_pol)) + ! this % total = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! this % total = this % absorption + sum(this%scatter(:,:,1,:,:),dim=1) + ! end if - ! Get Mult Data - allocate(this % mult(groups, groups, this % n_azi, this % n_pol)) - if (check_for_node(node_xsdata, "multiplicity")) then - arr_len = get_arraysize_double(node_xsdata, "multiplicity") - if (arr_len == groups * groups * this % n_azi * this % n_pol) then - allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata, "multiplicity", temp_arr) - this % mult = reshape(temp_arr, (/groups, groups, this % n_azi, this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Multiplicity Length Does Not Match!") - end if - else - this % mult = ONE - end if + ! ! Get Mult Data + ! allocate(this % mult(groups, groups, this % n_azi, this % n_pol)) + ! if (check_for_node(node_xsdata, "multiplicity")) then + ! arr_len = get_arraysize_double(node_xsdata, "multiplicity") + ! if (arr_len == groups * groups * this % n_azi * this % n_pol) then + ! allocate(temp_arr(arr_len)) + ! call get_node_array(node_xsdata, "multiplicity", temp_arr) + ! this % mult = reshape(temp_arr, (/groups, groups, this % n_azi, this % n_pol/)) + ! deallocate(temp_arr) + ! else + ! call fatal_error("Multiplicity Length Does Not Match!") + ! end if + ! else + ! this % mult = ONE + ! end if end subroutine nuclideangle_init @@ -823,6 +909,7 @@ module nuclide_header integer :: unit_ ! unit to write to integer :: size_total, size_scattmat, size_mgxs + integer :: gin ! set default unit for writing information if (present(unit)) then @@ -835,7 +922,15 @@ module nuclide_header call nuclidemg_print(this, unit_) ! Determine size of mgxs and scattering matrices - size_scattmat = (size(this % scatter) + size(this % mult)) * 8 + size_scattmat = 0 + do gin = 1, size(this % scatter % energy) + size_scattmat = size_scattmat + & + 2 * size(this % scatter % energy(gin) % data) + & + size(this % scatter % dist(gin) % data) + & + size(this % scatter % scattxs) + end do + size_scattmat = size_scattmat * 8 + size_mgxs = size(this % total) + size(this % absorption) + & size(this % nu_fission) + size(this % k_fission) + & size(this % fission) + size(this % chi) @@ -863,6 +958,7 @@ module nuclide_header integer :: unit_ ! unit to write to integer :: size_total, size_scattmat, size_mgxs + integer :: i_pol, i_azi, gin ! set default unit for writing information if (present(unit)) then @@ -877,6 +973,18 @@ module nuclide_header write(unit_,*) ' # of Azimuthal Angles = ' // trim(to_str(this % n_azi)) ! Determine size of mgxs and scattering matrices + size_scattmat = 0 + do i_pol = 1, this % n_pol + do i_azi = 1, this % n_azi + do gin = 1, size(this % scatter(i_azi,i_pol) % obj % energy) + size_scattmat = size_scattmat + & + 2 * size(this % scatter(i_azi,i_pol) % obj % energy(gin) % data) + & + size(this % scatter(i_azi,i_pol) % obj % dist(gin) % data) + end do + end do + end do + size_scattmat = size_scattmat * 8 + size_scattmat = (size(this % scatter) + size(this % mult)) * 8 size_mgxs = size(this % total) + size(this % absorption) + & size(this % nu_fission) + size(this % k_fission) + & @@ -925,13 +1033,13 @@ module nuclide_header if (present(gout)) then select case(xstype) case('mult') - xs = this % mult(gout,g) + xs = this % scatter % mult(g) % data(gout) case('nu_fission') xs = this % nu_fission(gout,g) case('f_mu', 'f_mu/mult') - xs = this % calc_f(g, gout, mu) + xs = this % scatter % calc_f(g, gout, mu) if (xstype == 'f_mu/mult') then - xs = xs / this % mult(gout,g) + xs = xs / this % scatter % mult(g) % data(gout) end if end select else @@ -949,7 +1057,7 @@ module nuclide_header case('chi') xs = this % chi(g) case('scatter') - xs = this % total(g) - this % absorption(g) + xs = this % scatter % scattxs(g) end select end if end function nuclideiso_get_xs @@ -985,15 +1093,15 @@ module nuclide_header if (present(gout)) then select case(xstype) case('mult') - xs = this % mult(gout,g,i_azi_,i_pol_) + xs = this % scatter(i_azi_,i_pol_) % obj % mult(g) % data(gout) case('nu_fission') xs = this % nu_fission(gout,g,i_azi_,i_pol_) case('chi') xs = this % chi(gout,i_azi_,i_pol_) case('f_mu', 'f_mu/mult') - xs = this % calc_f(g, gout, mu, I_AZI=i_azi_, I_POL=i_pol_) + xs = this % scatter(i_azi_,i_pol_) % obj % calc_f(g,gout,mu) if (xstype == 'f_mu/mult') then - xs = xs / this % mult(gout,g,i_azi_,i_pol_) + xs = xs / this % scatter(i_azi_,i_pol_) % obj % mult(g) % data(gout) end if end select else @@ -1011,116 +1119,10 @@ module nuclide_header case('chi') xs = this % chi(g,i_azi_,i_pol_) case('scatter') - xs = this % total(g,i_azi_,i_pol_) - this % absorption(g,i_azi_,i_pol_) + xs = this % scatter(i_azi_,i_pol_) % obj % scattxs(g) end select end if end function nuclideangle_get_xs -!=============================================================================== -! NUCLIDE*_CALC_F Finds the value of f(mu), the scattering angle probability, -! given mu -!=============================================================================== - - pure function nuclideiso_calc_f(this, gin, gout, mu, uvw, i_azi, i_pol) & - result(f) - class(NuclideIso), intent(in) :: this - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8), intent(in), optional :: uvw(3) ! Direction vector - integer, intent(in), optional :: i_azi ! Incoming Energy Group - integer, intent(in), optional :: i_pol ! Outgoing Energy Group - real(8) :: f ! Return value of f(mu) - - real(8) :: dmu, r - integer :: imu - - if (this % scatt_type == ANGLE_LEGENDRE) then - f = evaluate_legendre(this % scatter(gout,gin,:), mu) - else if (this % scatt_type == ANGLE_TABULAR) then - dmu = TWO / real(this % order - 1,8) - ! Find mu bin algebraically, knowing that the spacing is equal - f = (mu + ONE) / dmu + ONE - imu = floor(f) - ! But save the amount that mu is past the previous index - ! so we can use interpolation later. - f = f - real(imu,8) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % scatter, dim=3)) then - imu = imu - 1 - end if - - ! Now intepolate to find f(mu) - r = f / dmu - f = (ONE - r) * this % scatter(gout,gin,imu) + & - r * this % scatter(gout,gin,imu+1) - else ! (ANGLE_HISTOGRAM) - dmu = TWO / real(this % order,8) - ! Find mu bin algebraically, knowing that the spacing is equal - imu = floor((mu + ONE) / dmu + ONE) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % scatter, dim=3)) then - imu = imu - 1 - end if - f = this % scatter(gout, gin, imu) - - end if - - end function nuclideiso_calc_f - - pure function nuclideangle_calc_f(this, gin, gout, mu, uvw, i_azi, & - i_pol) result(f) - class(NuclideAngle), intent(in) :: this - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8), intent(in), optional :: uvw(3) ! Direction vector - integer, intent(in), optional :: i_azi ! Incoming Energy Group - integer, intent(in), optional :: i_pol ! Outgoing Energy Group - real(8) :: f ! Return value of f(mu) - - real(8) :: dmu, r - integer :: imu - integer :: i_azi_, i_pol_ - if (present(i_azi) .and. present(i_pol)) then - i_azi_ = i_azi - i_pol_ = i_pol - else if (present(uvw)) then - call find_angle(this % polar, this % azimuthal, uvw, i_azi_, i_pol_) - end if - - if (this % scatt_type == ANGLE_LEGENDRE) then - f = evaluate_legendre(this % scatter(gout,gin,:,i_azi_,i_pol_), mu) - else if (this % scatt_type == ANGLE_TABULAR) then - dmu = TWO / real(this % order - 1,8) - ! Find mu bin algebraically, knowing that the spacing is equal - f = (mu + ONE) / dmu + ONE - imu = floor(f) - ! But save the amount that mu is past the previous index - ! so we can use interpolation later. - f = f - real(imu,8) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % scatter, dim=3)) then - imu = imu - 1 - end if - - ! Now intepolate to find f(mu) - r = f / dmu - f = (ONE - r) * this % scatter(gout,gin,imu,i_azi_,i_pol_) + & - r * this % scatter(gout,gin,imu+1,i_azi_,i_pol_) - else ! (ANGLE_HISTOGRAM) - dmu = TWO / real(this % order,8) - ! Find mu bin algebraically, knowing that the spacing is equal - imu = floor((mu + ONE) / dmu + ONE) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % scatter, dim=3)) then - imu = imu - 1 - end if - f = this % scatter(gout, gin, imu,i_azi_,i_pol_) - - end if - - end function nuclideangle_calc_f - end module nuclide_header diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 949bd8707..003b31d87 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -35,26 +35,27 @@ module scattdata_header type(Jagged2D), allocatable :: dist(:) ! (Gin % data(Order/Nmu x Gout) integer, allocatable :: gmin(:) ! Minimum outgoing group integer, allocatable :: gmax(:) ! Maximum outgoing group + real(8), allocatable :: scattxs(:) ! Isotropic Sigma_{s,g_{in}} contains procedure(scattdata_init_), deferred :: init ! Initializes ScattData procedure(scattdata_calc_f_), deferred :: calc_f ! Calculates f, given mu procedure(scattdata_sample_), deferred :: sample ! sample the scatter event + ! Reproduces an unnormalized scattering matrix + procedure :: get_matrix => scattdata_get_matrix end type ScattData abstract interface - subroutine scattdata_init_(this, order, energy, mult, coeffs) + subroutine scattdata_init_(this, mult, coeffs) import ScattData - class(ScattData), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix + class(ScattData), intent(inout) :: this ! Scattering Object to work with real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use end subroutine scattdata_init_ pure function scattdata_calc_f_(this, gin, gout, mu) result(f) import ScattData - class(ScattData), intent(in) :: this ! The ScattData to evaluate + class(ScattData), intent(in) :: this !! Scattering Object to work with integer, intent(in) :: gin ! Incoming Energy Group integer, intent(in) :: gout ! Outgoing Energy Group real(8), intent(in) :: mu ! Angle of interest @@ -64,7 +65,7 @@ module scattdata_header subroutine scattdata_sample_(this, gin, gout, mu, wgt) import ScattData - class(ScattData), intent(in) :: this ! Scattering Object to Use + class(ScattData), intent(in) :: this !! Scattering Object to work with integer, intent(in) :: gin ! Incoming neutron group integer, intent(out) :: gout ! Sampled outgoin group real(8), intent(out) :: mu ! Sampled change in angle @@ -76,18 +77,20 @@ module scattdata_header ! Maximal value for rejection sampling from rectangle type(Jagged1D), allocatable :: max_val(:) ! (Gin % data(Gout)) contains - procedure :: init => scattdatalegendre_init - procedure :: calc_f => scattdatalegendre_calc_f - procedure :: sample => scattdatalegendre_sample + procedure :: init => scattdatalegendre_init + procedure :: calc_f => scattdatalegendre_calc_f + procedure :: sample => scattdatalegendre_sample + ! procedure :: get_matrix => scattdatalegendre_get_matrix end type ScattDataLegendre type, extends(ScattData) :: ScattDataHistogram real(8), allocatable :: mu(:) ! Mu bins real(8) :: dmu ! Mu spacing contains - procedure :: init => scattdatahistogram_init - procedure :: calc_f => scattdatahistogram_calc_f - procedure :: sample => scattdatahistogram_sample + procedure :: init => scattdatahistogram_init + procedure :: calc_f => scattdatahistogram_calc_f + procedure :: sample => scattdatahistogram_sample + ! procedure :: get_matrix => scattdatahistogram_get_matrix end type ScattDataHistogram type, extends(ScattData) :: ScattDataTabular @@ -96,9 +99,10 @@ module scattdata_header ! PDF of f(mu) type(Jagged2D), allocatable :: fmu(:) ! (Gin % data(Order/Nmu x Gout) contains - procedure :: init => scattdatatabular_init - procedure :: calc_f => scattdatatabular_calc_f - procedure :: sample => scattdatatabular_sample + procedure :: init => scattdatatabular_init + procedure :: calc_f => scattdatatabular_calc_f + procedure :: sample => scattdatatabular_sample + procedure :: get_matrix => scattdatatabular_get_matrix end type ScattDataTabular !=============================================================================== @@ -112,16 +116,17 @@ module scattdata_header contains !=============================================================================== -! SCATTDATA_INIT builds the scattdata object +! SCATTDATA*_INIT builds the scattdata object !=============================================================================== subroutine scattdata_init(this, order, energy, mult) class(ScattData), intent(inout) :: this ! Object to work on integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix + real(8), intent(inout) :: energy(:,:) ! Energy Transfer Matrix real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix integer :: groups, gmin, gmax, gin + real(8) :: norm groups = size(energy, dim=1) @@ -133,6 +138,9 @@ contains ! Use energy to find the gmin and gmax values ! Also set energy values when doing it do gin = 1, groups + ! Make sure energy is normalized (i.e., CDF is 1) + norm = sum(energy(:,gin)) + if (norm /= ZERO) energy(:,gin) = energy(:,gin) / norm ! Find gmin by checking the P0 moment do gmin = 1, groups if (energy(gmin,gin) > ZERO) exit @@ -156,23 +164,42 @@ contains this % gmin(gin) = gmin this % gmax(gin) = gmax end do - end subroutine scattdata_init - subroutine scattdatalegendre_init(this, order, energy, mult, coeffs) + subroutine scattdatalegendre_init(this, mult, coeffs) class(ScattDataLegendre), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use - real(8) :: dmu, mu, f - integer :: imu, Nmu, gout, gin, groups + real(8) :: dmu, mu, f, norm + integer :: imu, Nmu, gout, gin, groups, order + real(8), allocatable :: energy(:,:) + + groups = size(coeffs,dim=3) + order = size(coeffs,dim=1) + + ! Get scattxs value first before anything happens to coeffs + allocate(this % scattxs(groups)) + ! Get this by summing the now un-normalized P0 coefficient in coeffs + ! over all outgoing groups + this % scattxs = sum(coeffs(1,:,:),dim=1) + + allocate(energy(groups,groups)) + energy = ZERO + ! Build energy transfer probability matrix from data in coeffs + ! while also normalizing coeffs itself (making CDF of f(mu=1)=1) + do gin = 1, groups + do gout = 1, groups + norm = coeffs(1,gout,gin) + energy(gout,gin) = norm + if (norm /= ZERO) then + coeffs(:,gout,gin) = coeffs(:,gout,gin) / norm + end if + end do + end do call scattdata_init(this, order, energy, mult) - groups = size(this % energy,dim=1) - allocate(this % max_val(groups)) ! Set dist values from coeffs and initialize max_val do gin = 1, groups @@ -186,7 +213,7 @@ contains ! Step through the polynomial with fixed number of points to identify ! the maximal value. Nmu = 1001 - dmu = TWO / real(Nmu,8) + dmu = TWO / real(Nmu - 1,8) do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) do imu = 1, Nmu @@ -209,20 +236,39 @@ contains this % max_val(gin) % data(gout) * 1.1_8 end do end do - end subroutine scattdatalegendre_init - subroutine scattdatahistogram_init(this, order, energy, mult, coeffs) + subroutine scattdatahistogram_init(this, mult, coeffs) class(ScattDataHistogram), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use - integer :: imu, gin, gout, groups + integer :: imu, gin, gout, groups, order real(8) :: norm + real(8), allocatable :: energy(:,:) - groups = size(energy,dim=1) + groups = size(coeffs,dim=3) + order = size(coeffs,dim=1) + + ! Get scattxs value first before anything happens to coeffs + allocate(this % scattxs(groups)) + ! Get this by summing the now un-normalized P0 coefficient in coeffs + ! over all outgoing groups + this % scattxs = sum(sum(coeffs(:,:,:),dim=1),dim=1) + + allocate(energy(groups,groups)) + energy = ZERO + ! Build energy transfer probability matrix from data in coeffs + ! while also normalizing coeffs itself (making CDF of f(mu=1)=1) + do gin = 1, groups + do gout = 1, groups + norm = sum(coeffs(:,gout,gin)) + energy(gout,gin) = norm + if (norm /= ZERO) then + coeffs(:,gout,gin) = coeffs(:,gout,gin) / norm + end if + end do + end do call scattdata_init(this, order, energy, mult) @@ -253,91 +299,105 @@ contains end subroutine scattdatahistogram_init - subroutine scattdatatabular_init(this, order, energy, mult, coeffs) + subroutine scattdatatabular_init(this, mult, coeffs) class(ScattDataTabular), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(in) :: energy(:,:) ! Energy Transfer Matrix - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use - integer :: imu, gin, gout, groups + integer :: imu, gin, gout, groups, order real(8) :: norm - logical :: legendre_flag - integer :: this_order + real(8), allocatable :: energy(:,:) - if (order < 0) then - legendre_flag = .true. - this_order = -1 * order - else - legendre_flag = .false. - this_order = order - end if + groups = size(coeffs,dim=3) + order = size(coeffs,dim=1) - groups = size(energy,dim=1) - - call scattdata_init(this, this_order, energy, mult) - - allocate(this % mu(this_order)) - this % dmu = TWO / real(this_order - 1) - this % mu = -ONE - do imu = 2, this_order - 1 - this % mu(imu) = -ONE + real(imu - 1) * this % dmu + ! Build the angular distribution mu values + allocate(this % mu(order)) + this % dmu = TWO / real(order - 1,8) + this % mu(1) = -ONE + do imu = 2, order - 1 + this % mu(imu) = -ONE + real(imu - 1,8) * this % dmu end do - this % mu(this_order) = ONE + this % mu(order) = ONE + + ! Get scattxs before anything happens to coeffs + allocate(this % scattxs(groups)) + ! Get this by integrating the scattering distribution over all mu points + ! and then combining over all outgoing groups + ! over all outgoing groups + do gin = 1, groups + norm = ZERO + do gout = 1, groups + do imu = 2, order + norm = norm + HALF * this % dmu * (coeffs(imu - 1,gout,gin) + & + coeffs(imu,gout,gin)) + end do + end do + this % scattxs(gin) = norm + end do + + allocate(energy(groups,groups)) + energy = ZERO + ! Build energy transfer probability matrix from data in coeffs + do gin = 1, groups + do gout = 1, groups + norm = ZERO + do imu = 2, order + norm = norm + HALF * this % dmu * & + (coeffs(imu - 1,gout,gin) + coeffs(imu,gout,gin)) + end do + ! energy(gout,gin) = sum(coeffs(:,gout,gin)) + energy(gout,gin) = norm + end do + end do + call scattdata_init(this, order, energy, mult) ! Calculate f(mu) and integrate it so we can avoid rejection sampling allocate(this % fmu(groups)) do gin = 1, groups - allocate(this % fmu(gin) % data(this_order,& - this % gmin(gin):this % gmax(gin))) + allocate(this % fmu(gin) % data(order, & + this % gmin(gin):this % gmax(gin))) do gout = this % gmin(gin), this % gmax(gin) - if (legendre_flag) then - ! Coeffs are legendre coeffs. Need to build f(mu) then integrate - ! and store the integral in this % dist - ! Ensure the coeffs are normalized - if (coeffs(1,gout,gin) /= ZERO) then - norm = ONE / coeffs(1,gout,gin) - else - norm = ONE + ! Coeffs contain f(mu), put in f(mu) as that is where the + ! PDF lives + this % fmu(gin) % data(:,gout) = coeffs(:,gout,gin) + + ! Force positivity + do imu = 1, order + if (this % fmu(gin) % data(imu,gout) < ZERO) then + this % fmu(gin) % data(imu,gout) = ZERO end if - do imu = 1, this_order - this % fmu(gin) % data(imu,gout) = & - evaluate_legendre(norm * coeffs(:,gout,gin), this % mu(imu)) - ! Force positivity - if (this % fmu(gin) % data(imu,gout) < ZERO) then - this % fmu(gin) % data(imu,gout) = ZERO - end if - end do - else - ! Coeffs contain f(mu), put in f(mu) as that is where the - ! PDF lives - this % fmu(gin) % data(:,gout) = this % dist(gin) % data(:,gout) - end if + end do ! Re-normalize fmu for numerical integration issues and in case ! the negative fix-up introduced un-normalized data norm = ZERO - do imu = 2, this_order + do imu = 2, order norm = norm + HALF * this % dmu * & (this % fmu(gin) % data(imu - 1,gout) + & this % fmu(gin) % data(imu,gout)) end do if (norm > ZERO) then - this % fmu(gin) % data(:,gout) = this % fmu(gin) % data(:,gout) / norm + this % fmu(gin) % data(:,gout) = & + this % fmu(gin) % data(:,gout) / norm end if ! Now create CDF from fmu with trapezoidal rule this % dist(gin) % data(1,gout) = ZERO - do imu = 2, this_order - 1 + do imu = 2, order this % dist(gin) % data(imu,gout) = & this % dist(gin) % data(imu - 1,gout) + & HALF * this % dmu * (this % fmu(gin) % data(imu - 1,gout) + & this % fmu(gin) % data(imu,gout)) end do - this % dist(gin) % data(this_order,gout) = ONE + ! Ensure we normalize to 1 still + norm = this % dist(gin) % data(order,gout) + if (norm > ZERO) then + this % dist(gin) % data(:,gout) = & + this % dist(gin) % data(:,gout) / norm + end if end do end do - end subroutine scattdatatabular_init !=============================================================================== @@ -547,4 +607,57 @@ contains end subroutine scattdatatabular_sample +!=============================================================================== +! SCATTDATA*_GET_MATRIX Reproduces the original scattering matrix (densely) +! using ScattData's information of fmu/dist, energy, and scattxs +!=============================================================================== + + function scattdata_get_matrix(this, req_order) result(matrix) + class(ScattData), intent(in) :: this ! Scattering Object to work with + integer, intent(in) :: req_order ! Requested order of matrix + real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + + integer :: order, groups, gin, gout + + groups = size(this % energy) + order = min(req_order,size(this % dist(1) % data(:,1))) + + allocate(matrix(order,groups,groups)) + ! Initialize to 0; this way the zero entries in the dense matrix dont + ! need to be explicitly set, requiring a significant increase in the + ! lines of code. + matrix = ZERO + do gin = 1, groups + do gout = this % gmin(gin), this % gmax(gin) + matrix(:,gout,gin) = this % scattxs(gin) * & + this % energy(gin) % data(gout) * & + this % dist(gin) % data(1:order,gout) + end do + end do + end function scattdata_get_matrix + + function scattdatatabular_get_matrix(this, req_order) result(matrix) + class(ScattDataTabular), intent(in) :: this ! Scattering Object to work with + integer, intent(in) :: req_order ! Requested order of matrix + real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + + integer :: order, groups, gin, gout + + groups = size(this % energy) + order = min(req_order,size(this % dist(1) % data(:,1))) + + allocate(matrix(order,groups,groups)) + ! Initialize to 0; this way the zero entries in the dense matrix dont + ! need to be explicitly set, requiring a significant increase in the + ! lines of code. + matrix = ZERO + do gin = 1, groups + do gout = this % gmin(gin), this % gmax(gin) + matrix(:,gout,gin) = this % scattxs(gin) * & + this % energy(gin) % data(gout) * & + this % fmu(gin) % data(1:order,gout) + end do + end do + end function scattdatatabular_get_matrix + end module scattdata_header From c2aa26411a4b57824067f1e1dba61b10bc3af146 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Mon, 7 Mar 2016 16:01:01 -0500 Subject: [PATCH 007/147] incorporated the latest features angle-dependent mgxs --- src/macroxs_header.F90 | 224 +++++++------ src/nuclide_header.F90 | 665 +++++++++++++++++++++++++-------------- src/scattdata_header.F90 | 9 +- 3 files changed, 535 insertions(+), 363 deletions(-) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index d32cde96e..9eb3ea864 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -17,9 +17,6 @@ module macroxs_header !=============================================================================== type, abstract :: MacroXS - ! Data Order - integer :: order - contains procedure(macroxs_init_), deferred :: init ! initializes object procedure(macroxs_get_xs_), deferred :: get_xs ! Return xs @@ -149,68 +146,73 @@ contains integer :: i ! loop index over nuclides integer :: gin, gout ! group indices real(8) :: atom_density ! atom density of a nuclide - integer :: imu real(8) :: norm - integer :: mat_max_order, order, l + integer :: mat_max_order, order, order_dim, nuc_order_dim real(8), allocatable :: temp_mult(:,:) real(8), allocatable :: scatt_coeffs(:,:,:) + ! Determine the scattering type of our data and ensure all scattering orders + ! are the same. + select type(nuc => nuclides(mat % nuclide(1)) % obj) + type is (NuclideIso) + order = size(nuc % scatter % dist(1) % data, dim=1) + end select ! If we have tabular only data, then make sure all datasets have same size if (scatt_type == ANGLE_HISTOGRAM) then - ! Check all scattering data of same size - order = nuclides(mat % nuclide(1)) % obj % order + ! Check all scattering data to ensure it is the same size + ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) do i = 2, mat % n_nuclides - if (order /= nuclides(mat % nuclide(i)) % obj % order) then - call fatal_error("All Histogram Scattering Entries Must Be Same Length!") - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideIso) + if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & + call fatal_error("All Histogram Scattering Entries Must Be& + & Same Length!") + end select end do - ! Ok, got our order, store it - this % order = order + ! Ok, got our order, store the dimensionality + order_dim = order - ! Allocate stuff for later - allocate(scatt_coeffs(order, groups, groups)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(ScattDataHistogram :: this % scatter) else if (scatt_type == ANGLE_TABULAR) then - ! Check all scattering data of same size - order = nuclides(mat % nuclide(1)) % obj % order + ! Check all scattering data to ensure it is the same size do i = 2, mat % n_nuclides - if (order /= nuclides(mat % nuclide(i)) % obj % order) then - call fatal_error("All Tabular Scattering Entries Must Be Same Length!") - return - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideIso) + if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & + call fatal_error("All Tabular Scattering Entries Must Be& + & Same Length!") + end select end do - ! Ok, got our order, store it - this % order = order + ! Ok, got our order, store the dimensionality + order_dim = order - ! Allocate stuff for later - allocate(scatt_coeffs(this % order, groups, groups)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(ScattDataTabular :: this % scatter) else if (scatt_type == ANGLE_LEGENDRE) then - ! Otherwise find the maximum scattering order ! Need to determine the maximum scattering order of all data in this material mat_max_order = 0 do i = 1, mat % n_nuclides - if (nuclides(mat % nuclide(i)) % obj % order > mat_max_order) then - mat_max_order = nuclides(mat % nuclide(i)) % obj % order - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideIso) + if (size(nuc % scatter % dist(1) % data,dim=1) > mat_max_order) & + mat_max_order = size(nuc % scatter % dist(1) % data,dim=1) + end select end do ! Now need to compare this material maximum scattering order with ! the problem wide max scatt order and use whichever is lower - order = min(mat_max_order, max_order) + 1 - this % order = order + order = min(mat_max_order, max_order) + ! Ok, got our order, store the dimensionality + order_dim = order + 1 - ! Now we can allocate our scatt_coeffs object accordingly - allocate(scatt_coeffs(this % order, groups, groups)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(ScattDataLegendre :: this % scatter) end if - ! Allocate and initialize data within macro_xs(i_mat) object + ! Allocate and initialize data needed for macro_xs(i_mat) object allocate(this % total(groups)) this % total = ZERO allocate(this % absorption(groups)) @@ -225,10 +227,12 @@ contains end if allocate(this % nu_fission(groups)) this % nu_fission = ZERO - allocate(this % chi(groups, groups)) + allocate(this % chi(groups,groups)) this % chi = ZERO - allocate(temp_mult(groups, groups)) + allocate(temp_mult(groups,groups)) temp_mult = ZERO + allocate(scatt_coeffs(order_dim,groups,groups)) + scatt_coeffs = ZERO ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -276,21 +280,23 @@ contains end do ! Get the complete scattering matrix - scatt_coeffs(1:min(nuc % order, order),:,:) = scatt_coeffs + & + nuc_order_dim = size(nuc % scatter % dist(1) % data,dim=1) + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) + & atom_density * & - nuc % scatter % get_matrix(min(nuc % order, order)) + nuc % scatter % get_matrix(min(nuc_order_dim,order_dim)) type is (NuclideAngle) call fatal_error("Invalid Passing of NuclideAngle to MacroXSIso Object") end select end do + ! Initialize the ScattData Object call this % scatter % init(temp_mult,scatt_coeffs) ! Now normalize chi if (mat % fissionable) then do gin = 1, groups - ! Normalize Chi norm = sum(this % chi(:,gin)) if (norm > ZERO) then this % chi(:,gin) = this % chi(:,gin) / norm @@ -298,7 +304,7 @@ contains end do end if - ! Deallocate temporaries for the next material + ! Deallocate temporaries deallocate(scatt_coeffs, temp_mult) end subroutine macroxsiso_init @@ -318,9 +324,8 @@ contains integer :: gin, gout ! group indices real(8) :: atom_density ! atom density of a nuclide integer :: ipol, iazi, n_pol, n_azi - integer :: imu real(8) :: norm - integer :: mat_max_order, order, l + integer :: mat_max_order, order, order_dim, nuc_order_dim real(8), allocatable :: temp_mult(:,:,:,:) real(8), allocatable :: scatt_coeffs(:,:,:,:,:) @@ -346,21 +351,28 @@ contains end select end do + ! Determine the scattering type of our data and ensure all scattering orders + ! are the same. + select type(nuc => nuclides(mat % nuclide(1)) % obj) + type is (NuclideAngle) + order = size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1) + end select ! If we have tabular only data, then make sure all datasets have same size if (scatt_type == ANGLE_HISTOGRAM) then - ! Check all scattering data of same size - order = nuclides(mat % nuclide(1)) % obj % order + ! Check all scattering data to ensure it is the same size + ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) do i = 2, mat % n_nuclides - if (order /= nuclides(mat % nuclide(i)) % obj % order) then - call fatal_error("All Histogram Scattering Entries Must Be Same Length!") - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideAngle) + if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + call fatal_error("All Histogram Scattering Entries Must Be& + & Same Length!") + end select end do - ! Ok, got our order, store it - this % order = order + ! Ok, got our order, store the dimensionality + order_dim = order - ! Allocate stuff for later - allocate(scatt_coeffs(this % order,groups,groups,n_azi,n_pol)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(this % scatter(n_azi, n_pol)) do ipol = 1, n_pol do iazi = 1, n_azi @@ -369,19 +381,19 @@ contains end do else if (scatt_type == ANGLE_TABULAR) then - ! Check all scattering data of same size - order = nuclides(mat % nuclide(1)) % obj % order + ! Check all scattering data to ensure it is the same size do i = 2, mat % n_nuclides - if (order /= nuclides(mat % nuclide(i)) % obj % order) then - call fatal_error("All Tabular Scattering Entries Must Be Same Length!") - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideAngle) + if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + call fatal_error("All Tabular Scattering Entries Must Be& + & Same Length!") + end select end do - ! Ok, got our order, store it - this % order = order + ! Ok, got our order, store the dimensionality + order_dim = order - ! Allocate stuff for later - allocate(scatt_coeffs(this % order, groups, groups, n_azi, n_pol)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(this % scatter(n_azi, n_pol)) do ipol = 1, n_pol do iazi = 1, n_azi @@ -390,23 +402,23 @@ contains end do else if (scatt_type == ANGLE_LEGENDRE) then - ! Otherwise find the maximum scattering order ! Need to determine the maximum scattering order of all data in this material mat_max_order = 0 do i = 1, mat % n_nuclides - if (nuclides(mat % nuclide(i)) % obj % order > mat_max_order) then - mat_max_order = nuclides(mat % nuclide(i)) % obj % order - end if + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (NuclideAngle) + if (size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) > mat_max_order) & + mat_max_order = size(nuc % scatter(1,1) % obj% dist(1) % data,dim=1) + end select end do ! Now need to compare this material maximum scattering order with ! the problem wide max scatt order and use whichever is lower order = min(mat_max_order, max_order) - this % order = order + 1 + ! Ok, got our order, store the dimensionality + order_dim = order + 1 - ! Now we can allocate our scatt_coeffs object accordingly - allocate(scatt_coeffs(this % order, groups, groups, n_azi, n_pol)) - scatt_coeffs = ZERO + ! Set our Scatter Object Type allocate(this % scatter(n_azi, n_pol)) do ipol = 1, n_pol do iazi = 1, n_azi @@ -430,10 +442,12 @@ contains end if allocate(this % nu_fission(groups,n_azi,n_pol)) this % nu_fission = ZERO - allocate(this % chi(groups, groups, n_azi, n_pol)) + allocate(this % chi(groups, groups,n_azi,n_pol)) this % chi = ZERO allocate(temp_mult(groups,groups,n_azi,n_pol)) temp_mult = ZERO + allocate(scatt_coeffs(order_dim,groups,groups,n_azi,n_pol)) + scatt_coeffs = ZERO ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -474,60 +488,35 @@ contains end if end if - ! Now time to do the scattering + ! Get the multiplication matrix do ipol = 1, n_pol do iazi = 1, n_azi do gin = 1, groups -!!! Needs to be updated to match iso!!! -! this % scattxs(gin,iazi,ipol) = this % scattxs(gin,iazi,ipol) + & -! atom_density * nuc % scattxs(gin,iazi,ipol) do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & - nuc % scatter(iazi,ipol) % obj % gmax(gin) - - ! Multiplicity matrix - temp_mult(gout,gin,iazi,ipol) = & - temp_mult(gout,gin,iazi,ipol) + atom_density * & - nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - - if (scatt_type == ANGLE_HISTOGRAM) then - ! Determine the angular distribution - do imu = 1, order - scatt_coeffs(imu,gout,gin,iazi,ipol) = & - scatt_coeffs(imu,gout,gin,iazi,ipol) + & - atom_density * & - nuc % scatter(iazi,ipol) % obj % dist(gin) % data(imu,gout) - end do - else if (scatt_type == ANGLE_TABULAR) then - select type(scatt =>nuc % scatter(iazi,ipol) % obj) - type is (ScattDataTabular) - do imu = 1, order - scatt_coeffs(imu,gout,gin,iazi,ipol) = & - scatt_coeffs(imu,gout,gin,iazi,ipol) + & - atom_density * scatt % fmu(gin) % data(imu,gout) - end do - end select - else if (scatt_type == ANGLE_LEGENDRE) then - ! Determine the angular distribution coefficients so we can later - ! expand do the complete distribution - do l = 1, min(nuc % order, order) + 1 - scatt_coeffs(l,gout,gin,iazi,ipol) = & - scatt_coeffs(l,gout,gin,iazi,ipol) + & - atom_density * & - nuc % scatter(iazi,ipol) % obj % dist(gin) % data(l,gout) - end do - end if - ! Incorporate outgoing energy PDF information - scatt_coeffs(:,gout,gin,iazi,ipol) = & - scatt_coeffs(:,gout,gin,iazi,ipol) * & - nuc % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + nuc % scatter(iazi,ipol) % obj % gmax(gin) + temp_mult(gout,gin,iazi,ipol) = temp_mult(gout,gin,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) end do end do end do end do + + ! Get the complete scattering matrix + nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) + do ipol = 1, n_pol + do iazi = 1, n_azi + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % get_matrix(& + min(nuc_order_dim,order_dim,iazi,ipol)) + end do + end do end select end do - ! Initialize the scattering data + ! Initialize the ScattData Object do ipol = 1, n_pol do iazi = 1, n_azi call this % scatter(iazi, ipol) % obj % init( & @@ -535,12 +524,11 @@ contains end do end do - ! Now go through and normalize chi + ! Now normalize chi if (mat % fissionable) then do ipol = 1, n_pol do iazi = 1, n_azi do gin = 1, groups - ! Normalize Chi norm = sum(this % chi(:,gin,iazi,ipol)) if (norm > ZERO) then this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / norm diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index 88d7ce0ea..d2020a1e0 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -107,9 +107,6 @@ module nuclide_header end type NuclideCE type, abstract, extends(Nuclide) :: NuclideMG - ! Scattering Order Information - integer :: order ! Order of data (Scattering for NuclideIso, - ! Number of angles for all in NuclideAngle) integer :: scatt_type ! either legendre, histogram, or tabular. contains procedure(nuclidemg_init_), deferred :: init ! Initialize the data @@ -301,7 +298,7 @@ module nuclide_header character(MAX_LINE_LEN) :: temp_str - ! Load the data + ! Load the nuclide metadata call get_node_value(node_xsdata, "name", this % name) this % name = to_lower(this % name) if (check_for_node(node_xsdata, "kT")) then @@ -330,12 +327,6 @@ module nuclide_header this % scatt_type = ANGLE_LEGENDRE end if - if (check_for_node(node_xsdata, "order")) then - call get_node_value(node_xsdata, "order", this % order) - else - call fatal_error("Order Must Be Provided!") - end if - if (check_for_node(node_xsdata, "fissionable")) then call get_node_value(node_xsdata, "fissionable", temp_str) temp_str = to_lower(temp_str) @@ -368,26 +359,26 @@ module nuclide_header real(8), allocatable :: input_scatt(:,:,:) real(8), allocatable :: temp_scatt(:,:,:) real(8) :: dmu, mu, norm - integer :: order_dim, gin, gout, l, arr_len + integer :: order, order_dim, gin, gout, l, arr_len integer :: legendre_mu_points, imu - ! Call generic data gathering routine + ! Call generic data gathering routine (will populate the metadata) call nuclidemg_init(this, node_xsdata) ! Load the more specific data if (this % fissionable) then - if (check_for_node(node_xsdata, "chi")) then + if (check_for_node(node_xsdata,"chi")) then ! Get chi allocate(this % chi(groups)) - call get_node_array(node_xsdata, "chi", this % chi) + call get_node_array(node_xsdata,"chi",this % chi) ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata, "nu_fission")) then + if (check_for_node(node_xsdata,"nu_fission")) then allocate(temp_arr(groups * 1)) - call get_node_array(node_xsdata, "nu_fission", temp_arr) - allocate(this % nu_fission(groups, 1)) - this % nu_fission = reshape(temp_arr, (/groups, 1/)) + call get_node_array(node_xsdata,"nu_fission",temp_arr) + allocate(this % nu_fission(groups,1)) + this % nu_fission = reshape(temp_arr,(/groups,1/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -395,21 +386,23 @@ module nuclide_header else ! Get nu_fission (as a matrix) - if (check_for_node(node_xsdata, "nu_fission")) then + if (check_for_node(node_xsdata,"nu_fission")) then allocate(temp_arr(groups*groups)) - call get_node_array(node_xsdata, "nu_fission", temp_arr) + call get_node_array(node_xsdata,"nu_fission",temp_arr) allocate(this % nu_fission(groups, groups)) - this % nu_fission = reshape(temp_arr, (/groups, groups/)) + this % nu_fission = reshape(temp_arr,(/groups,groups/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") end if end if + ! If we have a need* for the fission and kappa-fission x/s, get them + ! (*Need is defined as will be using it to tally) if (get_fiss) then allocate(this % fission(groups)) - if (check_for_node(node_xsdata, "fission")) then - call get_node_array(node_xsdata, "fission", this % fission) + if (check_for_node(node_xsdata,"fission")) then + call get_node_array(node_xsdata,"fission",this % fission) else call fatal_error("Fission data missing, required due to fission& & tallies in tallies.xml file!") @@ -417,8 +410,8 @@ module nuclide_header end if if (get_kfiss) then allocate(this % k_fission(groups)) - if (check_for_node(node_xsdata, "kappa_fission")) then - call get_node_array(node_xsdata, "kappa_fission", this % k_fission) + if (check_for_node(node_xsdata,"kappa_fission")) then + call get_node_array(node_xsdata,"kappa_fission",this % k_fission) else call fatal_error("kappa_fission data missing, required due to & &kappa-fission tallies in tallies.xml file!") @@ -427,17 +420,37 @@ module nuclide_header end if allocate(this % absorption(groups)) - if (check_for_node(node_xsdata, "absorption")) then - call get_node_array(node_xsdata, "absorption", this % absorption) + if (check_for_node(node_xsdata,"absorption")) then + call get_node_array(node_xsdata,"absorption",this % absorption) else call fatal_error("Must provide absorption!") end if - ! Get scattering treatment - if (check_for_node(node_xsdata, "tabular_legendre")) then - call get_node_ptr(node_xsdata, "tabular_legendre", node_legendre_mu) + ! Get multiplication data if present + allocate(temp_mult(groups, groups)) + if (check_for_node(node_xsdata,"multiplicity")) then + arr_len = get_arraysize_double(node_xsdata,"multiplicity") + if (arr_len == groups * groups) then + allocate(temp_arr(arr_len)) + call get_node_array(node_xsdata,"multiplicity",temp_arr) + temp_mult = reshape(temp_arr, (/groups, groups/)) + deallocate(temp_arr) + else + call fatal_error("Multiplicity length not same as number of groups& + & squared!") + end if + else + temp_mult = ONE + end if + + ! Get scattering treatment information + ! Tabular_legendre tells us if we are to treat the provided + ! Legendre polynomials as tabular data (if enable is true) or leaving + ! them as Legendres (if enable is false, or the default) + if (check_for_node(node_xsdata,"tabular_legendre")) then + call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu, "enable", temp_str) + call get_node_value(node_legendre_mu,"enable",temp_str) temp_str = trim(to_lower(temp_str)) if (temp_str == 'true' .or. temp_str == '1') then enable_leg_mu = .true. @@ -447,48 +460,62 @@ module nuclide_header call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) end if else - enable_leg_mu = .true. - legendre_mu_points = 33 + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. end if - if (enable_leg_mu .and. & - check_for_node(node_legendre_mu, "num_points")) then - call get_node_value(node_legendre_mu, "num_points", & - legendre_mu_points) - if (legendre_mu_points <= 0) then - call fatal_error("num_points element must be positive and non-zero!") + ! Ok, so if we need to convert to a tabular form, get the user provided + ! number of points + if (enable_leg_mu) then + if (check_for_node(node_legendre_mu,"num_points")) then + call get_node_value(node_legendre_mu,"num_points", & + legendre_mu_points) + if (legendre_mu_points <= 0) & + call fatal_error("num_points element must be positive& + & and non-zero!") + else + ! Set the default number of points (0.0625 spacing) + legendre_mu_points = 33 end if end if end if - if (this % scatt_type == ANGLE_LEGENDRE) then - order_dim = this % order + 1 - else if (this % scatt_type == ANGLE_HISTOGRAM) then - order_dim = this % order - else if (this % scatt_type == ANGLE_TABULAR) then - order_dim = this % order + ! Get the library's value for the order + if (check_for_node(node_xsdata,"order")) then + call get_node_value(node_xsdata,"order",order) + else + call fatal_error("Order Must Be Provided!") end if + ! Before retrieving the data, store the dimensionality of the data in + ! order_dim. For Legendre data, we usually refer to it as Pn where + ! n is the order. However Pn has n+1 sets of points (since you need to + ! the count the P0 moment). Adjust for that. Histogram and Tabular + ! formats dont need this adjustment. + if (this % scatt_type == ANGLE_LEGENDRE) then + order_dim = order + 1 + else + order_dim = order + end if + + ! The input is gathered in the more user-friendly facing format of + ! Gout x Gin x Order. We will get it in that format in input_scatt, + ! but then need to convert it to a more useful ordering for processing + ! (Order x Gout x Gin). allocate(input_scatt(groups, groups, order_dim)) - if (check_for_node(node_xsdata, "scatter")) then + if (check_for_node(node_xsdata,"scatter")) then allocate(temp_arr(groups * groups * order_dim)) - call get_node_array(node_xsdata, "scatter", temp_arr) - input_scatt = reshape(temp_arr, (/groups, groups, order_dim/)) + call get_node_array(node_xsdata,"scatter",temp_arr) + input_scatt = reshape(temp_arr,(/groups,groups,order_dim/)) deallocate(temp_arr) ! Compare the number of orders given with the maximum order of the ! problem. Strip off the supefluous orders if needed. if (this % scatt_type == ANGLE_LEGENDRE) then - order_dim = min(order_dim, max_order + 1) - this % order = order_dim + order = min(order_dim - 1, max_order) + order_dim = order + 1 end if - allocate(temp_scatt(groups, groups, order_dim)) - do gin = 1, groups - do gout = 1, groups - do l = 1, order_dim - temp_scatt(gout,gin,l) = input_scatt(gout,gin,l) - end do - end do - end do + allocate(temp_scatt(groups,groups,order_dim)) + temp_scatt(:,:,:) = input_scatt(:,:,1:order_dim) ! Take input format (groups, groups, order) and convert to ! the more useful format needed for scattdata: (order, groups, groups) @@ -500,10 +527,10 @@ module nuclide_header ! Convert input parameters to what we need for the rest. this % scatt_type = ANGLE_TABULAR order_dim = legendre_mu_points - this % order = order_dim - dmu = TWO / real(this % order - 1,8) + order = order_dim + dmu = TWO / real(order - 1,8) - allocate(scatt_coeffs(order_dim, groups, groups)) + allocate(scatt_coeffs(order_dim,groups,groups)) do gin = 1, groups do gout = 1, groups norm = ZERO @@ -517,13 +544,17 @@ module nuclide_header end if scatt_coeffs(imu,gout,gin) = & evaluate_legendre(temp_scatt(gout,gin,:),mu) + ! Ensure positivity of distribution if (scatt_coeffs(imu,gout,gin) < ZERO) & scatt_coeffs(imu,gout,gin) = ZERO + ! And accrue the integral if (imu > 1) then norm = norm + HALF * dmu * (scatt_coeffs(imu-1,gout,gin) + & scatt_coeffs(imu,gout,gin)) end if end do + ! Now that we have the integral, lets ensure that the distribution + ! is normalized such that it preserves the original scattering xs if (norm > ZERO) then scatt_coeffs(:,gout,gin) = scatt_coeffs(:,gout,gin) * & temp_scatt(gout,gin,1) / norm @@ -533,7 +564,7 @@ module nuclide_header else ! Sticking with current representation, carry forward but change ! the array ordering - allocate(scatt_coeffs(order_dim, groups, groups)) + allocate(scatt_coeffs(order_dim,groups,groups)) do gin = 1, groups do gout = 1, groups do l = 1, order_dim @@ -545,28 +576,9 @@ module nuclide_header deallocate(temp_scatt) else call fatal_error("Must provide scatter!") - return end if - ! Get Mult Data - allocate(temp_mult(groups, groups)) - if (check_for_node(node_xsdata, "multiplicity")) then - arr_len = get_arraysize_double(node_xsdata, "multiplicity") - if (arr_len == groups * groups) then - allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata, "multiplicity", temp_arr) - temp_mult = reshape(temp_arr, (/groups, groups/)) - deallocate(temp_arr) - else - call fatal_error("Multiplicity length not same as number of groups& - & squared!") - return - end if - else - temp_mult = ONE - end if - - ! Allocate and initialize our ScattData Object.. + ! Allocate and initialize our ScattData Object. if (this % scatt_type == ANGLE_HISTOGRAM) then allocate(ScattDataHistogram :: this % scatter) else if (this % scatt_type == ANGLE_TABULAR) then @@ -576,18 +588,18 @@ module nuclide_header end if ! Initialize the ScattData Object - call this % scatter % init(temp_mult, scatt_coeffs(:,:,:)) + call this % scatter % init(temp_mult, scatt_coeffs) ! Get, or infer, total xs data. allocate(this % total(groups)) - if (check_for_node(node_xsdata, "total")) then - call get_node_array(node_xsdata, "total", this % total) + if (check_for_node(node_xsdata,"total")) then + call get_node_array(node_xsdata,"total",this % total) else this % total = this % absorption + this % scatter % scattxs end if ! Deallocate temporaries for the next material - deallocate(scatt_coeffs, temp_mult) + deallocate(input_scatt,scatt_coeffs,temp_mult) end subroutine nuclideiso_init @@ -600,168 +612,331 @@ module nuclide_header logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order - real(8), allocatable :: temp_arr(:) - integer :: arr_len - real(8) :: dangle - integer :: iangle - integer :: order_dim + type(Node), pointer :: node_legendre_mu + character(MAX_LINE_LEN) :: temp_str + logical :: enable_leg_mu + real(8), allocatable :: temp_arr(:) + real(8), allocatable :: temp_mult(:,:,:,:) + real(8), allocatable :: scatt_coeffs(:,:,:,:,:) + real(8), allocatable :: input_scatt(:,:,:,:,:) + real(8), allocatable :: temp_scatt(:,:,:,:,:) + real(8) :: dmu, mu, norm, dangle + integer :: order, order_dim, gin, gout, l, arr_len + integer :: legendre_mu_points, imu, i_pol, i_azi - ! Call generic data gathering routine + ! Call generic data gathering routine (will populate the metadata) call nuclidemg_init(this, node_xsdata) - if (this % scatt_type == ANGLE_LEGENDRE) then - order_dim = this % order + 1 - else if (this % scatt_type == ANGLE_HISTOGRAM) then - order_dim = this % order - else if (this % scatt_type == ANGLE_TABULAR) then - order_dim = this % order + if (check_for_node(node_xsdata, "num_polar")) then + call get_node_value(node_xsdata, "num_polar", this % n_pol) + else + call fatal_error("num_polar Must Be Provided!") end if - ! if (check_for_node(node_xsdata, "num_polar")) then - ! call get_node_value(node_xsdata, "num_polar", this % n_pol) - ! else - ! call fatal_error("num_polar Must Be Provided!") - ! end if + if (check_for_node(node_xsdata, "num_azimuthal")) then + call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) + else + call fatal_error("num_azimuthal Must Be Provided!") + end if - ! if (check_for_node(node_xsdata, "num_azimuthal")) then - ! call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) - ! else - ! call fatal_error("num_azimuthal Must Be Provided!") - ! end if + ! Load angle data, if present (else equally spaced) + allocate(this % polar(this % n_pol)) + allocate(this % azimuthal(this % n_azi)) + if (check_for_node(node_xsdata, "polar")) then + call fatal_error("User-Specified polar angle bins not yet supported!") + ! When this feature is supported, this line will be activated + call get_node_array(node_xsdata, "polar", this % polar) + else + dangle = PI / real(this % n_pol,8) + do i_pol = 1, this % n_pol + this % polar(i_pol) = (real(i_pol,8) - HALF) * dangle + end do + end if + if (check_for_node(node_xsdata, "azimuthal")) then + call fatal_error("User-Specified azimuthal angle bins not yet supported!") + ! When this feature is supported, this line will be activated + call get_node_array(node_xsdata, "azimuthal", this % azimuthal) + else + dangle = TWO * PI / real(this % n_azi,8) + do i_azi = 1, this % n_azi + this % azimuthal(i_azi) = -PI + (real(i_azi,8) - HALF) * dangle + end do + end if - ! ! Load angle data, if present (else equally spaced) - ! allocate(this % polar(this % n_pol)) - ! allocate(this % azimuthal(this % n_azi)) - ! if (check_for_node(node_xsdata, "polar")) then - ! call fatal_error("User-Specified polar angle bins not yet supported!") - ! ! When this feature is supported, this line will be activated - ! call get_node_array(node_xsdata, "polar", this % polar) - ! else - ! dangle = PI / real(this % n_pol,8) - ! do iangle = 1, this % n_pol - ! this % polar(iangle) = (real(iangle,8) - HALF) * dangle - ! end do - ! end if - ! if (check_for_node(node_xsdata, "azimuthal")) then - ! call fatal_error("User-Specified azimuthal angle bins not yet supported!") - ! ! When this feature is supported, this line will be activated - ! call get_node_array(node_xsdata, "azimuthal", this % azimuthal) - ! else - ! dangle = TWO * PI / real(this % n_azi,8) - ! do iangle = 1, this % n_azi - ! this % azimuthal(iangle) = -PI + (real(iangle,8) - HALF) * dangle - ! end do - ! end if + ! Load the more specific data + if (this % fissionable) then - ! ! Load the more specific data - ! if (this % fissionable) then + if (check_for_node(node_xsdata,"chi")) then + ! Get chi + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"chi",temp_arr) + allocate(this % chi(groups,this % n_azi,this % n_pol)) + this % chi = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) - ! if (check_for_node(node_xsdata, "chi")) then - ! ! Get chi - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "chi", temp_arr) - ! allocate(this % chi(groups, this % n_azi, this % n_pol)) - ! this % chi = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) + ! Get nu_fission (as a vector) + if (check_for_node(node_xsdata,"nu_fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"nu_fission", temp_arr) + allocate(this % nu_fission(groups,1,this % n_azi,this % n_pol)) + this % nu_fission = reshape(temp_arr, (/groups,1,this % n_azi, & + this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if - ! ! Get nu_fission (as a vector) - ! if (check_for_node(node_xsdata, "nu_fission")) then - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "nu_fission", temp_arr) - ! allocate(this % nu_fission(groups, 1, this % n_azi, this % n_pol)) - ! this % nu_fission = reshape(temp_arr, (/groups, 1, this % n_azi, & - ! this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("If fissionable, must provide nu_fission!") - ! end if + else + ! Get nu_fission (as a matrix) + if (check_for_node(node_xsdata,"nu_fission")) then - ! else - ! ! Get nu_fission (as a matrix) - ! if (check_for_node(node_xsdata, "nu_fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"nu_fission",temp_arr) + allocate(this % nu_fission(groups,groups,this % n_azi,this % n_pol)) + this % nu_fission = reshape(temp_arr,(/groups,groups, & + this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if + end if + ! If we have a need* for the fission and kappa-fission x/s, get them + ! (*Need is defined as will be using it to tally) + if (get_fiss) then + if (check_for_node(node_xsdata,"fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"fission",temp_arr) + allocate(this % fission(groups,this % n_azi,this % n_pol)) + this % fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Fission data missing, required due to fission& + & tallies in tallies.xml file!") + end if + end if + if (get_kfiss) then + if (check_for_node(node_xsdata,"kappa_fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"kappa_fission",temp_arr) + allocate(this % k_fission(groups,this % n_azi,this % n_pol)) + this % k_fission = reshape(temp_arr,(/groups, this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("kappa_fission data missing, required due to & + &kappa-fission tallies in tallies.xml file!") + end if + end if + end if - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "nu_fission", temp_arr) - ! allocate(this % nu_fission(groups, groups, this % n_azi, this % n_pol)) - ! this % nu_fission = reshape(temp_arr, (/groups, groups, & - ! this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("If fissionable, must provide nu_fission!") - ! end if - ! end if - ! if (get_fiss) then - ! if (check_for_node(node_xsdata, "fission")) then - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "fission", temp_arr) - ! allocate(this % fission(groups, this % n_azi, this % n_pol)) - ! this % fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("Fission data missing, required due to fission& - ! & tallies in tallies.xml file!") - ! end if - ! end if - ! if (get_kfiss) then - ! if (check_for_node(node_xsdata, "kappa_fission")) then - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "kappa_fission", temp_arr) - ! allocate(this % k_fission(groups, this % n_azi, this % n_pol)) - ! this % k_fission = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("kappa_fission data missing, required due to & - ! &kappa-fission tallies in tallies.xml file!") - ! end if - ! end if - ! end if + if (check_for_node(node_xsdata,"absorption")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"absorption",temp_arr) + allocate(this % absorption(groups,this % n_azi,this % n_pol)) + this % absorption = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Must provide absorption!") + end if - ! if (check_for_node(node_xsdata, "absorption")) then - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "absorption", temp_arr) - ! allocate(this % absorption(groups, this % n_azi, this % n_pol)) - ! this % absorption = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("Must provide absorption!") - ! end if + ! Get multiplication data if present + allocate(temp_mult(groups,groups,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"multiplicity")) then + arr_len = get_arraysize_double(node_xsdata,"multiplicity") + if (arr_len == groups * groups * this % n_azi * this % n_pol) then + allocate(temp_arr(arr_len)) + call get_node_array(node_xsdata,"multiplicity",temp_arr) + temp_mult = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Multiplicity length not same as number of groups& + & squared!") + end if + else + temp_mult = ONE + end if - ! allocate(this % scatter(groups, groups, order_dim, this % n_azi, this % n_pol)) - ! if (check_for_node(node_xsdata, "scatter")) then - ! allocate(temp_arr(groups * groups * order_dim * this % n_azi * this%n_pol)) - ! call get_node_array(node_xsdata, "scatter", temp_arr) - ! this % scatter = reshape(temp_arr, (/groups, groups, order_dim, & - ! this%n_azi,this%n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("Must provide scatter!") - ! end if + ! Get scattering treatment information + ! Tabular_legendre tells us if we are to treat the provided + ! Legendre polynomials as tabular data (if enable is true) or leaving + ! them as Legendres (if enable is false, or the default) + if (check_for_node(node_xsdata,"tabular_legendre")) then + call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) + if (check_for_node(node_legendre_mu, "enable")) then + call get_node_value(node_legendre_mu,"enable",temp_str) + temp_str = trim(to_lower(temp_str)) + if (temp_str == 'true' .or. temp_str == '1') then + enable_leg_mu = .true. + elseif (temp_str == 'false' .or. temp_str == '0') then + enable_leg_mu = .false. + else + call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + end if + else + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. + end if + ! Ok, so if we need to convert to a tabular form, get the user provided + ! number of points + if (enable_leg_mu) then + if (check_for_node(node_legendre_mu,"num_points")) then + call get_node_value(node_legendre_mu,"num_points", & + legendre_mu_points) + if (legendre_mu_points <= 0) & + call fatal_error("num_points element must be positive& + & and non-zero!") + else + ! Set the default number of points (0.0625 spacing) + legendre_mu_points = 33 + end if + end if + end if - ! if (check_for_node(node_xsdata, "total")) then - ! allocate(temp_arr(groups * this % n_azi * this % n_pol)) - ! call get_node_array(node_xsdata, "total", temp_arr) - ! allocate(this % total(groups, this % n_azi, this % n_pol)) - ! this % total = reshape(temp_arr, (/groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! this % total = this % absorption + sum(this%scatter(:,:,1,:,:),dim=1) - ! end if + ! Get the library's value for the order + if (check_for_node(node_xsdata,"order")) then + call get_node_value(node_xsdata,"order",order) + else + call fatal_error("Order Must Be Provided!") + end if - ! ! Get Mult Data - ! allocate(this % mult(groups, groups, this % n_azi, this % n_pol)) - ! if (check_for_node(node_xsdata, "multiplicity")) then - ! arr_len = get_arraysize_double(node_xsdata, "multiplicity") - ! if (arr_len == groups * groups * this % n_azi * this % n_pol) then - ! allocate(temp_arr(arr_len)) - ! call get_node_array(node_xsdata, "multiplicity", temp_arr) - ! this % mult = reshape(temp_arr, (/groups, groups, this % n_azi, this % n_pol/)) - ! deallocate(temp_arr) - ! else - ! call fatal_error("Multiplicity Length Does Not Match!") - ! end if - ! else - ! this % mult = ONE - ! end if + ! Before retrieving the data, store the dimensionality of the data in + ! order_dim. For Legendre data, we usually refer to it as Pn where + ! n is the order. However Pn has n+1 sets of points (since you need to + ! the count the P0 moment). Adjust for that. Histogram and Tabular + ! formats dont need this adjustment. + if (this % scatt_type == ANGLE_LEGENDRE) then + order_dim = order + 1 + else + order_dim = order + end if + + ! The input is gathered in the more user-friendly facing format of + ! Gout x Gin x Order x Azi x Pol. We will get it in that format in + ! input_scatt, but then need to convert it to a more useful ordering + ! for processing (Order x Gout x Gin x Azi x Pol). + allocate(input_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"scatter")) then + allocate(temp_arr(groups * groups * order_dim * this % n_azi * & + this % n_pol)) + call get_node_array(node_xsdata,"scatter",temp_arr) + input_scatt = reshape(temp_arr,(/groups,groups,order_dim,this % n_azi, & + this % n_pol/)) + deallocate(temp_arr) + + ! Compare the number of orders given with the maximum order of the + ! problem. Strip off the supefluous orders if needed. + if (this % scatt_type == ANGLE_LEGENDRE) then + order = min(order_dim - 1, max_order) + order_dim = order + 1 + end if + allocate(temp_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) + temp_scatt(:,:,:,:,:) = input_scatt(:,:,1:order_dim,:,:) + + ! Take input format (groups, groups, order) and convert to + ! the more useful format needed for scattdata: (order, groups, groups) + ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was + ! provided as Legendre coefficients), and the user requested that + ! these legendres be converted to tabular form (note this is also + ! the default behavior), convert that now. + if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then + ! Convert input parameters to what we need for the rest. + this % scatt_type = ANGLE_TABULAR + order_dim = legendre_mu_points + order = order_dim + dmu = TWO / real(order - 1,8) + + allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + do i_pol = 1, this % n_pol + do i_azi = 1, this % n_azi + do gin = 1, groups + do gout = 1, groups + norm = ZERO + do imu = 1, order_dim + if (imu == 1) then + mu = -ONE + else if (imu == order_dim) then + mu = ONE + else + mu = -ONE + real(imu - 1,8) * dmu + end if + scatt_coeffs(imu,gout,gin,i_azi,i_pol) = & + evaluate_legendre(temp_scatt(gout,gin,:,i_azi,i_pol),mu) + ! Ensure positivity of distribution + if (scatt_coeffs(imu,gout,gin,i_azi,i_pol) < ZERO) & + scatt_coeffs(imu,gout,gin,i_azi,i_pol) = ZERO + ! And accrue the integral + if (imu > 1) then + norm = norm + HALF * dmu * & + (scatt_coeffs(imu-1,gout,gin,i_azi,i_pol) + & + scatt_coeffs(imu,gout,gin,i_azi,i_pol)) + end if + end do + ! Now that we have the integral, lets ensure that the distribution + ! is normalized such that it preserves the original scattering xs + if (norm > ZERO) then + scatt_coeffs(:,gout,gin,i_azi,i_pol) = & + scatt_coeffs(:,gout,gin,i_azi,i_pol) * & + temp_scatt(gout,gin,1,i_azi,i_pol) / norm + end if + end do + end do + end do + end do + else + ! Sticking with current representation, carry forward but change + ! the array ordering + allocate(scatt_coeffs(order_dim,groups,groups,i_azi,i_pol)) + do i_pol = 1, this % n_pol + do i_azi = 1, this % n_azi + do gin = 1, groups + do gout = 1, groups + do l = 1, order_dim + scatt_coeffs(l,gout,gin,i_azi,i_pol) = & + temp_scatt(gout,gin,l,i_azi,i_pol) + end do + end do + end do + end do + end do + end if + deallocate(temp_scatt) + else + call fatal_error("Must provide scatter!") + end if + + allocate(this % scatter(this % n_azi, this % n_pol)) + do i_pol = 1, this % n_pol + do i_azi = 1, this % n_azi + ! Allocate and initialize our ScattData Object. + if (this % scatt_type == ANGLE_HISTOGRAM) then + allocate(ScattDataHistogram :: this % scatter(i_azi,i_pol) % obj) + else if (this % scatt_type == ANGLE_TABULAR) then + allocate(ScattDataTabular :: this % scatter(i_azi,i_pol) % obj) + else if (this % scatt_type == ANGLE_LEGENDRE) then + allocate(ScattDataLegendre :: this % scatter(i_azi,i_pol) % obj) + end if + + ! Initialize the ScattData Object + call this % scatter(i_azi,i_pol) % obj % init(& + temp_mult(:,:,i_azi,i_pol), scatt_coeffs(:,:,:,i_azi,i_pol)) + end do + end do + ! Deallocate temporaries for the next material + deallocate(input_scatt,scatt_coeffs,temp_mult) + + allocate(this % total(groups,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"total")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"total",temp_arr) + this % total = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + do i_pol = 1, this % n_pol + do i_azi = 1, this % n_azi + this % total(:,i_azi,i_pol) = this % absorption(:,i_azi,i_pol) + & + this % scatter(i_azi,i_pol) % obj % scattxs(:) + end do + end do + end if end subroutine nuclideangle_init @@ -886,17 +1061,27 @@ module nuclide_header if (this % scatt_type == ANGLE_LEGENDRE) then temp_str = "Legendre" write(unit_,*) ' Scattering Type = ' // trim(temp_str) - write(unit_,*) ' # of Scatter Moments = ' // & - trim(to_str(this % order)) + select type(this) + type is (NuclideIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1) + end select + write(unit_,*) ' Scattering Order = ' // trim(temp_str) else if (this % scatt_type == ANGLE_HISTOGRAM) then temp_str = "Histogram" write(unit_,*) ' Scattering Type = ' // trim(temp_str) - write(unit_,*) ' # of Scatter Bins = ' // & - trim(to_str(this % order)) + select type(this) + type is (NuclideIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) + end select + write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) else if (this % scatt_type == ANGLE_TABULAR) then temp_str = "Tabular" write(unit_,*) ' Scattering Type = ' // trim(temp_str) - write(unit_,*) ' # of Scatter Points = ' // trim(to_str(this % order)) + select type(this) + type is (NuclideIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) + end select + write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) end if write(unit_,*) ' Fissionable = ', this % fissionable @@ -926,9 +1111,9 @@ module nuclide_header do gin = 1, size(this % scatter % energy) size_scattmat = size_scattmat + & 2 * size(this % scatter % energy(gin) % data) + & - size(this % scatter % dist(gin) % data) + & - size(this % scatter % scattxs) + size(this % scatter % dist(gin) % data) end do + size_scattmat = size_scattmat + size(this % scatter % scattxs) size_scattmat = size_scattmat * 8 size_mgxs = size(this % total) + size(this % absorption) + & @@ -981,6 +1166,8 @@ module nuclide_header 2 * size(this % scatter(i_azi,i_pol) % obj % energy(gin) % data) + & size(this % scatter(i_azi,i_pol) % obj % dist(gin) % data) end do + size_scattmat = size_scattmat + & + size(this % scatter(i_azi,i_pol) % obj % scattxs) end do end do size_scattmat = size_scattmat * 8 diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 003b31d87..cf965f397 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -41,8 +41,7 @@ module scattdata_header procedure(scattdata_init_), deferred :: init ! Initializes ScattData procedure(scattdata_calc_f_), deferred :: calc_f ! Calculates f, given mu procedure(scattdata_sample_), deferred :: sample ! sample the scatter event - ! Reproduces an unnormalized scattering matrix - procedure :: get_matrix => scattdata_get_matrix + procedure :: get_matrix => scattdata_get_matrix ! Rebuild scattering matrix end type ScattData abstract interface @@ -55,7 +54,7 @@ module scattdata_header pure function scattdata_calc_f_(this, gin, gout, mu) result(f) import ScattData - class(ScattData), intent(in) :: this !! Scattering Object to work with + class(ScattData), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: gin ! Incoming Energy Group integer, intent(in) :: gout ! Outgoing Energy Group real(8), intent(in) :: mu ! Angle of interest @@ -65,7 +64,7 @@ module scattdata_header subroutine scattdata_sample_(this, gin, gout, mu, wgt) import ScattData - class(ScattData), intent(in) :: this !! Scattering Object to work with + class(ScattData), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: gin ! Incoming neutron group integer, intent(out) :: gout ! Sampled outgoin group real(8), intent(out) :: mu ! Sampled change in angle @@ -80,7 +79,6 @@ module scattdata_header procedure :: init => scattdatalegendre_init procedure :: calc_f => scattdatalegendre_calc_f procedure :: sample => scattdatalegendre_sample - ! procedure :: get_matrix => scattdatalegendre_get_matrix end type ScattDataLegendre type, extends(ScattData) :: ScattDataHistogram @@ -90,7 +88,6 @@ module scattdata_header procedure :: init => scattdatahistogram_init procedure :: calc_f => scattdatahistogram_calc_f procedure :: sample => scattdatahistogram_sample - ! procedure :: get_matrix => scattdatahistogram_get_matrix end type ScattDataHistogram type, extends(ScattData) :: ScattDataTabular From 33f74b5c909e884a593c420a3488f451f7db85b1 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 9 Mar 2016 06:48:10 -0500 Subject: [PATCH 008/147] tested nuclideangle implementation and worked out some kinks after my changes the other day --- src/macroxs_header.F90 | 6 +- src/nuclide_header.F90 | 148 ++++++++++++++++++++------------------- src/scattdata_header.F90 | 77 ++++++++++++++------ 3 files changed, 133 insertions(+), 98 deletions(-) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index 9eb3ea864..f86da1729 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -506,11 +506,11 @@ contains nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) do ipol = 1, n_pol do iazi = 1, n_azi - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) = & + scatt_coeffs(1:min(nuc_order_dim,order_dim),:,:,iazi,ipol) = & scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) + & atom_density * & nuc % scatter(iazi,ipol) % obj % get_matrix(& - min(nuc_order_dim,order_dim,iazi,ipol)) + min(nuc_order_dim,order_dim)) end do end do end select @@ -519,7 +519,7 @@ contains ! Initialize the ScattData Object do ipol = 1, n_pol do iazi = 1, n_azi - call this % scatter(iazi, ipol) % obj % init( & + call this % scatter(iazi,ipol) % obj % init( & temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) end do end do diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index d2020a1e0..e4dc717a8 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -126,7 +126,7 @@ module nuclide_header integer, intent(in) :: max_order ! Maximum requested order end subroutine nuclidemg_init_ - function nuclidemg_get_xs_(this, g, xstype, gout, uvw, mu, i_azi, i_pol) & + function nuclidemg_get_xs_(this, g, xstype, gout, uvw, mu, iazi, ipol) & result(xs) import NuclideMG class(NuclideMG), intent(in) :: this @@ -135,20 +135,20 @@ module nuclide_header integer, optional, intent(in) :: gout ! Outgoing Group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: i_azi ! Azimuthal Index - integer, optional, intent(in) :: i_pol ! Polar Index + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index real(8) :: xs ! Resultant xs end function nuclidemg_get_xs_ - pure function nuclidemg_calc_f_(this, gin, gout, mu, uvw, i_azi, i_pol) result(f) + pure function nuclidemg_calc_f_(this, gin, gout, mu, uvw, iazi, ipol) result(f) import NuclideMG class(NuclideMG), intent(in) :: this integer, intent(in) :: gin ! Incoming Energy Group integer, intent(in) :: gout ! Outgoing Energy Group real(8), intent(in) :: mu ! Angle of interest real(8), intent(in), optional :: uvw(3) ! Direction vector - integer, intent(in), optional :: i_azi ! Incoming Energy Group - integer, intent(in), optional :: i_pol ! Outgoing Energy Group + integer, intent(in), optional :: iazi ! Incoming Energy Group + integer, intent(in), optional :: ipol ! Outgoing Energy Group real(8) :: f ! Return value of f(mu) end function nuclidemg_calc_f_ @@ -447,6 +447,9 @@ module nuclide_header ! Tabular_legendre tells us if we are to treat the provided ! Legendre polynomials as tabular data (if enable is true) or leaving ! them as Legendres (if enable is false, or the default) + + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. if (check_for_node(node_xsdata,"tabular_legendre")) then call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) if (check_for_node(node_legendre_mu, "enable")) then @@ -459,9 +462,6 @@ module nuclide_header else call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) end if - else - ! Set the default (leave as Legendre polynomials) - enable_leg_mu = .false. end if ! Ok, so if we need to convert to a tabular form, get the user provided ! number of points @@ -622,7 +622,7 @@ module nuclide_header real(8), allocatable :: temp_scatt(:,:,:,:,:) real(8) :: dmu, mu, norm, dangle integer :: order, order_dim, gin, gout, l, arr_len - integer :: legendre_mu_points, imu, i_pol, i_azi + integer :: legendre_mu_points, imu, ipol, iazi ! Call generic data gathering routine (will populate the metadata) call nuclidemg_init(this, node_xsdata) @@ -648,8 +648,8 @@ module nuclide_header call get_node_array(node_xsdata, "polar", this % polar) else dangle = PI / real(this % n_pol,8) - do i_pol = 1, this % n_pol - this % polar(i_pol) = (real(i_pol,8) - HALF) * dangle + do ipol = 1, this % n_pol + this % polar(ipol) = (real(ipol,8) - HALF) * dangle end do end if if (check_for_node(node_xsdata, "azimuthal")) then @@ -658,8 +658,8 @@ module nuclide_header call get_node_array(node_xsdata, "azimuthal", this % azimuthal) else dangle = TWO * PI / real(this % n_azi,8) - do i_azi = 1, this % n_azi - this % azimuthal(i_azi) = -PI + (real(i_azi,8) - HALF) * dangle + do iazi = 1, this % n_azi + this % azimuthal(iazi) = -PI + (real(iazi,8) - HALF) * dangle end do end if @@ -759,6 +759,9 @@ module nuclide_header ! Tabular_legendre tells us if we are to treat the provided ! Legendre polynomials as tabular data (if enable is true) or leaving ! them as Legendres (if enable is false, or the default) + + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. if (check_for_node(node_xsdata,"tabular_legendre")) then call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) if (check_for_node(node_legendre_mu, "enable")) then @@ -771,9 +774,6 @@ module nuclide_header else call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) end if - else - ! Set the default (leave as Legendre polynomials) - enable_leg_mu = .false. end if ! Ok, so if we need to convert to a tabular form, get the user provided ! number of points @@ -828,6 +828,7 @@ module nuclide_header order = min(order_dim - 1, max_order) order_dim = order + 1 end if + allocate(temp_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) temp_scatt(:,:,:,:,:) = input_scatt(:,:,1:order_dim,:,:) @@ -838,6 +839,7 @@ module nuclide_header ! these legendres be converted to tabular form (note this is also ! the default behavior), convert that now. if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then + ! Convert input parameters to what we need for the rest. this % scatt_type = ANGLE_TABULAR order_dim = legendre_mu_points @@ -845,8 +847,8 @@ module nuclide_header dmu = TWO / real(order - 1,8) allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) - do i_pol = 1, this % n_pol - do i_azi = 1, this % n_azi + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi do gin = 1, groups do gout = 1, groups norm = ZERO @@ -858,24 +860,24 @@ module nuclide_header else mu = -ONE + real(imu - 1,8) * dmu end if - scatt_coeffs(imu,gout,gin,i_azi,i_pol) = & - evaluate_legendre(temp_scatt(gout,gin,:,i_azi,i_pol),mu) + scatt_coeffs(imu,gout,gin,iazi,ipol) = & + evaluate_legendre(temp_scatt(gout,gin,:,iazi,ipol),mu) ! Ensure positivity of distribution - if (scatt_coeffs(imu,gout,gin,i_azi,i_pol) < ZERO) & - scatt_coeffs(imu,gout,gin,i_azi,i_pol) = ZERO + if (scatt_coeffs(imu,gout,gin,iazi,ipol) < ZERO) & + scatt_coeffs(imu,gout,gin,iazi,ipol) = ZERO ! And accrue the integral if (imu > 1) then norm = norm + HALF * dmu * & - (scatt_coeffs(imu-1,gout,gin,i_azi,i_pol) + & - scatt_coeffs(imu,gout,gin,i_azi,i_pol)) + (scatt_coeffs(imu-1,gout,gin,iazi,ipol) + & + scatt_coeffs(imu,gout,gin,iazi,ipol)) end if end do ! Now that we have the integral, lets ensure that the distribution ! is normalized such that it preserves the original scattering xs if (norm > ZERO) then - scatt_coeffs(:,gout,gin,i_azi,i_pol) = & - scatt_coeffs(:,gout,gin,i_azi,i_pol) * & - temp_scatt(gout,gin,1,i_azi,i_pol) / norm + scatt_coeffs(:,gout,gin,iazi,ipol) = & + scatt_coeffs(:,gout,gin,iazi,ipol) * & + temp_scatt(gout,gin,1,iazi,ipol) / norm end if end do end do @@ -884,14 +886,14 @@ module nuclide_header else ! Sticking with current representation, carry forward but change ! the array ordering - allocate(scatt_coeffs(order_dim,groups,groups,i_azi,i_pol)) - do i_pol = 1, this % n_pol - do i_azi = 1, this % n_azi + allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi do gin = 1, groups do gout = 1, groups do l = 1, order_dim - scatt_coeffs(l,gout,gin,i_azi,i_pol) = & - temp_scatt(gout,gin,l,i_azi,i_pol) + scatt_coeffs(l,gout,gin,iazi,ipol) = & + temp_scatt(gout,gin,l,iazi,ipol) end do end do end do @@ -904,20 +906,20 @@ module nuclide_header end if allocate(this % scatter(this % n_azi, this % n_pol)) - do i_pol = 1, this % n_pol - do i_azi = 1, this % n_azi + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi ! Allocate and initialize our ScattData Object. if (this % scatt_type == ANGLE_HISTOGRAM) then - allocate(ScattDataHistogram :: this % scatter(i_azi,i_pol) % obj) + allocate(ScattDataHistogram :: this % scatter(iazi,ipol) % obj) else if (this % scatt_type == ANGLE_TABULAR) then - allocate(ScattDataTabular :: this % scatter(i_azi,i_pol) % obj) + allocate(ScattDataTabular :: this % scatter(iazi,ipol) % obj) else if (this % scatt_type == ANGLE_LEGENDRE) then - allocate(ScattDataLegendre :: this % scatter(i_azi,i_pol) % obj) + allocate(ScattDataLegendre :: this % scatter(iazi,ipol) % obj) end if ! Initialize the ScattData Object - call this % scatter(i_azi,i_pol) % obj % init(& - temp_mult(:,:,i_azi,i_pol), scatt_coeffs(:,:,:,i_azi,i_pol)) + call this % scatter(iazi,ipol) % obj % init(& + temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) end do end do ! Deallocate temporaries for the next material @@ -930,10 +932,10 @@ module nuclide_header this % total = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) deallocate(temp_arr) else - do i_pol = 1, this % n_pol - do i_azi = 1, this % n_azi - this % total(:,i_azi,i_pol) = this % absorption(:,i_azi,i_pol) + & - this % scatter(i_azi,i_pol) % obj % scattxs(:) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + this % total(:,iazi,ipol) = this % absorption(:,iazi,ipol) + & + this % scatter(iazi,ipol) % obj % scattxs(:) end do end do end if @@ -1143,7 +1145,7 @@ module nuclide_header integer :: unit_ ! unit to write to integer :: size_total, size_scattmat, size_mgxs - integer :: i_pol, i_azi, gin + integer :: ipol, iazi, gin ! set default unit for writing information if (present(unit)) then @@ -1159,15 +1161,15 @@ module nuclide_header ! Determine size of mgxs and scattering matrices size_scattmat = 0 - do i_pol = 1, this % n_pol - do i_azi = 1, this % n_azi - do gin = 1, size(this % scatter(i_azi,i_pol) % obj % energy) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, size(this % scatter(iazi,ipol) % obj % energy) size_scattmat = size_scattmat + & - 2 * size(this % scatter(i_azi,i_pol) % obj % energy(gin) % data) + & - size(this % scatter(i_azi,i_pol) % obj % dist(gin) % data) + 2 * size(this % scatter(iazi,ipol) % obj % energy(gin) % data) + & + size(this % scatter(iazi,ipol) % obj % dist(gin) % data) end do size_scattmat = size_scattmat + & - size(this % scatter(i_azi,i_pol) % obj % scattxs) + size(this % scatter(iazi,ipol) % obj % scattxs) end do end do size_scattmat = size_scattmat * 8 @@ -1198,7 +1200,7 @@ module nuclide_header ! NUCLIDE*_GET_XS Returns the requested data type !=============================================================================== - function nuclideiso_get_xs(this, g, xstype, gout, uvw, mu, i_azi, i_pol) & + function nuclideiso_get_xs(this, g, xstype, gout, uvw, mu, iazi, ipol) & result(xs) class(NuclideIso), intent(in) :: this integer, intent(in) :: g ! Incoming Energy group @@ -1206,8 +1208,8 @@ module nuclide_header integer, optional, intent(in) :: gout ! Outgoing Group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: i_azi ! Azimuthal Index - integer, optional, intent(in) :: i_pol ! Polar Index + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index real(8) :: xs ! Resultant xs xs = ZERO @@ -1249,7 +1251,7 @@ module nuclide_header end if end function nuclideiso_get_xs - function nuclideangle_get_xs(this, g, xstype, gout, uvw, mu, i_azi, i_pol) & + function nuclideangle_get_xs(this, g, xstype, gout, uvw, mu, iazi, ipol) & result(xs) class(NuclideAngle), intent(in) :: this integer, intent(in) :: g ! Incoming Energy group @@ -1257,11 +1259,11 @@ module nuclide_header integer, optional, intent(in) :: gout ! Outgoing Group real(8), optional, intent(in) :: mu ! Change in angle real(8), optional, intent(in) :: uvw(3) ! Requested Angle - integer, optional, intent(in) :: i_azi ! Azimuthal Index - integer, optional, intent(in) :: i_pol ! Polar Index + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index real(8) :: xs ! Resultant xs - integer :: i_azi_, i_pol_ + integer :: iazi_, ipol_ xs = ZERO @@ -1270,43 +1272,43 @@ module nuclide_header return end if - if (present(i_azi) .and. present(i_pol)) then - i_azi_ = i_azi - i_pol_ = i_pol + if (present(iazi) .and. present(ipol)) then + iazi_ = iazi + ipol_ = ipol else - call find_angle(this % polar, this % azimuthal, uvw, i_azi_, i_pol_) + call find_angle(this % polar, this % azimuthal, uvw, iazi_, ipol_) end if if (present(gout)) then select case(xstype) case('mult') - xs = this % scatter(i_azi_,i_pol_) % obj % mult(g) % data(gout) + xs = this % scatter(iazi_,ipol_) % obj % mult(g) % data(gout) case('nu_fission') - xs = this % nu_fission(gout,g,i_azi_,i_pol_) + xs = this % nu_fission(gout,g,iazi_,ipol_) case('chi') - xs = this % chi(gout,i_azi_,i_pol_) + xs = this % chi(gout,iazi_,ipol_) case('f_mu', 'f_mu/mult') - xs = this % scatter(i_azi_,i_pol_) % obj % calc_f(g,gout,mu) + xs = this % scatter(iazi_,ipol_) % obj % calc_f(g,gout,mu) if (xstype == 'f_mu/mult') then - xs = xs / this % scatter(i_azi_,i_pol_) % obj % mult(g) % data(gout) + xs = xs / this % scatter(iazi_,ipol_) % obj % mult(g) % data(gout) end if end select else select case(xstype) case('total') - xs = this % total(g,i_azi_,i_pol_) + xs = this % total(g,iazi_,ipol_) case('absorption') - xs = this % absorption(g,i_azi_,i_pol_) + xs = this % absorption(g,iazi_,ipol_) case('fission') - xs = this % fission(g,i_azi_,i_pol_) + xs = this % fission(g,iazi_,ipol_) case('k_fission') if (allocated(this % k_fission)) then - xs = this % k_fission(g,i_azi_,i_pol_) + xs = this % k_fission(g,iazi_,ipol_) end if case('chi') - xs = this % chi(g,i_azi_,i_pol_) + xs = this % chi(g,iazi_,ipol_) case('scatter') - xs = this % scatter(i_azi_,i_pol_) % obj % scattxs(g) + xs = this % scatter(iazi_,ipol_) % obj % scattxs(g) end select end if diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index cf965f397..dbbedc639 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -81,19 +81,22 @@ module scattdata_header procedure :: sample => scattdatalegendre_sample end type ScattDataLegendre - type, extends(ScattData) :: ScattDataHistogram - real(8), allocatable :: mu(:) ! Mu bins - real(8) :: dmu ! Mu spacing + type, extends(ScattData) :: ScattDataHistogram + real(8), allocatable :: mu(:) ! Mu bins + real(8) :: dmu ! Mu spacing + ! Histogram of f(mu) (dist has CDF) + type(Jagged2D), allocatable :: fmu(:) ! (Gin % data(Order/Nmu x Gout) contains procedure :: init => scattdatahistogram_init procedure :: calc_f => scattdatahistogram_calc_f procedure :: sample => scattdatahistogram_sample + procedure :: get_matrix => scattdatahistogram_get_matrix end type ScattDataHistogram - type, extends(ScattData) :: ScattDataTabular - real(8), allocatable :: mu(:) ! Mu bins - real(8) :: dmu ! Mu spacing - ! PDF of f(mu) + type, extends(ScattData) :: ScattDataTabular + real(8), allocatable :: mu(:) ! Mu bins + real(8) :: dmu ! Mu spacing + ! PDF of f(mu) (dist has CDF) type(Jagged2D), allocatable :: fmu(:) ! (Gin % data(Order/Nmu x Gout) contains procedure :: init => scattdatatabular_init @@ -276,15 +279,22 @@ contains this % mu(imu) = -ONE + real(imu - 1,8) * this % dmu end do - ! Best to integrate this histogram so we can avoid rejection sampling + ! Integrate this histogram so we can avoid rejection sampling while + ! also saving the original histogram in fmu + allocate(this % fmu(groups)) do gin = 1, groups + allocate(this % fmu(gin) % data(order, & + this % gmin(gin):this % gmax(gin))) do gout = this % gmin(gin), this % gmax(gin) + ! Store the histogram + this % fmu(gin) % data(:,gout) = coeffs(:,gout,gin) ! Integrate the histogram this % dist(gin) % data(1,gout) = this % dmu * coeffs(1,gout,gin) do imu = 2, order this % dist(gin) % data(imu,gout) = this % dmu * coeffs(imu,gout,gin) + & this % dist(gin) % data(imu - 1,gout) end do + ! Now make sure integral norms to zero norm = this % dist(gin) % data(order,gout) if (norm > ZERO) then @@ -423,14 +433,13 @@ contains integer :: imu ! Find mu bin - imu = floor((mu + ONE)/ this % dmu + ONE) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % dist, dim=1)) then - imu = imu - 1 + if (mu == ONE) then + imu = size(this % fmu(gin) % data,dim=1) + else + imu = floor((mu + ONE)/ this % dmu + ONE) end if - ! Use histogram interpolation to find f(mu) - f = this % dist(gin) % data(imu,gout) + f = this % fmu(gin) % data(imu,gout) end function scattdatahistogram_calc_f @@ -445,16 +454,16 @@ contains real(8) :: r ! Find mu bin - imu = floor((mu + ONE)/ this % dmu + ONE) - ! Adjust so interpolation works on the last bin if necessary - if (imu == size(this % dist, dim=1)) then - imu = imu - 1 + if (mu == ONE) then + imu = size(this % fmu(gin) % data,dim=1) - 1 + else + imu = floor((mu + ONE)/ this % dmu + ONE) end if ! Now interpolate to find f(mu) r = (mu - this % mu(imu)) / (this % mu(imu + 1) - this % mu(imu)) - f = (ONE - r) * this % dist(gin) % data(imu,gout) + & - r * this % dist(gin) % data(imu + 1,gout) + f = (ONE - r) * this % fmu(gin) % data(imu,gout) + & + r * this % fmu(gin) % data(imu + 1,gout) end function scattdatatabular_calc_f @@ -609,7 +618,7 @@ contains ! using ScattData's information of fmu/dist, energy, and scattxs !=============================================================================== - function scattdata_get_matrix(this, req_order) result(matrix) + pure function scattdata_get_matrix(this, req_order) result(matrix) class(ScattData), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: req_order ! Requested order of matrix real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built @@ -633,7 +642,31 @@ contains end do end function scattdata_get_matrix - function scattdatatabular_get_matrix(this, req_order) result(matrix) + pure function scattdatahistogram_get_matrix(this, req_order) result(matrix) + class(ScattDataHistogram), intent(in) :: this ! Scattering Object to work with + integer, intent(in) :: req_order ! Requested order of matrix + real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + + integer :: order, groups, gin, gout + + groups = size(this % energy) + order = min(req_order,size(this % dist(1) % data(:,1))) + + allocate(matrix(order,groups,groups)) + ! Initialize to 0; this way the zero entries in the dense matrix dont + ! need to be explicitly set, requiring a significant increase in the + ! lines of code. + matrix = ZERO + do gin = 1, groups + do gout = this % gmin(gin), this % gmax(gin) + matrix(:,gout,gin) = this % scattxs(gin) * & + this % energy(gin) % data(gout) * & + this % fmu(gin) % data(1:order,gout) + end do + end do + end function scattdatahistogram_get_matrix + + pure function scattdatatabular_get_matrix(this, req_order) result(matrix) class(ScattDataTabular), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: req_order ! Requested order of matrix real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built From 8088eda6fd4bcc19f37c291b7d087b1cc4dd20c2 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 9 Mar 2016 20:01:47 -0500 Subject: [PATCH 009/147] Removing need to have coeffs (inout) in the scattdata_init routines --- src/scattdata_header.F90 | 76 ++++++++++++++++++++++++---------------- 1 file changed, 45 insertions(+), 31 deletions(-) diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index dbbedc639..955e66783 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -49,7 +49,7 @@ module scattdata_header import ScattData class(ScattData), intent(inout) :: this ! Scattering Object to work with real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use end subroutine scattdata_init_ pure function scattdata_calc_f_(this, gin, gout, mu) result(f) @@ -169,31 +169,36 @@ contains subroutine scattdatalegendre_init(this, mult, coeffs) class(ScattDataLegendre), intent(inout) :: this ! Object to work on real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use real(8) :: dmu, mu, f, norm integer :: imu, Nmu, gout, gin, groups, order real(8), allocatable :: energy(:,:) + real(8), allocatable :: matrix(:,:,:) groups = size(coeffs,dim=3) order = size(coeffs,dim=1) - ! Get scattxs value first before anything happens to coeffs + ! make a copy of coeffs that we can use to extract data and normalize + allocate(matrix(order,groups,groups)) + matrix = coeffs + + ! Get scattxs value allocate(this % scattxs(groups)) - ! Get this by summing the now un-normalized P0 coefficient in coeffs + ! Get this by summing the un-normalized P0 coefficient in matrix ! over all outgoing groups - this % scattxs = sum(coeffs(1,:,:),dim=1) + this % scattxs = sum(matrix(1,:,:),dim=1) allocate(energy(groups,groups)) energy = ZERO - ! Build energy transfer probability matrix from data in coeffs - ! while also normalizing coeffs itself (making CDF of f(mu=1)=1) + ! Build energy transfer probability matrix from data in matrix + ! while also normalizing matrix itself (making CDF of f(mu=1)=1) do gin = 1, groups do gout = 1, groups - norm = coeffs(1,gout,gin) + norm = matrix(1,gout,gin) energy(gout,gin) = norm if (norm /= ZERO) then - coeffs(:,gout,gin) = coeffs(:,gout,gin) / norm + matrix(:,gout,gin) = matrix(:,gout,gin) / norm end if end do end do @@ -201,10 +206,10 @@ contains call scattdata_init(this, order, energy, mult) allocate(this % max_val(groups)) - ! Set dist values from coeffs and initialize max_val + ! Set dist values from matrix and initialize max_val do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) - this % dist(gin) % data(:,gout) = coeffs(:,gout,gin) + this % dist(gin) % data(:,gout) = matrix(:,gout,gin) end do allocate(this % max_val(gin) % data(this % gmin(gin):this % gmax(gin))) this % max_val(gin) % data = ZERO @@ -240,32 +245,37 @@ contains subroutine scattdatahistogram_init(this, mult, coeffs) class(ScattDataHistogram), intent(inout) :: this ! Object to work on - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use integer :: imu, gin, gout, groups, order real(8) :: norm real(8), allocatable :: energy(:,:) + real(8), allocatable :: matrix(:,:,:) groups = size(coeffs,dim=3) order = size(coeffs,dim=1) - ! Get scattxs value first before anything happens to coeffs + ! make a copy of coeffs that we can use to extract data and normalize + allocate(matrix(order,groups,groups)) + matrix = coeffs + + ! Get scattxs value allocate(this % scattxs(groups)) - ! Get this by summing the now un-normalized P0 coefficient in coeffs + ! Get this by summing the un-normalized P0 coefficient in matrix ! over all outgoing groups - this % scattxs = sum(sum(coeffs(:,:,:),dim=1),dim=1) + this % scattxs = sum(sum(matrix(:,:,:),dim=1),dim=1) allocate(energy(groups,groups)) energy = ZERO - ! Build energy transfer probability matrix from data in coeffs - ! while also normalizing coeffs itself (making CDF of f(mu=1)=1) + ! Build energy transfer probability matrix from data in matrix + ! while also normalizing matrix itself (making CDF of f(mu=1)=1) do gin = 1, groups do gout = 1, groups - norm = sum(coeffs(:,gout,gin)) + norm = sum(matrix(:,gout,gin)) energy(gout,gin) = norm if (norm /= ZERO) then - coeffs(:,gout,gin) = coeffs(:,gout,gin) / norm + matrix(:,gout,gin) = matrix(:,gout,gin) / norm end if end do end do @@ -287,11 +297,11 @@ contains this % gmin(gin):this % gmax(gin))) do gout = this % gmin(gin), this % gmax(gin) ! Store the histogram - this % fmu(gin) % data(:,gout) = coeffs(:,gout,gin) + this % fmu(gin) % data(:,gout) = matrix(:,gout,gin) ! Integrate the histogram - this % dist(gin) % data(1,gout) = this % dmu * coeffs(1,gout,gin) + this % dist(gin) % data(1,gout) = this % dmu * matrix(1,gout,gin) do imu = 2, order - this % dist(gin) % data(imu,gout) = this % dmu * coeffs(imu,gout,gin) + & + this % dist(gin) % data(imu,gout) = this % dmu * matrix(imu,gout,gin) + & this % dist(gin) % data(imu - 1,gout) end do @@ -309,15 +319,20 @@ contains subroutine scattdatatabular_init(this, mult, coeffs) class(ScattDataTabular), intent(inout) :: this ! Object to work on real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(inout) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use integer :: imu, gin, gout, groups, order real(8) :: norm real(8), allocatable :: energy(:,:) + real(8), allocatable :: matrix(:,:,:) groups = size(coeffs,dim=3) order = size(coeffs,dim=1) + ! make a copy of coeffs that we can use to extract data and normalize + allocate(matrix(order,groups,groups)) + matrix = coeffs + ! Build the angular distribution mu values allocate(this % mu(order)) this % dmu = TWO / real(order - 1,8) @@ -327,7 +342,7 @@ contains end do this % mu(order) = ONE - ! Get scattxs before anything happens to coeffs + ! Get scattxs allocate(this % scattxs(groups)) ! Get this by integrating the scattering distribution over all mu points ! and then combining over all outgoing groups @@ -336,8 +351,8 @@ contains norm = ZERO do gout = 1, groups do imu = 2, order - norm = norm + HALF * this % dmu * (coeffs(imu - 1,gout,gin) + & - coeffs(imu,gout,gin)) + norm = norm + HALF * this % dmu * (matrix(imu - 1,gout,gin) + & + matrix(imu,gout,gin)) end do end do this % scattxs(gin) = norm @@ -345,15 +360,14 @@ contains allocate(energy(groups,groups)) energy = ZERO - ! Build energy transfer probability matrix from data in coeffs + ! Build energy transfer probability matrix from data in matrix do gin = 1, groups do gout = 1, groups norm = ZERO do imu = 2, order norm = norm + HALF * this % dmu * & - (coeffs(imu - 1,gout,gin) + coeffs(imu,gout,gin)) + (matrix(imu - 1,gout,gin) + matrix(imu,gout,gin)) end do - ! energy(gout,gin) = sum(coeffs(:,gout,gin)) energy(gout,gin) = norm end do end do @@ -367,7 +381,7 @@ contains do gout = this % gmin(gin), this % gmax(gin) ! Coeffs contain f(mu), put in f(mu) as that is where the ! PDF lives - this % fmu(gin) % data(:,gout) = coeffs(:,gout,gin) + this % fmu(gin) % data(:,gout) = matrix(:,gout,gin) ! Force positivity do imu = 1, order From a53b3fc781f78334e75e6872088895daf8f33df8 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 9 Mar 2016 21:01:26 -0500 Subject: [PATCH 010/147] Updated test results, made fission sampling in MG mode a smidge faster --- src/macroxs_header.F90 | 8 +- src/scattdata_header.F90 | 2 + tests/test_mg_basic/results_true.dat | 2 +- tests/test_mg_max_order/inputs_true.dat | 2 +- tests/test_mg_max_order/results_true.dat | 2 +- tests/test_mg_max_order/test_mg_max_order.py | 3 +- tests/test_mg_nuclide/results_true.dat | 2 +- tests/test_mg_tallies/results_true.dat | 1306 +++++++++--------- 8 files changed, 665 insertions(+), 662 deletions(-) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index f86da1729..2fd7dfe28 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -628,8 +628,8 @@ contains real(8) :: prob ! Running probability xi = prn() - prob = ZERO - gout = 0 + gout = 1 + prob = this % chi(gout,gin) do while (prob < xi) gout = gout + 1 @@ -650,8 +650,8 @@ contains call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) xi = prn() - prob = ZERO - gout = 0 + gout = 1 + prob = this % chi(gout,gin,iazi,ipol) do while (prob < xi) gout = gout + 1 diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 955e66783..04d48d22f 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -308,6 +308,8 @@ contains ! Now make sure integral norms to zero norm = this % dist(gin) % data(order,gout) if (norm > ZERO) then + this % fmu(gin) % data(:,gout) = & + this % fmu(gin) % data(:,gout) / norm this % dist(gin) % data(:,gout) = & this % dist(gin) % data(:,gout) / norm end if diff --git a/tests/test_mg_basic/results_true.dat b/tests/test_mg_basic/results_true.dat index 35f3e73d4..55c2af813 100644 --- a/tests/test_mg_basic/results_true.dat +++ b/tests/test_mg_basic/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.045320E+00 5.851680E-02 +1.033731E+00 4.974463E-02 diff --git a/tests/test_mg_max_order/inputs_true.dat b/tests/test_mg_max_order/inputs_true.dat index 1ad336e19..937ceb462 100644 --- a/tests/test_mg_max_order/inputs_true.dat +++ b/tests/test_mg_max_order/inputs_true.dat @@ -1 +1 @@ -abe20c626d613e73ccb1a3f8468ad1b9aecca528afa9e8131a411d754eb86b8ab64a6fb1fdc9c0b8b8158ff7c82f548de5912041bf035aa5a2d4532cfe0c9510 \ No newline at end of file +322483933c38fe6ecfa41d632c7214b5cd35af4a56415872585914d9c775dc99171e918eebf3221ab6292689c37269b8c3ce5ff85b3633b5c05ee481bf1b212a \ No newline at end of file diff --git a/tests/test_mg_max_order/results_true.dat b/tests/test_mg_max_order/results_true.dat index 1b2300560..f75c1300a 100644 --- a/tests/test_mg_max_order/results_true.dat +++ b/tests/test_mg_max_order/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.083030E+00 1.855038E-02 +1.055274E+00 1.715904E-02 diff --git a/tests/test_mg_max_order/test_mg_max_order.py b/tests/test_mg_max_order/test_mg_max_order.py index 2f5ee4e4e..d64956fbf 100644 --- a/tests/test_mg_max_order/test_mg_max_order.py +++ b/tests/test_mg_max_order/test_mg_max_order.py @@ -76,9 +76,10 @@ class MGMaxOrderTestHarness(PyAPITestHarness): self._input_set = MGNuclideInputSet() def _build_inputs(self): - super(MGMaxOrderTestHarness, self)._build_inputs() # Set P1 scattering self._input_set.settings.max_order = 1 + # Call standard input build + super(MGMaxOrderTestHarness, self)._build_inputs() if __name__ == '__main__': harness = MGMaxOrderTestHarness('statepoint.10.*', False, mg=True) diff --git a/tests/test_mg_nuclide/results_true.dat b/tests/test_mg_nuclide/results_true.dat index 5b60cef22..5e05e2451 100644 --- a/tests/test_mg_nuclide/results_true.dat +++ b/tests/test_mg_nuclide/results_true.dat @@ -1,2 +1,2 @@ k-combined: -1.380785E-01 5.556526E-03 +1.317412E-01 5.926047E-03 diff --git a/tests/test_mg_tallies/results_true.dat b/tests/test_mg_tallies/results_true.dat index 0cb47a712..5f4964a4e 100644 --- a/tests/test_mg_tallies/results_true.dat +++ b/tests/test_mg_tallies/results_true.dat @@ -1,86 +1,86 @@ k-combined: -1.045320E+00 5.851680E-02 +1.033731E+00 4.974463E-02 tally 1: -2.286064E+00 -1.057353E+00 -6.503987E-02 -8.851627E-04 -3.376363E+00 -2.323627E+00 -2.733240E-02 -1.607534E-04 -6.776283E-02 -9.880704E-04 -2.391658E+00 -1.201477E+00 -7.241106E-02 -1.103780E-03 -3.614949E+00 -2.730438E+00 -3.146867E-02 -2.110753E-04 -7.801752E-02 -1.297373E-03 -2.762725E+00 -1.705088E+00 -8.684520E-02 -1.654173E-03 -4.172232E+00 -3.847245E+00 -3.834947E-02 -3.212662E-04 -9.507651E-02 -1.974662E-03 -2.802290E+00 -1.773339E+00 -8.347451E-02 -1.574952E-03 -4.206829E+00 -3.971225E+00 -3.593646E-02 -2.967708E-04 -8.909414E-02 -1.824101E-03 -2.383708E+00 -1.176784E+00 -7.337273E-02 -1.097240E-03 -3.624903E+00 -2.690697E+00 -3.213890E-02 -2.139948E-04 -7.967917E-02 -1.315319E-03 -2.398216E+00 -1.234567E+00 -6.905889E-02 -9.879327E-04 -3.479138E+00 -2.538252E+00 -2.911091E-02 -1.750648E-04 -7.217215E-02 -1.076035E-03 -2.563998E+00 -1.354089E+00 -7.357381E-02 -1.097086E-03 -3.753156E+00 -2.867475E+00 -3.097034E-02 -1.948794E-04 -7.678206E-02 -1.197826E-03 -2.293243E+00 -1.172767E+00 -6.702582E-02 -9.267762E-04 -3.407144E+00 -2.469472E+00 -2.857514E-02 -1.688581E-04 -7.084385E-02 -1.037886E-03 +3.163666E+00 +2.165097E+00 +9.964133E-02 +2.052446E-03 +4.861844E+00 +4.978206E+00 +4.417216E-02 +4.040216E-04 +1.095122E-01 +2.483317E-03 +3.324437E+00 +2.299850E+00 +9.574329E-02 +1.968438E-03 +4.881821E+00 +4.943976E+00 +4.041706E-02 +3.650255E-04 +1.002025E-01 +2.243628E-03 +3.199995E+00 +2.091126E+00 +8.859707E-02 +1.592091E-03 +4.671522E+00 +4.439001E+00 +3.660515E-02 +2.728602E-04 +9.075197E-02 +1.677135E-03 +2.910284E+00 +1.723356E+00 +9.207508E-02 +1.744614E-03 +4.421737E+00 +3.979362E+00 +4.080063E-02 +3.481887E-04 +1.011535E-01 +2.140141E-03 +2.506574E+00 +1.326705E+00 +8.637880E-02 +1.598941E-03 +3.920683E+00 +3.263607E+00 +3.978214E-02 +3.424111E-04 +9.862841E-02 +2.104629E-03 +2.951103E+00 +1.826551E+00 +8.748324E-02 +1.648479E-03 +4.309848E+00 +3.903067E+00 +3.741466E-02 +3.141687E-04 +9.275891E-02 +1.931037E-03 +3.048521E+00 +2.007251E+00 +9.483162E-02 +1.935789E-03 +4.599534E+00 +4.527383E+00 +4.168244E-02 +3.813062E-04 +1.033396E-01 +2.343697E-03 +2.982958E+00 +1.966657E+00 +9.896454E-02 +2.016812E-03 +4.645921E+00 +4.599347E+00 +4.489740E-02 +4.108900E-04 +1.113102E-01 +2.525534E-03 0.000000E+00 0.000000E+00 0.000000E+00 @@ -171,86 +171,86 @@ tally 1: 0.000000E+00 0.000000E+00 0.000000E+00 -2.604127E+00 -1.442914E+00 -7.142299E-02 -1.083324E-03 -3.786547E+00 -2.990260E+00 -2.935394E-02 -1.905369E-04 -7.277467E-02 -1.171135E-03 -2.457755E+00 -1.228862E+00 -6.655630E-02 -9.411086E-04 -3.528688E+00 -2.561047E+00 -2.709124E-02 -1.640319E-04 -6.716494E-02 -1.008221E-03 -2.450846E+00 -1.295337E+00 -6.779278E-02 -9.992248E-04 -3.519409E+00 -2.693620E+00 -2.793186E-02 -1.714064E-04 -6.924902E-02 -1.053549E-03 -2.469234E+00 -1.300419E+00 -7.347034E-02 -1.175743E-03 -3.675903E+00 -2.880386E+00 -3.155996E-02 -2.200036E-04 -7.824386E-02 -1.352252E-03 -2.576106E+00 -1.365945E+00 -7.241428E-02 -1.090052E-03 -3.719498E+00 -2.861357E+00 -3.008961E-02 -1.906170E-04 -7.459854E-02 -1.171627E-03 -2.503651E+00 -1.290812E+00 -7.432507E-02 -1.132918E-03 -3.702398E+00 -2.813425E+00 -3.186491E-02 -2.091477E-04 -7.899991E-02 -1.285525E-03 -2.395349E+00 -1.202098E+00 -7.095925E-02 -1.051988E-03 -3.559388E+00 -2.628753E+00 -3.041477E-02 -1.959992E-04 -7.540470E-02 -1.204709E-03 -1.910174E+00 -7.331782E-01 -6.366813E-02 -8.166135E-04 -2.966770E+00 -1.762376E+00 -2.893278E-02 -1.712979E-04 -7.173053E-02 -1.052882E-03 +2.806322E+00 +1.650116E+00 +8.677689E-02 +1.577748E-03 +4.271173E+00 +3.787053E+00 +3.812147E-02 +3.107861E-04 +9.451124E-02 +1.910246E-03 +2.767101E+00 +1.574082E+00 +8.523508E-02 +1.523190E-03 +4.143067E+00 +3.546386E+00 +3.725690E-02 +2.974028E-04 +9.236779E-02 +1.827986E-03 +2.767691E+00 +1.557585E+00 +7.816996E-02 +1.254835E-03 +4.015666E+00 +3.289915E+00 +3.260527E-02 +2.211412E-04 +8.083542E-02 +1.359243E-03 +2.734236E+00 +1.510579E+00 +8.505695E-02 +1.474976E-03 +4.114798E+00 +3.424404E+00 +3.737976E-02 +2.870194E-04 +9.267239E-02 +1.764164E-03 +2.421441E+00 +1.195490E+00 +8.292263E-02 +1.384777E-03 +3.817448E+00 +2.942804E+00 +3.814207E-02 +2.931372E-04 +9.456230E-02 +1.801767E-03 +2.724650E+00 +1.519118E+00 +9.238437E-02 +1.725646E-03 +4.305602E+00 +3.753830E+00 +4.235399E-02 +3.657508E-04 +1.050046E-01 +2.248086E-03 +2.703678E+00 +1.593893E+00 +8.744732E-02 +1.597761E-03 +4.110489E+00 +3.592877E+00 +3.913038E-02 +3.184391E-04 +9.701255E-02 +1.957285E-03 +2.707705E+00 +1.792230E+00 +8.754036E-02 +1.760104E-03 +4.203619E+00 +4.162497E+00 +3.927598E-02 +3.456207E-04 +9.737351E-02 +2.124357E-03 0.000000E+00 0.000000E+00 0.000000E+00 @@ -341,86 +341,86 @@ tally 1: 0.000000E+00 0.000000E+00 0.000000E+00 -2.593479E+00 -1.421618E+00 -7.731733E-02 -1.249860E-03 -3.880469E+00 -3.167768E+00 -3.330331E-02 -2.319171E-04 -8.256599E-02 -1.425478E-03 -2.563470E+00 -1.449702E+00 -7.411043E-02 -1.158986E-03 -3.692974E+00 -2.935486E+00 -3.125554E-02 -2.061246E-04 -7.748913E-02 -1.266944E-03 -2.657580E+00 -1.493736E+00 -7.749682E-02 -1.277831E-03 -3.892576E+00 -3.190262E+00 -3.289903E-02 -2.334764E-04 -8.156370E-02 -1.435062E-03 -2.701357E+00 -1.517431E+00 -8.804410E-02 -1.639744E-03 -4.161224E+00 -3.606273E+00 -3.959674E-02 -3.345554E-04 -9.816875E-02 -2.056343E-03 -2.745200E+00 -1.523378E+00 -7.925308E-02 -1.270874E-03 -3.962649E+00 -3.165021E+00 -3.340000E-02 -2.283904E-04 -8.280570E-02 -1.403801E-03 -2.678775E+00 -1.492394E+00 -8.646776E-02 -1.554919E-03 -4.147456E+00 -3.551060E+00 -3.875994E-02 -3.125295E-04 -9.609415E-02 -1.920962E-03 -2.678888E+00 -1.497390E+00 -7.616647E-02 -1.203778E-03 -3.868905E+00 -3.108718E+00 -3.186093E-02 -2.136540E-04 -7.899003E-02 -1.313223E-03 -2.189117E+00 -9.756340E-01 -6.824988E-02 -9.549688E-04 -3.259136E+00 -2.150849E+00 -2.997262E-02 -1.883650E-04 -7.430850E-02 -1.157785E-03 +2.333969E+00 +1.124588E+00 +6.982134E-02 +1.014762E-03 +3.448351E+00 +2.435965E+00 +3.004987E-02 +1.926319E-04 +7.450003E-02 +1.184011E-03 +3.086286E+00 +1.981929E+00 +1.016918E-01 +2.146313E-03 +4.741530E+00 +4.626144E+00 +4.593581E-02 +4.489950E-04 +1.138847E-01 +2.759746E-03 +2.871515E+00 +1.672027E+00 +8.533571E-02 +1.469319E-03 +4.221958E+00 +3.599412E+00 +3.658547E-02 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-1.676655E-03 -4.716109E+00 -4.596488E+00 -3.654407E-02 -2.855910E-04 -9.060053E-02 -1.755384E-03 -3.091331E+00 -2.117646E+00 -8.528196E-02 -1.564336E-03 -4.492326E+00 -4.405850E+00 -3.513814E-02 -2.665883E-04 -8.711494E-02 -1.638584E-03 -2.649730E+00 -1.444519E+00 -8.510948E-02 -1.506094E-03 -4.117595E+00 -3.501517E+00 -3.810553E-02 -3.052819E-04 -9.447172E-02 -1.876414E-03 -2.875773E+00 -1.758531E+00 -9.127582E-02 -1.780419E-03 -4.328266E+00 -3.989840E+00 -4.045386E-02 -3.513542E-04 -1.002937E-01 -2.159598E-03 -3.102792E+00 -1.949906E+00 -9.153879E-02 -1.691646E-03 -4.578530E+00 -4.235906E+00 -3.913672E-02 -3.094156E-04 -9.702826E-02 -1.901822E-03 -3.238743E+00 -2.146355E+00 -8.902551E-02 -1.593536E-03 -4.683916E+00 -4.438028E+00 -3.660342E-02 -2.683183E-04 -9.074766E-02 -1.649218E-03 -3.006635E+00 -1.887385E+00 -8.716712E-02 -1.586834E-03 -4.383965E+00 -4.008888E+00 -3.688262E-02 -2.862513E-04 -9.143987E-02 -1.759443E-03 -2.749904E+00 -1.550561E+00 -9.244273E-02 -1.748082E-03 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+2.313941E+00 +3.125803E-02 +2.124583E-04 +7.749531E-02 +1.305874E-03 +2.250156E+00 +1.052173E+00 +6.400255E-02 +8.818690E-04 +3.268015E+00 +2.245559E+00 +2.679559E-02 +1.634377E-04 +6.643197E-02 +1.004569E-03 0.000000E+00 0.000000E+00 0.000000E+00 @@ -1191,86 +1191,86 @@ tally 1: 0.000000E+00 0.000000E+00 0.000000E+00 -2.556952E+00 -1.416458E+00 -8.087467E-02 -1.431667E-03 -3.806748E+00 -3.158182E+00 -3.571995E-02 -2.831832E-04 -8.855737E-02 -1.740585E-03 -2.546384E+00 -1.446967E+00 -8.000281E-02 -1.363415E-03 -3.844739E+00 -3.222133E+00 -3.533522E-02 -2.621956E-04 -8.760354E-02 -1.611584E-03 -2.474418E+00 -1.302438E+00 -7.728372E-02 -1.265047E-03 -3.818517E+00 -3.076074E+00 -3.414744E-02 -2.483215E-04 -8.465877E-02 -1.526307E-03 -2.478272E+00 -1.299434E+00 -7.866430E-02 -1.293627E-03 -3.758685E+00 -2.973817E+00 -3.491240E-02 -2.542033E-04 -8.655529E-02 -1.562460E-03 -2.941937E+00 -1.842278E+00 -9.491310E-02 -1.902183E-03 -4.564730E+00 -4.427111E+00 -4.252722E-02 -3.828960E-04 -1.054340E-01 -2.353469E-03 -2.850564E+00 -1.719152E+00 -8.118192E-02 -1.404765E-03 -4.190858E+00 -3.722715E+00 -3.411695E-02 -2.522778E-04 -8.458318E-02 -1.550625E-03 -2.726097E+00 -1.648250E+00 -7.879124E-02 -1.424955E-03 -3.940978E+00 -3.461222E+00 -3.322044E-02 -2.688615E-04 -8.236053E-02 -1.652557E-03 -2.304822E+00 -1.153775E+00 -7.500010E-02 -1.314077E-03 -3.542935E+00 -2.786864E+00 -3.369367E-02 -2.798215E-04 -8.353377E-02 -1.719922E-03 +2.149693E+00 +9.566763E-01 +6.325375E-02 +8.781459E-04 +3.163781E+00 +2.089993E+00 +2.699802E-02 +1.754950E-04 +6.693384E-02 +1.078679E-03 +2.368262E+00 +1.206255E+00 +6.517665E-02 +9.363557E-04 +3.403305E+00 +2.501730E+00 +2.677251E-02 +1.620249E-04 +6.637476E-02 +9.958857E-04 +2.280249E+00 +1.070455E+00 +7.456831E-02 +1.147671E-03 +3.475673E+00 +2.476848E+00 +3.352210E-02 +2.345869E-04 +8.310842E-02 +1.441888E-03 +2.226928E+00 +1.011037E+00 +7.770236E-02 +1.243393E-03 +3.524398E+00 +2.538453E+00 +3.601410E-02 +2.702997E-04 +8.928663E-02 +1.661396E-03 +2.407411E+00 +1.170093E+00 +7.171133E-02 +1.029235E-03 +3.502484E+00 +2.461827E+00 +3.070568E-02 +1.889715E-04 +7.612591E-02 +1.161513E-03 +2.331359E+00 +1.134448E+00 +6.734317E-02 +9.407363E-04 +3.333577E+00 +2.267345E+00 +2.832929E-02 +1.772720E-04 +7.023433E-02 +1.089602E-03 +2.008838E+00 +8.722179E-01 +5.586199E-02 +7.051708E-04 +2.903675E+00 +1.807255E+00 +2.309145E-02 +1.322637E-04 +5.724863E-02 +8.129585E-04 +2.226061E+00 +1.048269E+00 +6.536859E-02 +9.623671E-04 +3.297988E+00 +2.324450E+00 +2.791406E-02 +1.866630E-04 +6.920490E-02 +1.147324E-03 0.000000E+00 0.000000E+00 0.000000E+00 @@ -2892,15 +2892,15 @@ tally 1: 0.000000E+00 0.000000E+00 tally 2: -4.283244E+01 -3.698890E+02 -4.285612E+01 -3.702981E+02 -6.926001E+00 -9.669342E+00 -6.926497E+00 -9.670727E+00 -1.223563E+02 -3.025594E+03 -1.223563E+02 -3.025594E+03 +4.075585E+01 +3.339527E+02 +4.077838E+01 +3.343221E+02 +6.274554E+00 +7.936999E+00 +6.275007E+00 +7.938146E+00 +1.122968E+02 +2.557771E+03 +1.122968E+02 +2.557771E+03 From a1764196ce703a305a7068e21a264d07cb17d3cd Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 9 Mar 2016 21:03:53 -0500 Subject: [PATCH 011/147] small editorial comment --- src/input_xml.F90 | 6 +++++- 1 file changed, 5 insertions(+), 1 deletion(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index b89b8807f..a7366d2cd 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -169,7 +169,11 @@ contains if (check_for_node(doc, "max_order")) then call get_node_value(doc, "max_order", max_order) else - ! Set to default of largest int, which means to use whatever is contained in library + ! Set to default of largest int - 1, which means to use whatever is + ! contained in library. + ! This is largest int - 1 because for legendre scattering, a value of + ! 1 is added to the order; adding 1 to huge(0) gets you the largest + ! negative integer, which is not what we want. max_order = huge(0) - 1 end if else From 28c0cebe386a6aacc94ff8dc8ef1227254c6542e Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 10 Mar 2016 19:20:14 -0500 Subject: [PATCH 012/147] Added checks for gout value to see if it is included in the new sparse format when querying the scattering distro info. --- src/macroxs_header.F90 | 54 +++++++++++--------- src/nuclide_header.F90 | 94 +++++++++++++++++++---------------- src/output.F90 | 6 ++- src/scattdata_header.F90 | 44 +++++++++++------ src/tally.F90 | 103 +++++++++++++++++++++++---------------- 5 files changed, 177 insertions(+), 124 deletions(-) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index 2fd7dfe28..6d74b081a 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -42,11 +42,11 @@ module macroxs_header integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? end subroutine macroxs_init_ - function macroxs_get_xs_(this, g, xstype, gout, uvw) result(xs) + function macroxs_get_xs_(this, xstype, gin, gout, uvw) result(xs) import MacroXS class(MacroXS), intent(in) :: this ! The MacroXS to initialize - integer, intent(in) :: g ! Incoming Energy group character(*) , intent(in) :: xstype ! Cross Section Type + integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8) :: xs ! Resultant xs @@ -547,41 +547,46 @@ contains ! MACROXS_*_GET_XS returns the requested data type !=============================================================================== - function macroxsiso_get_xs(this, g, xstype, gout, uvw) result(xs) + function macroxsiso_get_xs(this, xstype, gin, gout, uvw) result(xs) class(MacroXSIso), intent(in) :: this ! The MacroXS to initialize - integer, intent(in) :: g ! Incoming Energy group character(*) , intent(in) :: xstype ! Type of xs requested + integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8) :: xs ! Requested x/s select case(xstype) case('total') - xs = this % total(g) + xs = this % total(gin) case('absorption') - xs = this % absorption(g) + xs = this % absorption(gin) case('fission') - xs = this % fission(g) + xs = this % fission(gin) case('k_fission') - xs = this % k_fission(g) + xs = this % k_fission(gin) case('nu_fission') - xs = this % nu_fission(g) + xs = this % nu_fission(gin) case('scatter') - xs = this % scatter % scattxs(g) + xs = this % scatter % scattxs(gin) case('mult') if (present(gout)) then - xs = this % scatter % mult(g) % data(gout) + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % mult(gin) % data(gout) + end if else - xs = sum(this % scatter % mult(g) % data(:)) + xs = sum(this % scatter % mult(gin) % data(:)) end if end select end function macroxsiso_get_xs - function macroxsangle_get_xs(this, g, xstype, gout,uvw) result(xs) + function macroxsangle_get_xs(this, xstype, gin, gout, uvw) result(xs) class(MacroXSAngle), intent(in) :: this ! The MacroXS to initialize - integer, intent(in) :: g ! Incoming Energy group character(*) , intent(in) :: xstype ! Type of xs requested + integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8) :: xs ! Requested x/s @@ -592,22 +597,27 @@ contains call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) select case(xstype) case('total') - xs = this % total(g,iazi,ipol) + xs = this % total(gin,iazi,ipol) case('absorption') - xs = this % absorption(g,iazi,ipol) + xs = this % absorption(gin,iazi,ipol) case('fission') - xs = this % fission(g,iazi,ipol) + xs = this % fission(gin,iazi,ipol) case('k_fission') - xs = this % k_fission(g,iazi,ipol) + xs = this % k_fission(gin,iazi,ipol) case('nu_fission') - xs = this % nu_fission(g,iazi,ipol) + xs = this % nu_fission(gin,iazi,ipol) case('scatter') - xs = this % scatter(iazi,ipol) % obj % scattxs(g) + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) case('mult') if (present(gout)) then - xs = this % scatter(iazi,ipol) % obj % mult(g) % data(gout) + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if else - xs = sum(this % scatter(iazi,ipol) % obj % mult(g) % data(:)) + xs = sum(this % scatter(iazi,ipol) % obj % mult(gin) % data(:)) end if end select end if diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index e4dc717a8..35048454e 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -126,12 +126,12 @@ module nuclide_header integer, intent(in) :: max_order ! Maximum requested order end subroutine nuclidemg_init_ - function nuclidemg_get_xs_(this, g, xstype, gout, uvw, mu, iazi, ipol) & + function nuclidemg_get_xs_(this, xstype, gin, gout, uvw, mu, iazi, ipol) & result(xs) import NuclideMG class(NuclideMG), intent(in) :: this - integer, intent(in) :: g ! Incoming Energy group character(*), intent(in) :: xstype ! Cross Section Type + integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8), optional, intent(in) :: mu ! Change in angle @@ -1200,17 +1200,17 @@ module nuclide_header ! NUCLIDE*_GET_XS Returns the requested data type !=============================================================================== - function nuclideiso_get_xs(this, g, xstype, gout, uvw, mu, iazi, ipol) & + function nuclideiso_get_xs(this, xstype, gin, gout, uvw, mu, iazi, ipol) & result(xs) class(NuclideIso), intent(in) :: this - integer, intent(in) :: g ! Incoming Energy group - character(*), intent(in) :: xstype ! Cross Section Type - integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index - real(8) :: xs ! Resultant xs + character(*), intent(in) :: xstype ! Cross Section Type + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Group + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index + real(8) :: xs ! Resultant xs xs = ZERO @@ -1222,46 +1222,51 @@ module nuclide_header if (present(gout)) then select case(xstype) case('mult') - xs = this % scatter % mult(g) % data(gout) + xs = this % scatter % mult(gin) % data(gout) case('nu_fission') - xs = this % nu_fission(gout,g) + xs = this % nu_fission(gout,gin) case('f_mu', 'f_mu/mult') - xs = this % scatter % calc_f(g, gout, mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter % mult(g) % data(gout) + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % calc_f(gin, gout, mu) + if (xstype == 'f_mu/mult') then + xs = xs / this % scatter % mult(gin) % data(gout) + end if end if end select else select case(xstype) case('total') - xs = this % total(g) + xs = this % total(gin) case('absorption') - xs = this % absorption(g) + xs = this % absorption(gin) case('fission') - xs = this % fission(g) + xs = this % fission(gin) case('k_fission') if (allocated(this % k_fission)) then - xs = this % k_fission(g) + xs = this % k_fission(gin) end if case('chi') - xs = this % chi(g) + xs = this % chi(gin) case('scatter') - xs = this % scatter % scattxs(g) + xs = this % scatter % scattxs(gin) end select end if end function nuclideiso_get_xs - function nuclideangle_get_xs(this, g, xstype, gout, uvw, mu, iazi, ipol) & + function nuclideangle_get_xs(this, xstype, gin, gout, uvw, mu, iazi, ipol) & result(xs) class(NuclideAngle), intent(in) :: this - integer, intent(in) :: g ! Incoming Energy group - character(*), intent(in) :: xstype ! Cross Section Type - integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: mu ! Change in angle - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index - real(8) :: xs ! Resultant xs + character(*), intent(in) :: xstype ! Cross Section Type + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Group + real(8), optional, intent(in) :: mu ! Change in angle + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index + real(8) :: xs ! Resultant xs integer :: iazi_, ipol_ @@ -1282,33 +1287,38 @@ module nuclide_header if (present(gout)) then select case(xstype) case('mult') - xs = this % scatter(iazi_,ipol_) % obj % mult(g) % data(gout) + xs = this % scatter(iazi_,ipol_) % obj % mult(gin) % data(gout) case('nu_fission') - xs = this % nu_fission(gout,g,iazi_,ipol_) + xs = this % nu_fission(gout,gin,iazi_,ipol_) case('chi') xs = this % chi(gout,iazi_,ipol_) case('f_mu', 'f_mu/mult') - xs = this % scatter(iazi_,ipol_) % obj % calc_f(g,gout,mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter(iazi_,ipol_) % obj % mult(g) % data(gout) + if (gout < this % scatter(iazi_,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi_,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi_,ipol_) % obj % calc_f(gin,gout,mu) + if (xstype == 'f_mu/mult') then + xs = xs / this % scatter(iazi_,ipol_) % obj % mult(gin) % data(gout) + end if end if end select else select case(xstype) case('total') - xs = this % total(g,iazi_,ipol_) + xs = this % total(gin,iazi_,ipol_) case('absorption') - xs = this % absorption(g,iazi_,ipol_) + xs = this % absorption(gin,iazi_,ipol_) case('fission') - xs = this % fission(g,iazi_,ipol_) + xs = this % fission(gin,iazi_,ipol_) case('k_fission') if (allocated(this % k_fission)) then - xs = this % k_fission(g,iazi_,ipol_) + xs = this % k_fission(gin,iazi_,ipol_) end if case('chi') - xs = this % chi(g,iazi_,ipol_) + xs = this % chi(gin,iazi_,ipol_) case('scatter') - xs = this % scatter(iazi_,ipol_) % obj % scattxs(g) + xs = this % scatter(iazi_,ipol_) % obj % scattxs(gin) end select end if diff --git a/src/output.F90 b/src/output.F90 index 125fe010b..768f19775 100644 --- a/src/output.F90 +++ b/src/output.F90 @@ -904,7 +904,11 @@ contains write(UNIT=unit_tally, FMT='(1X,2A,1X,A)') repeat(" ", indent), & "Total Material" else - i_listing = nuclides(i_nuclide) % listing + if (run_CE) then + i_listing = nuclides(i_nuclide) % listing + else + i_listing = nuclides_MG(i_nuclide) % obj % listing + end if write(UNIT=unit_tally, FMT='(1X,2A,1X,A)') repeat(" ", indent), & trim(xs_listings(i_listing) % alias) end if diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index 04d48d22f..f36fe6043 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -435,7 +435,11 @@ contains real(8) :: f ! Return value of f(mu) ! Plug mu in to the legendre expansion and go from there - f = evaluate_legendre(this % dist(gin) % data(:,gout),mu) + if (gout < this % gmin(gin) .or. gout > this % gmax(gin)) then + f = ZERO + else + f = evaluate_legendre(this % dist(gin) % data(:,gout),mu) + end if end function scattdatalegendre_calc_f @@ -448,14 +452,18 @@ contains integer :: imu - ! Find mu bin - if (mu == ONE) then - imu = size(this % fmu(gin) % data,dim=1) + if (gout < this % gmin(gin) .or. gout > this % gmax(gin)) then + f = ZERO else - imu = floor((mu + ONE)/ this % dmu + ONE) - end if + ! Find mu bin + if (mu == ONE) then + imu = size(this % fmu(gin) % data,dim=1) + else + imu = floor((mu + ONE)/ this % dmu + ONE) + end if - f = this % fmu(gin) % data(imu,gout) + f = this % fmu(gin) % data(imu,gout) + end if end function scattdatahistogram_calc_f @@ -469,17 +477,21 @@ contains integer :: imu real(8) :: r - ! Find mu bin - if (mu == ONE) then - imu = size(this % fmu(gin) % data,dim=1) - 1 + if (gout < this % gmin(gin) .or. gout > this % gmax(gin)) then + f = ZERO else - imu = floor((mu + ONE)/ this % dmu + ONE) - end if + ! Find mu bin + if (mu == ONE) then + imu = size(this % fmu(gin) % data,dim=1) - 1 + else + imu = floor((mu + ONE)/ this % dmu + ONE) + end if - ! Now interpolate to find f(mu) - r = (mu - this % mu(imu)) / (this % mu(imu + 1) - this % mu(imu)) - f = (ONE - r) * this % fmu(gin) % data(imu,gout) + & - r * this % fmu(gin) % data(imu + 1,gout) + ! Now interpolate to find f(mu) + r = (mu - this % mu(imu)) / (this % mu(imu + 1) - this % mu(imu)) + f = (ONE - r) * this % fmu(gin) % data(imu,gout) + & + r * this % fmu(gin) % data(imu + 1,gout) + end if end function scattdatatabular_calc_f diff --git a/src/tally.F90 b/src/tally.F90 index 5a54d9846..94ca2812c 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -806,6 +806,7 @@ contains real(8) :: macro_scatt ! material macro scatt xs real(8) :: micro_abs ! nuclidic microscopic abs real(8) :: p_uvw(3) ! Particle's current uvw + real(8) :: mult ! Weight multiplier ! Set the direction, if needed for nuclidic data, so that nuc % get_xs ! knows wihch direction it should be using for direction-dependent @@ -866,7 +867,7 @@ contains else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'total', UVW=p_uvw) * & + score = nuc % get_xs('total',p % g,UVW=p_uvw) * & atom_density * flux end associate else @@ -908,7 +909,7 @@ contains ! Note SCORE_SCATTER_N not available for tracklength/collision. if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'scatter', UVW=p_uvw) * & + score = nuc % get_xs('scatter',p % g,UVW=p_uvw) * & atom_density * flux end associate else @@ -917,16 +918,28 @@ contains end if end if +!!! CURRENT PROBLEMS: +!!! 1) See comment jus below +!!! 2) groups and energy filters are in reverse order (i.e., low E filter is bin 1) +!!! 3) nuclide sigt/macro sigt weight change +!!! 4) do i have right p % g vs p % last_g everywhere throughout?? + +!!! This next if/else block (and equivalent in nu scatter & PN/YN) +!!! is incorrect. There is no outgoing energy group if using tracklength +!!! scoring. if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu/mult', p % last_g, & - p % last_uvw, p % mu) + score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & + p % last_uvw,p % mu) end associate else - score = score / & - macro_xs(p % material) % obj % get_xs(p % g, 'mult', & - p % last_g, & - p % last_uvw) + mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & + p % last_uvw) + if (mult > ZERO) then + score = score / mult + else + score = ZERO + end if end if @@ -944,14 +957,17 @@ contains if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu/mult', p % last_g, & - p % last_uvw, p % mu) + score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & + p % last_uvw,p % mu) end associate else - score = score / & - macro_xs(p % material) % obj % get_xs(p % g, 'mult', & - p % last_g, & - p % last_uvw) + mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & + p % last_uvw) + if (mult > ZERO) then + score = score / mult + else + score = ZERO + end if end if @@ -969,14 +985,17 @@ contains if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu/mult', p % last_g, & - p % last_uvw, p % mu) + score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & + p % last_uvw,p % mu) end associate else - score = score / & - macro_xs(p % material) % obj % get_xs(p % g, 'mult', & - p % last_g, & - p % last_uvw) + mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & + p % last_uvw) + if (mult > ZERO) then + score = score / mult + else + score = ZERO + end if end if @@ -990,7 +1009,7 @@ contains score = p % wgt if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = score * nuc % get_xs('f_mu',p % last_g,p % g, & p % last_uvw, p % mu) end associate end if @@ -1009,7 +1028,7 @@ contains score = p % wgt if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = score * nuc % get_xs('f_mu',p % last_g,p % g, & p % last_uvw, p % mu) end associate end if @@ -1028,7 +1047,7 @@ contains score = p % wgt if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = score * nuc % get_xs('f_mu',p % last_g,p % g, & p % last_uvw, p % mu) end associate end if @@ -1075,7 +1094,7 @@ contains else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'absorption', UVW=p_uvw) & + score = nuc % get_xs('absorption',p % g,UVW=p_uvw) & * atom_density * flux end associate else @@ -1091,11 +1110,10 @@ contains ! calculate fraction of absorptions that would have resulted in ! fission associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs(p % g, 'absorption', UVW=p_uvw) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) if (micro_abs > ZERO) then score = p % absorb_wgt * & - nuc % get_xs(p % g, 'fission', UVW=p_uvw) & - / micro_abs + nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs else score = ZERO end if @@ -1108,20 +1126,20 @@ contains ! fission reaction rate associate (nuc => nuclides_MG(i_nuclide) % obj) score = p % last_wgt & - * nuc % get_xs(p % g, 'fission', UVW=p_uvw) & - / nuc % get_xs(p % g, 'absorption', UVW=p_uvw) + * nuc % get_xs('fission',p % g,UVW=p_uvw) & + / nuc % get_xs('absorption',p % g,UVW=p_uvw) end associate end if else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'fission', UVW=p_uvw) * & + score = nuc % get_xs('fission',p % g,UVW=p_uvw) * & atom_density * flux end associate else - score = flux * macro_xs(p % material) % obj % get_xs(p % g, & - 'fission', UVW=p_uvw) + score = flux * macro_xs(p % material) % obj % get_xs('fission',& + p % g,UVW=p_uvw) end if end if @@ -1145,11 +1163,10 @@ contains ! calculate fraction of absorptions that would have resulted in ! nu-fission associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs(p % g, 'absorption', UVW=p_uvw) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) if (micro_abs > ZERO) then score = p % absorb_wgt * & - nuc % get_xs(p % g, 'fission', UVW=p_uvw) / & - micro_abs + nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs else score = ZERO end if @@ -1168,7 +1185,7 @@ contains else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'nu_fission', UVW=p_uvw) & + score = nuc % get_xs('nu_fission',p % g,UVW=p_uvw) & * atom_density * flux end associate else @@ -1186,10 +1203,10 @@ contains ! calculate fraction of absorptions that would have resulted in ! fission scale by kappa-fission associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs(p % g, 'absorption', UVW=p_uvw) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) if (micro_abs > ZERO) then score = p % absorb_wgt * & - nuc % get_xs(p % g, 'k_fission', UVW=p_uvw) / & + nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & micro_abs end if end associate @@ -1201,20 +1218,20 @@ contains ! the fission energy production rate associate (nuc => nuclides_MG(i_nuclide) % obj) score = p % last_wgt * & - nuc % get_xs(p % g, 'k_fission', UVW=p_uvw) / & - nuc % get_xs(p % g, 'absorption', UVW=p_uvw) + nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & + nuc % get_xs('absorption',p % g,UVW=p_uvw) end associate end if else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs(p % g, 'k_fission', UVW=p_uvw) & + score = nuc % get_xs('k_fission',p % g,UVW=p_uvw) & * atom_density * flux end associate else - score = flux * macro_xs(p % material) % obj % get_xs(p % g, & - 'k_fission', UVW=p_uvw) + score = flux * macro_xs(p % material) % obj % get_xs('k_fission', & + p % g,UVW=p_uvw) end if end if From dba40a91aa826339610eb2bb336da45637257629 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Fri, 11 Mar 2016 06:43:40 -0500 Subject: [PATCH 013/147] Saving status on updating tallying for nuclide specifi quantities --- src/input_xml.F90 | 29 ++++-- src/macroxs_header.F90 | 8 +- src/nuclide_header.F90 | 20 ++-- src/particle_header.F90 | 2 +- src/physics_mg.F90 | 2 +- src/tally.F90 | 203 ++++++++++++++++++++++++++++------------ 6 files changed, 184 insertions(+), 80 deletions(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index a7366d2cd..64016b8d5 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -2842,11 +2842,15 @@ contains allocate(t % filters(j) % real_bins(n_words)) call get_node_array(node_filt, "bins", t % filters(j) % real_bins) + ! We can save tallying time if we know that the tally bins + ! match the energy group structure. In that case, the matching bin + ! index is simply the group (after flipping for the different + ! ordering of the library and tallying systems). if (.not. run_CE) then - if (n_words /= energy_groups + 1) then - t % energy_matches_groups = .false. - else if (all(t % filters(j) % real_bins == energy_bins)) then - t % energy_matches_groups = .false. + if (n_words == energy_groups + 1) then + if (all(t % filters(j) % real_bins == & + energy_bins(energy_groups + 1:1:-1))) & + t % energy_matches_groups = .true. end if end if @@ -2861,11 +2865,15 @@ contains allocate(t % filters(j) % real_bins(n_words)) call get_node_array(node_filt, "bins", t % filters(j) % real_bins) + ! We can save tallying time if we know that the tally bins + ! match the energy group structure. In that case, the matching bin + ! index is simply the group (after flipping for the different + ! ordering of the library and tallying systems). if (.not. run_CE) then - if (n_words /= energy_groups + 1) then - t % energy_matches_groups = .false. - else if (all(t % filters(j) % real_bins == energy_bins)) then - t % energy_matches_groups = .false. + if (n_words == energy_groups + 1) then + if (all(t % filters(j) % real_bins == & + energy_bins(energy_groups + 1:1:-1))) & + t % energyout_matches_groups = .true. end if end if @@ -4502,6 +4510,7 @@ contains type(Node), pointer :: doc => null() type(Node), pointer :: node_xsdata => null() type(NodeList), pointer :: node_xsdata_list => null() + real(8), allocatable :: rev_energy_bins(:) ! Check if cross_sections.xml exists inquire(FILE=path_cross_sections, EXIST=file_exists) @@ -4523,6 +4532,7 @@ contains call fatal_error("groups element must exist!") end if + allocate(rev_energy_bins(energy_groups + 1)) allocate(energy_bins(energy_groups + 1)) if (check_for_node(doc, "group_structure")) then ! Get neutron group structure @@ -4531,6 +4541,9 @@ contains call fatal_error("group_structures element must exist!") end if + ! First reverse the order of energy_groups + energy_bins = energy_bins(energy_groups + 1:1:-1) + allocate(energy_bin_avg(energy_groups)) do i = 1, energy_groups energy_bin_avg(i) = HALF * (energy_bins(i) + energy_bins(i + 1)) diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index 6d74b081a..db1ffc479 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -251,11 +251,11 @@ contains do gin = 1, groups do gout = 1, groups this % chi(gout,gin) = this % chi(gout,gin) + atom_density * & - nuc % chi(gout) * nuc % nu_fission(gin,1) + nuc % chi(gout) * nuc % nu_fission(1,gin) end do end do this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission(:,1) + nuc % nu_fission(1,:) else this % chi = this % chi + atom_density * nuc % nu_fission do gin = 1, groups @@ -468,11 +468,11 @@ contains do gin = 1, groups do gout = 1, groups this % chi(gout,gin,:,:) = this % chi(gout,gin,:,:) + atom_density * & - nuc % chi(gout,:,:) * nuc % nu_fission(gin,1,:,:) + nuc % chi(gout,:,:) * nuc % nu_fission(1,gin,:,:) end do end do this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission(:,1,:,:) + nuc % nu_fission(1,:,:,:) else this % chi = this % chi + atom_density * nuc % nu_fission do gin = 1, groups diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index 35048454e..809ecdfa4 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -375,10 +375,10 @@ module nuclide_header ! Get nu_fission (as a vector) if (check_for_node(node_xsdata,"nu_fission")) then - allocate(temp_arr(groups * 1)) + allocate(temp_arr(1 * groups)) call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(this % nu_fission(groups,1)) - this % nu_fission = reshape(temp_arr,(/groups,1/)) + allocate(this % nu_fission(1,groups)) + this % nu_fission = reshape(temp_arr,(/1,groups/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -676,10 +676,10 @@ module nuclide_header ! Get nu_fission (as a vector) if (check_for_node(node_xsdata,"nu_fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) + allocate(temp_arr(1 * groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata,"nu_fission", temp_arr) - allocate(this % nu_fission(groups,1,this % n_azi,this % n_pol)) - this % nu_fission = reshape(temp_arr, (/groups,1,this % n_azi, & + allocate(this % nu_fission(1,groups,this % n_azi,this % n_pol)) + this % nu_fission = reshape(temp_arr, (/1,groups,this % n_azi, & this % n_pol/)) deallocate(temp_arr) else @@ -1242,6 +1242,8 @@ module nuclide_header xs = this % total(gin) case('absorption') xs = this % absorption(gin) + case('nu_fission') + xs = sum(this % nu_fission(:,gin)) case('fission') xs = this % fission(gin) case('k_fission') @@ -1293,8 +1295,8 @@ module nuclide_header case('chi') xs = this % chi(gout,iazi_,ipol_) case('f_mu', 'f_mu/mult') - if (gout < this % scatter(iazi_,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi_,ipol) % obj % gmax(gin)) then + if (gout < this % scatter(iazi_,ipol_) % obj % gmin(gin) .or. & + gout > this % scatter(iazi_,ipol_) % obj % gmax(gin)) then xs = ZERO else xs = this % scatter(iazi_,ipol_) % obj % calc_f(gin,gout,mu) @@ -1309,6 +1311,8 @@ module nuclide_header xs = this % total(gin,iazi_,ipol_) case('absorption') xs = this % absorption(gin,iazi_,ipol_) + case('nu_fission') + xs = sum(this % nu_fission(:,gin,iazi_,ipol_)) case('fission') xs = this % fission(gin,iazi_,ipol_) case('k_fission') diff --git a/src/particle_header.F90 b/src/particle_header.F90 index 4ad4119b7..8544cb38b 100644 --- a/src/particle_header.F90 +++ b/src/particle_header.F90 @@ -202,7 +202,7 @@ contains this % last_g = int(src % E) this % E = energy_bin_avg(this % g) end if - this % last_E = src % E + this % last_E = this % E end subroutine initialize_from_source diff --git a/src/physics_mg.F90 b/src/physics_mg.F90 index 6a58540c1..93a0c81e2 100644 --- a/src/physics_mg.F90 +++ b/src/physics_mg.F90 @@ -248,7 +248,7 @@ contains mu = TWO * prn() - ONE ! Sample azimuthal angle uniformly in [0,2*pi) - phi = TWO*PI*prn() + phi = TWO * PI * prn() bank_array(i) % uvw(1) = mu bank_array(i) % uvw(2) = sqrt(ONE - mu*mu) * cos(phi) bank_array(i) % uvw(3) = sqrt(ONE - mu*mu) * sin(phi) diff --git a/src/tally.F90 b/src/tally.F90 index 94ca2812c..50daa86fd 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -28,8 +28,9 @@ module tally !$omp threadprivate(position) - procedure(score_general_), pointer :: score_general => null() - procedure(get_scoring_bins_), pointer :: get_scoring_bins => null() + procedure(score_general_), pointer :: score_general => null() + procedure(score_analog_tally_), pointer :: score_analog_tally => null() + procedure(get_scoring_bins_), pointer :: get_scoring_bins => null() abstract interface subroutine score_general_(p, t, start_index, filter_index, i_nuclide, & @@ -45,6 +46,11 @@ module tally real(8), intent(in) :: atom_density ! atom/b-cm end subroutine score_general_ + subroutine score_analog_tally_(p) + import Particle + type(Particle), intent(in) :: p + end subroutine score_analog_tally_ + subroutine get_scoring_bins_(p, i_tally, found_bin) import Particle type(Particle), intent(in) :: p @@ -62,11 +68,13 @@ contains subroutine init_tally_routines() if (run_CE) then - score_general => score_general_ce - get_scoring_bins => get_scoring_bins_ce + score_general => score_general_ce + score_analog_tally => score_analog_tally_ce + get_scoring_bins => get_scoring_bins_ce else - score_general => score_general_mg - get_scoring_bins => get_scoring_bins_mg + score_general => score_general_mg + score_analog_tally => score_analog_tally_mg + get_scoring_bins => get_scoring_bins_mg end if end subroutine init_tally_routines @@ -808,7 +816,7 @@ contains real(8) :: p_uvw(3) ! Particle's current uvw real(8) :: mult ! Weight multiplier - ! Set the direction, if needed for nuclidic data, so that nuc % get_xs + ! Set the direction, if needed, for nuclidic data, so that nuc % get_xs ! knows wihch direction it should be using for direction-dependent ! mgxs if (i_nuclide > 0) then @@ -918,19 +926,10 @@ contains end if end if -!!! CURRENT PROBLEMS: -!!! 1) See comment jus below -!!! 2) groups and energy filters are in reverse order (i.e., low E filter is bin 1) -!!! 3) nuclide sigt/macro sigt weight change -!!! 4) do i have right p % g vs p % last_g everywhere throughout?? - -!!! This next if/else block (and equivalent in nu scatter & PN/YN) -!!! is incorrect. There is no outgoing energy group if using tracklength -!!! scoring. if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & - p % last_uvw,p % mu) + p % last_uvw,p % mu) * TWO end associate else mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & @@ -1124,11 +1123,13 @@ contains ! All fission events will contribute, so again we can use ! particle's weight entering the collision as the estimate for the ! fission reaction rate - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = p % last_wgt & - * nuc % get_xs('fission',p % g,UVW=p_uvw) & - / nuc % get_xs('absorption',p % g,UVW=p_uvw) - end associate + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = p % last_wgt & + * nuc % get_xs('fission',p % g,UVW=p_uvw) & + / nuc % get_xs('absorption',p % g,UVW=p_uvw) + end associate + end if end if else @@ -1162,15 +1163,17 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! nu-fission - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs - else - score = ZERO - end if - end associate + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) + if (micro_abs > ZERO) then + score = p % absorb_wgt * & + nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs + else + score = ZERO + end if + end associate + end if else ! Skip any non-fission events if (.not. p % fission) cycle SCORE_LOOP @@ -1185,8 +1188,8 @@ contains else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('nu_fission',p % g,UVW=p_uvw) & - * atom_density * flux + score = nuc % get_xs('nu_fission',p % g,UVW=p_uvw) * & + atom_density * flux end associate else score = material_xs % nu_fission * flux @@ -1202,25 +1205,29 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! fission scale by kappa-fission - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & - micro_abs - end if - end associate + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) + if (micro_abs > ZERO) then + score = p % absorb_wgt * & + nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & + micro_abs + end if + end associate + end if else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission events will contribute, so again we can use ! particle's weight entering the collision as the estimate for ! the fission energy production rate - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = p % last_wgt * & - nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & - nuc % get_xs('absorption',p % g,UVW=p_uvw) - end associate + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = p % last_wgt * & + nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & + nuc % get_xs('absorption',p % g,UVW=p_uvw) + end associate + end if end if else @@ -1242,6 +1249,16 @@ contains end select + ! If we have a nuclidic tally, we need to scale the score by the nuclides + ! macroscopic total xs over the material's macroscopic total, since we did + ! not sample a specfic nuclide in the physics module. + if (t % estimator == ESTIMATOR_ANALOG .and. i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = score * (nuc % get_xs('total',p % g,UVW=p_uvw) * & + atom_density / material_xs % total) + end associate + end if + !######################################################################### ! Expand score if necessary and add to tally results. call expand_and_score(p, t, score_index, filter_index, score_bin, & @@ -1422,7 +1439,7 @@ contains ! triggered at every collision, not every event !=============================================================================== - subroutine score_analog_tally(p) + subroutine score_analog_tally_ce(p) type(Particle), intent(in) :: p @@ -1432,17 +1449,9 @@ contains ! position during the loop integer :: filter_index ! single index for single bin integer :: i_nuclide ! index in nuclides array - real(8) :: last_wgt ! pre-collision particle weight - real(8) :: wgt ! post-collision particle weight - real(8) :: mu ! cosine of angle of collision logical :: found_bin ! scoring bin found? type(TallyObject), pointer :: t - ! Copy particle's pre- and post-collision weight and angle - last_wgt = p % last_wgt - wgt = p % wgt - mu = p % mu - ! A loop over all tallies is necessary because we need to simultaneously ! determine different filter bins for the same tally in order to score to it @@ -1521,7 +1530,87 @@ contains ! Reset tally map positioning position = 0 - end subroutine score_analog_tally + end subroutine score_analog_tally_ce + + subroutine score_analog_tally_mg(p) + + type(Particle), intent(in) :: p + + integer :: i, m + integer :: i_tally + integer :: k ! loop index for nuclide bins + ! position during the loop + integer :: filter_index ! single index for single bin + integer :: i_nuclide ! index in nuclides array + logical :: found_bin ! scoring bin found? + type(TallyObject), pointer :: t + type(Material), pointer :: mat + real(8) :: atom_density + + ! A loop over all tallies is necessary because we need to simultaneously + ! determine different filter bins for the same tally in order to score to it + + TALLY_LOOP: do i = 1, active_analog_tallies % size() + ! Get index of tally and pointer to tally + i_tally = active_analog_tallies % get_item(i) + t => tallies(i_tally) + + ! Get pointer to current material. We need this in order to determine what + ! nuclides are in the material + mat => materials(p % material) + + ! ======================================================================= + ! DETERMINE SCORING BIN COMBINATION + + call get_scoring_bins(p, i_tally, found_bin) + if (.not. found_bin) cycle + + ! ======================================================================= + ! CALCULATE RESULTS AND ACCUMULATE TALLY + + ! If we have made it here, we have a scoring combination of bins for this + ! tally -- now we need to determine where in the results array we should + ! be accumulating the tally values + + ! Determine scoring index for this filter combination + filter_index = sum((matching_bins(1:t%n_filters) - 1) * t % stride) + 1 + + ! Check for nuclide bins + k = 0 + NUCLIDE_LOOP: do while (k < t % n_nuclide_bins) + + ! Increment the index in the list of nuclide bins + k = k + 1 + + i_nuclide = t % nuclide_bins(k) + + ! Check to see if this nuclide was in the material of our collision. + do m = 1, mat % n_nuclides + if (mat % nuclide(m) == i_nuclide) then + atom_density = mat % atom_density(m) + exit + end if + end do + + ! Determine score for each bin + call score_general(p, t, (k-1)*t % n_score_bins, filter_index, & + i_nuclide, atom_density, ZERO) + + end do NUCLIDE_LOOP + + ! If the user has specified that we can assume all tallies are spatially + ! separate, this implies that once a tally has been scored to, we needn't + ! check the others. This cuts down on overhead when there are many + ! tallies specified + + if (assume_separate) exit TALLY_LOOP + + end do TALLY_LOOP + + ! Reset tally map positioning + position = 0 + + end subroutine score_analog_tally_mg !=============================================================================== ! SCORE_FISSION_EOUT handles a special case where we need to store neutron @@ -2619,7 +2708,6 @@ contains end if end if - case (FILTER_ENERGYOUT) if (t % energyout_matches_groups) then ! Since all groups are filters, the filter bin is the group @@ -2643,7 +2731,6 @@ contains end if end if - case (FILTER_MU) ! determine mu bin n = t % filters(i) % n_bins From a2d8e9580456e73f2af2999160bba37202d2e4b1 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 12 Mar 2016 15:23:32 -0500 Subject: [PATCH 014/147] 1) MG tallies were all sorts of messed up, mostly for nuclidic tallies which i am not a common user for sadly. Now all should be good to go, but i still want to thoroughly test this by seeing if i can create a mgxs library from mg mode and compare that library to the inputted library - both should be the same!. 2) fixed state_point reading/writing issue when using MG mode and nuclidic tallies (pointing to CE nuclide array not MG array), 3) removed N_1N from MG mode, makes no sense to include and at best is a duplicate of scatter, 4) cleaned up MG general tallying routine by combining select cases for all the SCORE_SCATTER* options, and did same for nu-scatter, 5) added ability to do nu-scatter or nu-scatter-0 score type with tracklength if no outgoing E filters applied in MG mode, just like scatter or scatter-0 --- src/input_xml.F90 | 27 +++- src/macroxs_header.F90 | 55 ++++++-- src/nuclide_header.F90 | 20 ++- src/physics_mg.F90 | 3 +- src/state_point.F90 | 6 +- src/summary.F90 | 6 +- src/tally.F90 | 290 ++++++++++++++++------------------------- 7 files changed, 201 insertions(+), 206 deletions(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 64016b8d5..89dcc5e99 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -3332,8 +3332,13 @@ contains case ('nu-scatter') t % score_bins(j) = SCORE_NU_SCATTER - ! Set tally estimator to analog - t % estimator = ESTIMATOR_ANALOG + ! Set tally estimator to analog for CE mode + ! (MG mode has all data available without a collision being + ! necessary) + if (run_CE) then + t % estimator = ESTIMATOR_ANALOG + end if + case ('scatter-n') if (n_order == 0) then t % score_bins(j) = SCORE_SCATTER @@ -3345,12 +3350,16 @@ contains t % moment_order(j) = n_order case ('nu-scatter-n') - ! Set tally estimator to analog - t % estimator = ESTIMATOR_ANALOG if (n_order == 0) then t % score_bins(j) = SCORE_NU_SCATTER else t % score_bins(j) = SCORE_NU_SCATTER_N + ! Set tally estimator to analog for CE mode + ! (MG mode has all data available without a collision being + ! necessary) + if (run_CE) then + t % estimator = ESTIMATOR_ANALOG + end if end if t % moment_order(j) = n_order @@ -3391,10 +3400,14 @@ contains call fatal_error("Diffusion score no longer supported for tallies, & &please remove") case ('n1n') - t % score_bins(j) = SCORE_N_1N + if (run_CE) then + t % score_bins(j) = SCORE_N_1N - ! Set tally estimator to analog - t % estimator = ESTIMATOR_ANALOG + ! Set tally estimator to analog + t % estimator = ESTIMATOR_ANALOG + else + call fatal_error("Cannot tally n1n rate in multi-group mode!") + end if case ('n2n', '(n,2n)') t % score_bins(j) = N_2N diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 index db1ffc479..ff04d8a4e 100644 --- a/src/macroxs_header.F90 +++ b/src/macroxs_header.F90 @@ -42,13 +42,14 @@ module macroxs_header integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? end subroutine macroxs_init_ - function macroxs_get_xs_(this, xstype, gin, gout, uvw) result(xs) + function macroxs_get_xs_(this, xstype, gin, gout, uvw, mu) result(xs) import MacroXS class(MacroXS), intent(in) :: this ! The MacroXS to initialize character(*) , intent(in) :: xstype ! Cross Section Type integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle real(8) :: xs ! Resultant xs end function macroxs_get_xs_ @@ -547,12 +548,13 @@ contains ! MACROXS_*_GET_XS returns the requested data type !=============================================================================== - function macroxsiso_get_xs(this, xstype, gin, gout, uvw) result(xs) + function macroxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) class(MacroXSIso), intent(in) :: this ! The MacroXS to initialize character(*) , intent(in) :: xstype ! Type of xs requested integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle real(8) :: xs ! Requested x/s select case(xstype) @@ -562,7 +564,7 @@ contains xs = this % absorption(gin) case('fission') xs = this % fission(gin) - case('k_fission') + case('kappa_fission') xs = this % k_fission(gin) case('nu_fission') xs = this % nu_fission(gin) @@ -577,19 +579,33 @@ contains xs = this % scatter % mult(gin) % data(gout) end if else - xs = sum(this % scatter % mult(gin) % data(:)) + xs = dot_product(this % scatter % mult(gin) % data, & + this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data) + xs = xs / this % scatter % scattxs(gin) + end if + case('f_mu', 'f_mu/mult') + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % calc_f(gin, gout, mu) + if (xstype == 'f_mu/mult') then + xs = xs / this % scatter % mult(gin) % data(gout) + end if end if end select end function macroxsiso_get_xs - function macroxsangle_get_xs(this, xstype, gin, gout, uvw) result(xs) - class(MacroXSAngle), intent(in) :: this ! The MacroXS to initialize - character(*) , intent(in) :: xstype ! Type of xs requested - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Energy group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8) :: xs ! Requested x/s + function macroxsangle_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) + class(MacroXSAngle), intent(in) :: this ! The MacroXS to initialize + character(*) , intent(in) :: xstype ! Type of xs requested + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Energy group + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle + real(8) :: xs ! Requested x/s integer :: iazi, ipol @@ -602,7 +618,7 @@ contains xs = this % absorption(gin,iazi,ipol) case('fission') xs = this % fission(gin,iazi,ipol) - case('k_fission') + case('kappa_fission') xs = this % k_fission(gin,iazi,ipol) case('nu_fission') xs = this % nu_fission(gin,iazi,ipol) @@ -617,7 +633,20 @@ contains xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) end if else - xs = sum(this % scatter(iazi,ipol) % obj % mult(gin) % data(:)) + xs = dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & + this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data) + xs = xs / this % scatter(iazi,ipol) % obj % scattxs(gin) + end if + case('f_mu', 'f_mu/mult') + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % calc_f(gin,gout,mu) + if (xstype == 'f_mu/mult') then + xs = xs / this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if end if end select end if diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index 809ecdfa4..7a093fa77 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -1215,7 +1215,7 @@ module nuclide_header xs = ZERO if ((xstype == 'nu_fission' .or. xstype == 'fission' .or. xstype =='chi' & - .or. xstype =='k_fission') .and. (.not. this % fissionable)) then + .or. xstype =='kappa_fission') .and. (.not. this % fissionable)) then return end if @@ -1246,7 +1246,7 @@ module nuclide_header xs = sum(this % nu_fission(:,gin)) case('fission') xs = this % fission(gin) - case('k_fission') + case('kappa_fission') if (allocated(this % k_fission)) then xs = this % k_fission(gin) end if @@ -1254,6 +1254,11 @@ module nuclide_header xs = this % chi(gin) case('scatter') xs = this % scatter % scattxs(gin) + case('mult') + xs = dot_product(this % scatter % mult(gin) % data, & + this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data) + xs = xs / this % scatter % scattxs(gin) end select end if end function nuclideiso_get_xs @@ -1264,8 +1269,8 @@ module nuclide_header character(*), intent(in) :: xstype ! Cross Section Type integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: mu ! Change in angle real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle integer, optional, intent(in) :: iazi ! Azimuthal Index integer, optional, intent(in) :: ipol ! Polar Index real(8) :: xs ! Resultant xs @@ -1275,7 +1280,7 @@ module nuclide_header xs = ZERO if ((xstype == 'nu_fission' .or. xstype == 'fission' .or. xstype =='chi' & - .or. xstype =='k_fission') .and. (.not. this % fissionable)) then + .or. xstype =='kappa_fission') .and. (.not. this % fissionable)) then return end if @@ -1315,7 +1320,7 @@ module nuclide_header xs = sum(this % nu_fission(:,gin,iazi_,ipol_)) case('fission') xs = this % fission(gin,iazi_,ipol_) - case('k_fission') + case('kappa_fission') if (allocated(this % k_fission)) then xs = this % k_fission(gin,iazi_,ipol_) end if @@ -1323,6 +1328,11 @@ module nuclide_header xs = this % chi(gin,iazi_,ipol_) case('scatter') xs = this % scatter(iazi_,ipol_) % obj % scattxs(gin) + case('mult') + xs = dot_product(this % scatter(iazi_,ipol_) % obj % mult(gin) % data, & + this % scatter(iazi_,ipol_) % obj % scattxs(gin) * & + this % scatter(iazi_,ipol_) % obj % energy(gin) % data) + xs = xs / this % scatter(iazi_,ipol_) % obj % scattxs(gin) end select end if diff --git a/src/physics_mg.F90 b/src/physics_mg.F90 index 93a0c81e2..209808dc9 100644 --- a/src/physics_mg.F90 +++ b/src/physics_mg.F90 @@ -77,6 +77,7 @@ contains call create_fission_sites(p, p % secondary_bank, p % n_secondary) end if end if + ! If survival biasing is being used, the following subroutine adjusts the ! weight of the particle. Otherwise, it checks to see if absorption occurs @@ -256,7 +257,7 @@ contains ! Sample secondary energy distribution for fission reaction and set energy ! in fission bank bank_array(i) % E = & - real(xs % sample_fission_energy(p % g, fission_bank(i) % uvw), 8) + real(xs % sample_fission_energy(p % g, bank_array(i) % uvw), 8) end do ! increment number of bank sites diff --git a/src/state_point.F90 b/src/state_point.F90 index 6c0e309e2..ccd368b49 100644 --- a/src/state_point.F90 +++ b/src/state_point.F90 @@ -295,7 +295,11 @@ contains NUCLIDE_LOOP: do j = 1, tally%n_nuclide_bins if (tally%nuclide_bins(j) > 0) then ! Get index in cross section listings for this nuclide - i_list = nuclides(tally%nuclide_bins(j))%listing + if (run_CE) then + i_list = nuclides(tally % nuclide_bins(j)) % listing + else + i_list = nuclides_MG(tally % nuclide_bins(j)) % obj % listing + end if ! Determine position of . in alias string (e.g. "U-235.71c"). If ! no . is found, just use the entire string. diff --git a/src/summary.F90 b/src/summary.F90 index e662aa473..41dbee702 100644 --- a/src/summary.F90 +++ b/src/summary.F90 @@ -630,7 +630,11 @@ contains allocate(str_array(t%n_nuclide_bins)) NUCLIDE_LOOP: do j = 1, t%n_nuclide_bins if (t%nuclide_bins(j) > 0) then - i_list = nuclides(t%nuclide_bins(j))%listing + if (run_CE) then + i_list = nuclides(t % nuclide_bins(j)) % listing + else + i_list = nuclides_MG(t % nuclide_bins(j)) % obj % listing + end if i_xs = index(xs_listings(i_list)%alias, '.') if (i_xs > 0) then str_array(j) = xs_listings(i_list)%alias(1:i_xs - 1) diff --git a/src/tally.F90 b/src/tally.F90 index 50daa86fd..d23cd8691 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -814,12 +814,11 @@ contains real(8) :: macro_scatt ! material macro scatt xs real(8) :: micro_abs ! nuclidic microscopic abs real(8) :: p_uvw(3) ! Particle's current uvw - real(8) :: mult ! Weight multiplier - ! Set the direction, if needed, for nuclidic data, so that nuc % get_xs - ! knows wihch direction it should be using for direction-dependent - ! mgxs - if (i_nuclide > 0) then + ! Set the direction to use with get_xs + if (t % estimator == ESTIMATOR_ANALOG) then + p_uvw = p % last_uvw + else p_uvw = p % coord(p % n_coord) % uvw end if @@ -904,153 +903,92 @@ contains end if - case (SCORE_SCATTER, SCORE_SCATTER_N) + case (SCORE_SCATTER, SCORE_SCATTER_N, SCORE_SCATTER_PN, SCORE_SCATTER_YN) if (t % estimator == ESTIMATOR_ANALOG) then ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP + if (p % event /= EVENT_SCATTER) then + if (score_bin == SCORE_SCATTER_PN) then + i = i + t % moment_order(i) + else + i = i + (t % moment_order(i) + 1)**2 - 1 + end if + cycle SCORE_LOOP + end if + ! Since only scattering events make it here, again we can use ! the weight entering the collision as the estimator for the ! reaction rate score = p % last_wgt + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = score * nuc % get_xs('f_mu',p % last_g,p % g, & + UVW=p_uvw,MU=p % mu) / & + macro_xs(p % material) % obj % get_xs('f_mu',p % last_g, & + p % g, UVW=p_uvw, & + MU=p % mu) + end associate + end if + else ! Note SCORE_SCATTER_N not available for tracklength/collision. + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = nuc % get_xs('scatter',p % g,UVW=p_uvw) * & + atom_density * flux / & + nuc % get_xs('mult',p % g,UVW=p_uvw) + end associate + else + ! Get the scattering x/s (stored in % elastic) and take away + ! the multiplication baked in to sigS + score = material_xs % elastic * flux / & + macro_xs(p % material) % obj % get_xs('mult',p % g,UVW=p_uvw) + end if + end if + + + case (SCORE_NU_SCATTER, SCORE_NU_SCATTER_N, SCORE_NU_SCATTER_PN, & + SCORE_NU_SCATTER_YN) + if (t % estimator == ESTIMATOR_ANALOG) then + ! Skip any event where the particle didn't scatter + if (p % event /= EVENT_SCATTER) then + if (score_bin == SCORE_NU_SCATTER_PN) then + i = i + t % moment_order(i) + else if (score_bin == SCORE_NU_SCATTER_YN) then + i = i + (t % moment_order(i) + 1)**2 - 1 + end if + cycle SCORE_LOOP + end if + + ! For scattering production, we need to use the pre-collision + ! weight times the multiplicity as the estimate for the number of + ! neutrons exiting a reaction with neutrons in the exit channel + score = p % wgt + + if (i_nuclide > 0) then + associate (nuc => nuclides_MG(i_nuclide) % obj) + score = score * nuc % get_xs('f_mu',p % last_g,p % g, & + UVW=p_uvw,MU=p % mu) / & + macro_xs(p % material) % obj % get_xs('f_mu',p % last_g, & + p % g, UVW=p_uvw, & + MU=p % mu) + end associate + end if + + else + ! Note SCORE_NU_SCATTER_* not available for tracklength/collision. if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) score = nuc % get_xs('scatter',p % g,UVW=p_uvw) * & atom_density * flux end associate else - ! Get the scattering x/s (stored in % elastic) + ! Get the scattering x/s (stored in % elastic) and take away + ! the multiplication baked in to sigS score = material_xs % elastic * flux end if end if - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & - p % last_uvw,p % mu) * TWO - end associate - else - mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & - p % last_uvw) - if (mult > ZERO) then - score = score / mult - else - score = ZERO - end if - end if - - - case (SCORE_SCATTER_PN) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) then - i = i + t % moment_order(i) - cycle SCORE_LOOP - end if - ! Since only scattering events make it here, again we can use - ! the weight entering the collision as the estimator for the - ! reaction rate - score = p % last_wgt - - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & - p % last_uvw,p % mu) - end associate - else - mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & - p % last_uvw) - if (mult > ZERO) then - score = score / mult - else - score = ZERO - end if - end if - - - case (SCORE_SCATTER_YN) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) then - i = i + (t % moment_order(i) + 1)**2 - 1 - cycle SCORE_LOOP - end if - ! Since only scattering events make it here, again we can use - ! the weight entering the collision as the estimator for the - ! reaction rate - score = p % last_wgt - - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu/mult',p % last_g,p % g, & - p % last_uvw,p % mu) - end associate - else - mult = macro_xs(p % material) % obj % get_xs('mult',p % last_g,p % g, & - p % last_uvw) - if (mult > ZERO) then - score = score / mult - else - score = ZERO - end if - end if - - - case (SCORE_NU_SCATTER, SCORE_NU_SCATTER_N) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP - ! For scattering production, we need to use the pre-collision - ! weight times the multiplicity as the estimate for the number of - ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu',p % last_g,p % g, & - p % last_uvw, p % mu) - end associate - end if - - - case (SCORE_NU_SCATTER_PN) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) then - i = i + t % moment_order(i) - cycle SCORE_LOOP - end if - ! For scattering production, we need to use the pre-collision - ! weight times the multiplicity as the estimate for the number of - ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu',p % last_g,p % g, & - p % last_uvw, p % mu) - end associate - end if - - - case (SCORE_NU_SCATTER_YN) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) then - i = i + (t % moment_order(i) + 1)**2 - 1 - cycle SCORE_LOOP - end if - ! For scattering production, we need to use the pre-collision - ! weight times the multiplicity as the estimate for the number of - ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu',p % last_g,p % g, & - p % last_uvw, p % mu) - end associate - end if - case (SCORE_TRANSPORT) ! Only analog estimators are available. @@ -1066,16 +1004,6 @@ contains score = (macro_total - p % mu * macro_scatt) * (ONE / macro_scatt) - case (SCORE_N_1N) - ! Only analog estimators are available. - ! Skip any event where the particle didn't scatter - if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP - ! Skip any events where weight of particle changed - if (p % wgt /= p % last_wgt) cycle SCORE_LOOP - ! All events that reach this point are (n,1n) reactions - score = p % last_wgt - - case (SCORE_ABSORPTION) if (t % estimator == ESTIMATOR_ANALOG) then if (survival_biasing) then @@ -1125,10 +1053,19 @@ contains ! fission reaction rate if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = p % last_wgt & - * nuc % get_xs('fission',p % g,UVW=p_uvw) & - / nuc % get_xs('absorption',p % g,UVW=p_uvw) + score = p % last_wgt * & + nuc % get_xs('fission',p % g,UVW=p_uvw) * & + atom_density / & + macro_xs(p % material) % obj % get_xs('absorption',& + p % g,UVW=p_uvw) end associate + else + score = p % last_wgt * & + macro_xs(p % material) % obj % get_xs('fission', & + p % g,UVW=p_uvw) * & + atom_density / & + macro_xs(p % material) % obj % get_xs('absorption', & + p % g,UVW=p_uvw) end if end if @@ -1139,7 +1076,7 @@ contains atom_density * flux end associate else - score = flux * macro_xs(p % material) % obj % get_xs('fission',& + score = flux * macro_xs(p % material) % obj % get_xs('fission', & p % g,UVW=p_uvw) end if @@ -1168,7 +1105,7 @@ contains micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) if (micro_abs > ZERO) then score = p % absorb_wgt * & - nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs + nuc % get_xs('nu_fission',p % g,UVW=p_uvw) / micro_abs else score = ZERO end if @@ -1198,47 +1135,54 @@ contains case (SCORE_KAPPA_FISSION) - ! Determine kappa-fission cross section - score = ZERO if (t % estimator == ESTIMATOR_ANALOG) then if (survival_biasing) then ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in - ! fission scale by kappa-fission - if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & - micro_abs - end if - end associate - end if + ! fission + associate (nuc => nuclides_MG(i_nuclide) % obj) + micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) + if (micro_abs > ZERO) then + score = p % absorb_wgt * & + nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) / micro_abs + else + score = ZERO + end if + end associate else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission events will contribute, so again we can use - ! particle's weight entering the collision as the estimate for - ! the fission energy production rate + ! particle's weight entering the collision as the estimate for the + ! fission reaction rate if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) score = p % last_wgt * & - nuc % get_xs('k_fission',p % g,UVW=p_uvw) / & - nuc % get_xs('absorption',p % g,UVW=p_uvw) + nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + atom_density / & + macro_xs(p % material) % obj % get_xs('absorption',& + p % g,UVW=p_uvw) end associate + else + score = p % last_wgt * & + macro_xs(p % material) % obj % get_xs('kappa_fission', & + p % g,UVW=p_uvw) * & + atom_density / & + macro_xs(p % material) % obj % get_xs('absorption', & + p % g,UVW=p_uvw) end if end if else if (i_nuclide > 0) then associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('k_fission',p % g,UVW=p_uvw) & - * atom_density * flux + score = nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + atom_density * flux end associate else - score = flux * macro_xs(p % material) % obj % get_xs('k_fission', & + score = flux * macro_xs(p % material) % obj % get_xs('kappa_fission', & p % g,UVW=p_uvw) + end if end if @@ -1249,16 +1193,6 @@ contains end select - ! If we have a nuclidic tally, we need to scale the score by the nuclides - ! macroscopic total xs over the material's macroscopic total, since we did - ! not sample a specfic nuclide in the physics module. - if (t % estimator == ESTIMATOR_ANALOG .and. i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * (nuc % get_xs('total',p % g,UVW=p_uvw) * & - atom_density / material_xs % total) - end associate - end if - !######################################################################### ! Expand score if necessary and add to tally results. call expand_and_score(p, t, score_index, filter_index, score_bin, & From a3e3c8278ef5e7aa55e79ebf92706ca8e6278653 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 12 Mar 2016 15:30:44 -0500 Subject: [PATCH 015/147] Updating tallying test for previous commit --- tests/test_mg_tallies/results_true.dat | 8 ++++---- 1 file changed, 4 insertions(+), 4 deletions(-) diff --git a/tests/test_mg_tallies/results_true.dat b/tests/test_mg_tallies/results_true.dat index 5f4964a4e..debbfa537 100644 --- a/tests/test_mg_tallies/results_true.dat +++ b/tests/test_mg_tallies/results_true.dat @@ -2892,12 +2892,12 @@ tally 1: 0.000000E+00 0.000000E+00 tally 2: -4.075585E+01 -3.339527E+02 +4.076711E+01 +3.341374E+02 4.077838E+01 3.343221E+02 -6.274554E+00 -7.936999E+00 +6.274781E+00 +7.937573E+00 6.275007E+00 7.938146E+00 1.122968E+02 From eb75826cae283d7b93bdfbad9ea188ca91785f0a Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 12 Mar 2016 15:52:54 -0500 Subject: [PATCH 016/147] Added abstract class for the mgxs data. Still need to do the actual extended types Iso and Angle --- src/mgxs_header.F90 | 129 +++++++++++++++++++++++++++++++++++++++++ src/nuclide_header.F90 | 2 +- 2 files changed, 130 insertions(+), 1 deletion(-) create mode 100644 src/mgxs_header.F90 diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 new file mode 100644 index 000000000..8ae55da94 --- /dev/null +++ b/src/mgxs_header.F90 @@ -0,0 +1,129 @@ +module mgxs_header + + use constants, only: MAX_FILE_LEN, ZERO, ONE, TWO, PI + use error, only: fatal_error + use list_header, only: ListInt + use material_header, only: material + use math, only: calc_pn, calc_rn, expand_harmonic, & + evaluate_legendre, find_angle + use nuclide_header, only: NuclideMGContainer, MaterialMacroXS + use random_lcg, only: prn + use scattdata_header + use string + use xml_interface + +!=============================================================================== +! MGXS contains the base mgxs data for a nuclide/material +!=============================================================================== + + type, abstract :: Mgxs + character(12) :: name ! name of dataset, e.g. 92235.03c + integer :: zaid ! Z and A identifier, e.g. 92235 + real(8) :: awr ! Atomic Weight Ratio + integer :: listing ! index in xs_listings + real(8) :: kT ! temperature in MeV (k*T) + + ! Fission information + logical :: fissionable ! mgxs object is fissionable? + integer :: scatt_type ! either legendre, histogram, or tabular. + + contains + procedure(mgxs_print_), deferred :: print ! Writes object info + procedure(mgxs_init_xml_), deferred :: init_xml ! Initialize the data + procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs + procedure(mgxs_combine_), deferred :: combine ! initializes object + ! Sample the outgoing energy from a fission event + procedure(mgxs_sample_fission_), deferred :: sample_fission_energy + ! Sample the outgoing energy and angle from a scatter event + procedure(mgxs_sample_scatter_), deferred :: sample_scatter + ! Calculate the material specific MGXS data from the nuclides + procedure(mgxs_calculate_xs_), deferred :: calculate_xs + end type Mgxs + + abstract interface + subroutine mgxs_print_(this, unit) + import Mgxs + class(Mgxs),intent(in) :: this + integer, optional, intent(in) :: unit + end subroutine mgxs_print_ + + subroutine mgxs_init_xml_(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order) + import Mgxs, Node + class(Mgxs), intent(inout) :: this ! Working Object + type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml + integer, intent(in) :: groups ! Number of Energy groups + logical, intent(in) :: get_kfiss ! Need Kappa-Fission? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order + end subroutine mgxs_init_xml_ + + function mgxs_get_xs_(this, xstype, gin, gout, uvw, mu, iazi, ipol) & + result(xs) + import Mgxs + class(Mgxs), intent(in) :: this + character(*), intent(in) :: xstype ! Cross Section Type + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Group + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle + integer, optional, intent(in) :: iazi ! Azimuthal Index + integer, optional, intent(in) :: ipol ! Polar Index + real(8) :: xs ! Resultant xs + end function mgxs_get_xs_ + + pure function mgxs_calc_f_(this, gin, gout, mu, uvw, iazi, ipol) result(f) + import Mgxs + class(Mgxs), intent(in) :: this + integer, intent(in) :: gin ! Incoming Energy Group + integer, intent(in) :: gout ! Outgoing Energy Group + real(8), intent(in) :: mu ! Angle of interest + real(8), intent(in), optional :: uvw(3) ! Direction vector + integer, intent(in), optional :: iazi ! Incoming Energy Group + integer, intent(in), optional :: ipol ! Outgoing Energy Group + real(8) :: f ! Return value of f(mu) + + end function mgxs_calc_f_ + + subroutine mgxs_combine_(this, mat, nuclides, groups, get_kfiss, get_fiss, & + max_order, scatt_type) + import Mgxs, Material, NuclideMGContainer, MAX_LINE_LEN + class(Mgxs), intent(inout) :: this ! The Mgxs to initialize + type(Material), pointer, intent(in) :: mat ! base material + type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? + end subroutine mgxs_combine_ + + function mgxs_sample_fission_(this, gin, uvw) result(gout) + import Mgxs + class(Mgxs), intent(in) :: this ! Data to work with + integer, intent(in) :: gin ! Incoming energy group + real(8), intent(in) :: uvw(3) ! Particle Direction + integer :: gout ! Sampled outgoing group + + end function mgxs_sample_fission_ + + subroutine mgxs_sample_scatter_(this, uvw, gin, gout, mu, wgt) + import Mgxs + class(Mgxs), intent(in) :: this + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + integer, intent(in) :: gin ! Incoming neutron group + integer, intent(out) :: gout ! Sampled outgoin group + real(8), intent(out) :: mu ! Sampled change in angle + real(8), intent(inout) :: wgt ! Particle weight + end subroutine mgxs_sample_scatter_ + + subroutine mgxs_calculate_xs_(this, gin, uvw, xs) + import Mgxs, MaterialMacroXS + class(Mgxs), intent(in) :: this + integer, intent(in) :: gin ! Incoming neutron group + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + type(MaterialMacroXS), intent(inout) :: xs + end subroutine mgxs_calculate_xs_ + end interface + +end module mgxs_header \ No newline at end of file diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index 3a75e8b61..e964e970d 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -28,7 +28,7 @@ module nuclide_header real(8) :: kT ! temperature in MeV (k*T) ! Fission information - logical :: fissionable ! nuclide is fissionable? + logical :: fissionable ! nuclide is fissionable? contains procedure(nuclide_print_), deferred :: print ! Writes nuclide info From 96c5e42858b3d6819632becbd763fead1d988429 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 13 Mar 2016 09:00:45 -0400 Subject: [PATCH 017/147] Implemented the Mgxs objects member functions so now we can start replacing NuclideMG and MacroXS directly --- src/mgxs_header.F90 | 1657 ++++++++++++++++++++++++++++++++++++++++++- 1 file changed, 1637 insertions(+), 20 deletions(-) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 8ae55da94..36e3964da 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -2,6 +2,7 @@ module mgxs_header use constants, only: MAX_FILE_LEN, ZERO, ONE, TWO, PI use error, only: fatal_error + use, intrinsic :: ISO_FORTRAN_ENV, only: OUTPUT_UNIT use list_header, only: ListInt use material_header, only: material use math, only: calc_pn, calc_rn, expand_harmonic, & @@ -28,27 +29,21 @@ module mgxs_header integer :: scatt_type ! either legendre, histogram, or tabular. contains - procedure(mgxs_print_), deferred :: print ! Writes object info - procedure(mgxs_init_xml_), deferred :: init_xml ! Initialize the data - procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs - procedure(mgxs_combine_), deferred :: combine ! initializes object - ! Sample the outgoing energy from a fission event + procedure(mgxs_init_file_), deferred :: init_file ! Initialize the data + procedure(mgxs_print_), deferred :: print ! Writes object info + procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs + ! procedure(mgxs_combine_), deferred :: combine ! initializes object + ! ! Sample the outgoing energy from a fission event procedure(mgxs_sample_fission_), deferred :: sample_fission_energy - ! Sample the outgoing energy and angle from a scatter event + ! ! Sample the outgoing energy and angle from a scatter event procedure(mgxs_sample_scatter_), deferred :: sample_scatter - ! Calculate the material specific MGXS data from the nuclides + ! ! Calculate the material specific MGXS data from the nuclides procedure(mgxs_calculate_xs_), deferred :: calculate_xs end type Mgxs abstract interface - subroutine mgxs_print_(this, unit) - import Mgxs - class(Mgxs),intent(in) :: this - integer, optional, intent(in) :: unit - end subroutine mgxs_print_ - - subroutine mgxs_init_xml_(this, node_xsdata, groups, get_kfiss, get_fiss, & - max_order) + subroutine mgxs_init_file_(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order) import Mgxs, Node class(Mgxs), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml @@ -56,10 +51,15 @@ module mgxs_header logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order - end subroutine mgxs_init_xml_ + end subroutine mgxs_init_file_ - function mgxs_get_xs_(this, xstype, gin, gout, uvw, mu, iazi, ipol) & - result(xs) + subroutine mgxs_print_(this, unit) + import Mgxs + class(Mgxs),intent(in) :: this + integer, optional, intent(in) :: unit + end subroutine mgxs_print_ + + function mgxs_get_xs_(this, xstype, gin, gout, uvw, mu) result(xs) import Mgxs class(Mgxs), intent(in) :: this character(*), intent(in) :: xstype ! Cross Section Type @@ -67,8 +67,6 @@ module mgxs_header integer, optional, intent(in) :: gout ! Outgoing Group real(8), optional, intent(in) :: uvw(3) ! Requested Angle real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index real(8) :: xs ! Resultant xs end function mgxs_get_xs_ @@ -126,4 +124,1623 @@ module mgxs_header end subroutine mgxs_calculate_xs_ end interface +!=============================================================================== +! MGXSISO contains the base MGXS data specifically for +! isotropically weighted MGXS +!=============================================================================== + + type, extends(Mgxs) :: MgxsIso + + ! Microscopic cross sections + real(8), allocatable :: total(:) ! total cross section + real(8), allocatable :: absorption(:) ! absorption cross section + class(ScattData), allocatable :: scatter ! scattering information + real(8), allocatable :: nu_fission(:) ! fission matrix (Gout x Gin) + real(8), allocatable :: k_fission(:) ! kappa-fission + real(8), allocatable :: fission(:) ! neutron production + real(8), allocatable :: chi(:,:) ! Fission Spectra + + contains + procedure :: init_file => mgxsiso_init_file ! Initialize Nuclidic MGXS Data + procedure :: print => mgxsiso_print ! Writes nuclide info + procedure :: get_xs => mgxsiso_get_xs ! Gets Size of Data w/in Object + ! procedure :: combine => mgxsiso_combine ! inits object + procedure :: sample_fission_energy => mgxsiso_sample_fission_energy + procedure :: sample_scatter => mgxsiso_sample_scatter + procedure :: calculate_xs => mgxsiso_calculate_xs + end type MgxsIso + +!=============================================================================== +! MGXSANGLE contains the base MGXS data specifically for +! angular flux weighted MGXS +!=============================================================================== + + type, extends(Mgxs) :: MgxsAngle + + ! Microscopic cross sections + real(8), allocatable :: total(:,:,:) ! total cross section + real(8), allocatable :: absorption(:,:,:) ! absorption cross section + class(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information + real(8), allocatable :: nu_fission(:,:,:) ! fission matrix (Gout x Gin) + real(8), allocatable :: k_fission(:,:,:) ! kappa-fission + real(8), allocatable :: fission(:,:,:) ! neutron production + real(8), allocatable :: chi(:,:,:,:) ! Fission Spectra + ! In all cases, right-most indices are theta, phi + integer :: n_pol ! Number of polar angles + integer :: n_azi ! Number of azimuthal angles + real(8), allocatable :: polar(:) ! polar angles + real(8), allocatable :: azimuthal(:) ! azimuthal angles + + contains + procedure :: init_file => mgxsang_init_file ! Initialize Nuclidic MGXS Data + procedure :: print => mgxsang_print ! Writes nuclide info + procedure :: get_xs => mgxsang_get_xs ! Gets Size of Data w/in Object + ! procedure :: combine => mgxsang_combine ! inits object + procedure :: sample_fission_energy => mgxsang_sample_fission_energy + procedure :: sample_scatter => mgxsang_sample_scatter + procedure :: calculate_xs => mgxsang_calculate_xs + end type MgxsAngle + +!=============================================================================== +! MGXSCONTAINER pointer array for storing Nuclides +!=============================================================================== + + type MgxsContainer + class(Mgxs), pointer :: obj + end type MgxsContainer + + contains + +!=============================================================================== +! MGXS*_INIT reads in the data from the XML file. At the point of entry +! the file would have been opened and metadata read. This routine begins with +! the xsdata object node itself. +!=============================================================================== + + subroutine mgxs_init_file(this, node_xsdata) + class(Mgxs), intent(inout) :: this ! Working Object + type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml + + character(MAX_LINE_LEN) :: temp_str + + ! Load the nuclide metadata + call get_node_value(node_xsdata, "name", this % name) + this % name = to_lower(this % name) + if (check_for_node(node_xsdata, "kT")) then + call get_node_value(node_xsdata, "kT", this % kT) + else + this % kT = ZERO + end if + if (check_for_node(node_xsdata, "zaid")) then + call get_node_value(node_xsdata, "zaid", this % zaid) + else + this % zaid = -1 + end if + if (check_for_node(node_xsdata, "scatt_type")) then + call get_node_value(node_xsdata, "scatt_type", temp_str) + temp_str = trim(to_lower(temp_str)) + if (temp_str == 'legendre') then + this % scatt_type = ANGLE_LEGENDRE + else if (temp_str == 'histogram') then + this % scatt_type = ANGLE_HISTOGRAM + else if (temp_str == 'tabular') then + this % scatt_type = ANGLE_TABULAR + else + call fatal_error("Invalid Scatt Type Option!") + end if + else + this % scatt_type = ANGLE_LEGENDRE + end if + + if (check_for_node(node_xsdata, "fissionable")) then + call get_node_value(node_xsdata, "fissionable", temp_str) + temp_str = to_lower(temp_str) + if (trim(temp_str) == 'true' .or. trim(temp_str) == '1') then + this % fissionable = .true. + else + this % fissionable = .false. + end if + else + call fatal_error("Fissionable element must be set!") + end if + + end subroutine mgxs_init_file + + subroutine mgxsiso_init_file(this,node_xsdata,groups,get_kfiss,get_fiss,max_order) + class(MgxsIso), intent(inout) :: this ! Working Object + type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml + integer, intent(in) :: groups ! Number of Energy groups + logical, intent(in) :: get_kfiss ! Need Kappa-Fission? + logical, intent(in) :: get_fiss ! Need fiss data? + integer, intent(in) :: max_order ! Maximum requested order + + type(Node), pointer :: node_legendre_mu + character(MAX_LINE_LEN) :: temp_str + logical :: enable_leg_mu + real(8), allocatable :: temp_arr(:), temp_2d(:,:) + real(8), allocatable :: temp_mult(:,:) + real(8), allocatable :: scatt_coeffs(:,:,:) + real(8), allocatable :: input_scatt(:,:,:) + real(8), allocatable :: temp_scatt(:,:,:) + real(8) :: dmu, mu, norm + integer :: order, order_dim, gin, gout, l, arr_len + integer :: legendre_mu_points, imu + + ! Call generic data gathering routine (will populate the metadata) + call mgxs_init_file(this, node_xsdata) + + ! Load the more specific data + allocate(this % nu_fission(groups)) + allocate(this % chi(groups,groups)) + if (this % fissionable) then + if (check_for_node(node_xsdata,"chi")) then + ! Chi was provided, that means they are giving chi and nu-fission + ! vectors + ! Get chi + allocate(temp_arr(1 * groups)) + call get_node_array(node_xsdata,"chi",temp_arr) + do gin = 1, groups + do gout = 1, groups + this % chi(gout,gin) = temp_arr(gout) + end do + ! Normalize chi so its CDF goes to 1 + this % chi(:,gin) = this % chi(:,gin) / sum(this % chi(:,gin)) + end do + deallocate(temp_arr) + + ! Get nu_fission (as a vector) + if (check_for_node(node_xsdata,"nu_fission")) then + call get_node_array(node_xsdata,"nu_fission",this % nu_fission) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if + + else + ! chi isnt provided but is within nu_fission, existing as a matrix + ! So, get nu_fission (as a matrix) + if (check_for_node(node_xsdata,"nu_fission")) then + allocate(temp_arr(groups*groups)) + call get_node_array(node_xsdata,"nu_fission",temp_arr) + allocate(temp_2d(groups,groups)) + temp_2d = reshape(temp_arr,(/groups,groups/)) + deallocate(temp_arr) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if + + ! Set the vector nu-fission from the matrix nu-fission + do gin = 1, groups + this % nu_fission(gin) = sum(temp_2d(:,gin)) + end do + + ! Now pull out information needed for chi + this % chi = temp_2d + ! Normalize chi so its CDF goes to 1 + do gin = 1, groups + this % chi(:,gin) = this % chi(:,gin) / sum(this % chi(:,gin)) + end do + deallocate(temp_2d) + end if + ! If we have a need* for the fission and kappa-fission x/s, get them + ! (*Need is defined as will be using it to tally) + if (get_fiss) then + allocate(this % fission(groups)) + if (check_for_node(node_xsdata,"fission")) then + call get_node_array(node_xsdata,"fission",this % fission) + else + call fatal_error("Fission data missing, required due to fission& + & tallies in tallies.xml file!") + end if + end if + if (get_kfiss) then + allocate(this % k_fission(groups)) + if (check_for_node(node_xsdata,"kappa_fission")) then + call get_node_array(node_xsdata,"kappa_fission",this % k_fission) + else + call fatal_error("kappa_fission data missing, required due to & + &kappa-fission tallies in tallies.xml file!") + end if + end if + else + this % nu_fission = ZERO + this % chi = ZERO + end if + + allocate(this % absorption(groups)) + if (check_for_node(node_xsdata,"absorption")) then + call get_node_array(node_xsdata,"absorption",this % absorption) + else + call fatal_error("Must provide absorption!") + end if + + ! Get multiplication data if present + allocate(temp_mult(groups, groups)) + if (check_for_node(node_xsdata,"multiplicity")) then + arr_len = get_arraysize_double(node_xsdata,"multiplicity") + if (arr_len == groups * groups) then + allocate(temp_arr(arr_len)) + call get_node_array(node_xsdata,"multiplicity",temp_arr) + temp_mult = reshape(temp_arr, (/groups, groups/)) + deallocate(temp_arr) + else + call fatal_error("Multiplicity length not same as number of groups& + & squared!") + end if + else + temp_mult = ONE + end if + + ! Get scattering treatment information + ! Tabular_legendre tells us if we are to treat the provided + ! Legendre polynomials as tabular data (if enable is true) or leaving + ! them as Legendres (if enable is false, or the default) + + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. + if (check_for_node(node_xsdata,"tabular_legendre")) then + call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) + if (check_for_node(node_legendre_mu, "enable")) then + call get_node_value(node_legendre_mu,"enable",temp_str) + temp_str = trim(to_lower(temp_str)) + if (temp_str == 'true' .or. temp_str == '1') then + enable_leg_mu = .true. + elseif (temp_str == 'false' .or. temp_str == '0') then + enable_leg_mu = .false. + else + call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + end if + end if + ! Ok, so if we need to convert to a tabular form, get the user provided + ! number of points + if (enable_leg_mu) then + if (check_for_node(node_legendre_mu,"num_points")) then + call get_node_value(node_legendre_mu,"num_points", & + legendre_mu_points) + if (legendre_mu_points <= 0) & + call fatal_error("num_points element must be positive& + & and non-zero!") + else + ! Set the default number of points (0.0625 spacing) + legendre_mu_points = 33 + end if + end if + end if + + ! Get the library's value for the order + if (check_for_node(node_xsdata,"order")) then + call get_node_value(node_xsdata,"order",order) + else + call fatal_error("Order Must Be Provided!") + end if + + ! Before retrieving the data, store the dimensionality of the data in + ! order_dim. For Legendre data, we usually refer to it as Pn where + ! n is the order. However Pn has n+1 sets of points (since you need to + ! the count the P0 moment). Adjust for that. Histogram and Tabular + ! formats dont need this adjustment. + if (this % scatt_type == ANGLE_LEGENDRE) then + order_dim = order + 1 + else + order_dim = order + end if + + ! The input is gathered in the more user-friendly facing format of + ! Gout x Gin x Order. We will get it in that format in input_scatt, + ! but then need to convert it to a more useful ordering for processing + ! (Order x Gout x Gin). + allocate(input_scatt(groups, groups, order_dim)) + if (check_for_node(node_xsdata,"scatter")) then + allocate(temp_arr(groups * groups * order_dim)) + call get_node_array(node_xsdata,"scatter",temp_arr) + input_scatt = reshape(temp_arr,(/groups,groups,order_dim/)) + deallocate(temp_arr) + + ! Compare the number of orders given with the maximum order of the + ! problem. Strip off the supefluous orders if needed. + if (this % scatt_type == ANGLE_LEGENDRE) then + order = min(order_dim - 1, max_order) + order_dim = order + 1 + end if + allocate(temp_scatt(groups,groups,order_dim)) + temp_scatt(:,:,:) = input_scatt(:,:,1:order_dim) + + ! Take input format (groups, groups, order) and convert to + ! the more useful format needed for scattdata: (order, groups, groups) + ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was + ! provided as Legendre coefficients), and the user requested that + ! these legendres be converted to tabular form (note this is also + ! the default behavior), convert that now. + if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then + ! Convert input parameters to what we need for the rest. + this % scatt_type = ANGLE_TABULAR + order_dim = legendre_mu_points + order = order_dim + dmu = TWO / real(order - 1,8) + + allocate(scatt_coeffs(order_dim,groups,groups)) + do gin = 1, groups + do gout = 1, groups + norm = ZERO + do imu = 1, order_dim + if (imu == 1) then + mu = -ONE + else if (imu == order_dim) then + mu = ONE + else + mu = -ONE + real(imu - 1,8) * dmu + end if + scatt_coeffs(imu,gout,gin) = & + evaluate_legendre(temp_scatt(gout,gin,:),mu) + ! Ensure positivity of distribution + if (scatt_coeffs(imu,gout,gin) < ZERO) & + scatt_coeffs(imu,gout,gin) = ZERO + ! And accrue the integral + if (imu > 1) then + norm = norm + HALF * dmu * (scatt_coeffs(imu-1,gout,gin) + & + scatt_coeffs(imu,gout,gin)) + end if + end do + ! Now that we have the integral, lets ensure that the distribution + ! is normalized such that it preserves the original scattering xs + if (norm > ZERO) then + scatt_coeffs(:,gout,gin) = scatt_coeffs(:,gout,gin) * & + temp_scatt(gout,gin,1) / norm + end if + end do + end do + else + ! Sticking with current representation, carry forward but change + ! the array ordering + allocate(scatt_coeffs(order_dim,groups,groups)) + do gin = 1, groups + do gout = 1, groups + do l = 1, order_dim + scatt_coeffs(l,gout,gin) = temp_scatt(gout,gin,l) + end do + end do + end do + end if + deallocate(temp_scatt) + else + call fatal_error("Must provide scatter!") + end if + + ! Allocate and initialize our ScattData Object. + if (this % scatt_type == ANGLE_HISTOGRAM) then + allocate(ScattDataHistogram :: this % scatter) + else if (this % scatt_type == ANGLE_TABULAR) then + allocate(ScattDataTabular :: this % scatter) + else if (this % scatt_type == ANGLE_LEGENDRE) then + allocate(ScattDataLegendre :: this % scatter) + end if + + ! Initialize the ScattData Object + call this % scatter % init(temp_mult, scatt_coeffs) + + ! Get, or infer, total xs data. + allocate(this % total(groups)) + if (check_for_node(node_xsdata,"total")) then + call get_node_array(node_xsdata,"total",this % total) + else + this % total = this % absorption + this % scatter % scattxs + end if + + ! Deallocate temporaries for the next material + deallocate(input_scatt,scatt_coeffs,temp_mult) + + end subroutine mgxsiso_init_file + + subroutine mgxsang_init_file(this,node_xsdata,groups,get_kfiss,get_fiss,max_order) + class(MgxsAngle), intent(inout) :: this ! Working Object + type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml + integer, intent(in) :: groups ! Number of Energy groups + logical, intent(in) :: get_kfiss ! Need Kappa-Fission? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order + + type(Node), pointer :: node_legendre_mu + character(MAX_LINE_LEN) :: temp_str + logical :: enable_leg_mu + real(8), allocatable :: temp_arr(:), temp_4d(:,:,:,:) + real(8), allocatable :: temp_mult(:,:,:,:) + real(8), allocatable :: scatt_coeffs(:,:,:,:,:) + real(8), allocatable :: input_scatt(:,:,:,:,:) + real(8), allocatable :: temp_scatt(:,:,:,:,:) + real(8) :: dmu, mu, norm, dangle + integer :: order, order_dim, gin, gout, l, arr_len + integer :: legendre_mu_points, imu, ipol, iazi + + ! Call generic data gathering routine (will populate the metadata) + call mgxs_init_file(this, node_xsdata) + + if (check_for_node(node_xsdata, "num_polar")) then + call get_node_value(node_xsdata, "num_polar", this % n_pol) + else + call fatal_error("num_polar Must Be Provided!") + end if + + if (check_for_node(node_xsdata, "num_azimuthal")) then + call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) + else + call fatal_error("num_azimuthal Must Be Provided!") + end if + + ! Load angle data, if present (else equally spaced) + allocate(this % polar(this % n_pol)) + allocate(this % azimuthal(this % n_azi)) + if (check_for_node(node_xsdata, "polar")) then + call fatal_error("User-Specified polar angle bins not yet supported!") + ! When this feature is supported, this line will be activated + call get_node_array(node_xsdata, "polar", this % polar) + else + dangle = PI / real(this % n_pol,8) + do ipol = 1, this % n_pol + this % polar(ipol) = (real(ipol,8) - HALF) * dangle + end do + end if + if (check_for_node(node_xsdata, "azimuthal")) then + call fatal_error("User-Specified azimuthal angle bins not yet supported!") + ! When this feature is supported, this line will be activated + call get_node_array(node_xsdata, "azimuthal", this % azimuthal) + else + dangle = TWO * PI / real(this % n_azi,8) + do iazi = 1, this % n_azi + this % azimuthal(iazi) = -PI + (real(iazi,8) - HALF) * dangle + end do + end if + + ! Load the more specific data + allocate(this % nu_fission(groups,this % n_azi,this % n_pol)) + allocate(this % chi(groups,groups,this % n_azi,this % n_pol)) + if (this % fissionable) then + if (check_for_node(node_xsdata,"chi")) then + ! Chi was provided, that means they are giving chi and nu-fission + ! vectors + ! Get chi + allocate(temp_arr(1 * groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"chi",temp_arr) + ! Initialize counter for temp_arr + l = 0 + gin = 1 + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gout = 1, groups + l = l + 1 + this % chi(gout,gin,iazi,ipol) = temp_arr(l) + end do + ! Normalize chi so its CDF goes to 1 + this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / & + sum(this % chi(:,gin,iazi,ipol)) + end do + end do + + ! Now set all the other gin values + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 2, groups + this % chi(:,gin,iazi,ipol) = this % chi(:,1,iazi,ipol) + end do + end do + end do + deallocate(temp_arr) + + ! Get nu_fission (as a vector) + if (check_for_node(node_xsdata,"nu_fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"nu_fission",temp_arr) + this % nu_fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if + + else + ! chi isnt provided but is within nu_fission, existing as a matrix + ! So, get nu_fission (as a matrix) + if (check_for_node(node_xsdata,"nu_fission")) then + allocate(temp_arr(groups * groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"nu_fission",temp_arr) + allocate(temp_4d(groups,groups,this % n_azi,this % n_pol)) + temp_4d = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("If fissionable, must provide nu_fission!") + end if + + ! Set the vector nu-fission from the matrix nu-fission + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, groups + this % nu_fission(gin,iazi,ipol) = sum(temp_4d(:,gin,iazi,ipol)) + end do + end do + end do + + ! Now pull out information needed for chi + this % chi = temp_4d + ! Normalize chi so its CDF goes to 1 + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, groups + this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / & + sum(this % chi(:,gin,iazi,ipol)) + end do + end do + end do + deallocate(temp_4d) + end if + + ! If we have a need* for the fission and kappa-fission x/s, get them + ! (*Need is defined as will be using it to tally) + if (get_fiss) then + if (check_for_node(node_xsdata,"fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"fission",temp_arr) + allocate(this % fission(groups,this % n_azi,this % n_pol)) + this % fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Fission data missing, required due to fission& + & tallies in tallies.xml file!") + end if + end if + if (get_kfiss) then + if (check_for_node(node_xsdata,"kappa_fission")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"kappa_fission",temp_arr) + allocate(this % k_fission(groups,this % n_azi,this % n_pol)) + this % k_fission = reshape(temp_arr,(/groups, this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("kappa_fission data missing, required due to & + &kappa-fission tallies in tallies.xml file!") + end if + end if + else + this % nu_fission = ZERO + this % chi = ZERO + end if + + if (check_for_node(node_xsdata,"absorption")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"absorption",temp_arr) + allocate(this % absorption(groups,this % n_azi,this % n_pol)) + this % absorption = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Must provide absorption!") + end if + + ! Get multiplication data if present + allocate(temp_mult(groups,groups,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"multiplicity")) then + arr_len = get_arraysize_double(node_xsdata,"multiplicity") + if (arr_len == groups * groups * this % n_azi * this % n_pol) then + allocate(temp_arr(arr_len)) + call get_node_array(node_xsdata,"multiplicity",temp_arr) + temp_mult = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + call fatal_error("Multiplicity length not same as number of groups& + & squared!") + end if + else + temp_mult = ONE + end if + + ! Get scattering treatment information + ! Tabular_legendre tells us if we are to treat the provided + ! Legendre polynomials as tabular data (if enable is true) or leaving + ! them as Legendres (if enable is false, or the default) + + ! Set the default (leave as Legendre polynomials) + enable_leg_mu = .false. + if (check_for_node(node_xsdata,"tabular_legendre")) then + call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) + if (check_for_node(node_legendre_mu, "enable")) then + call get_node_value(node_legendre_mu,"enable",temp_str) + temp_str = trim(to_lower(temp_str)) + if (temp_str == 'true' .or. temp_str == '1') then + enable_leg_mu = .true. + elseif (temp_str == 'false' .or. temp_str == '0') then + enable_leg_mu = .false. + else + call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + end if + end if + ! Ok, so if we need to convert to a tabular form, get the user provided + ! number of points + if (enable_leg_mu) then + if (check_for_node(node_legendre_mu,"num_points")) then + call get_node_value(node_legendre_mu,"num_points", & + legendre_mu_points) + if (legendre_mu_points <= 0) & + call fatal_error("num_points element must be positive& + & and non-zero!") + else + ! Set the default number of points (0.0625 spacing) + legendre_mu_points = 33 + end if + end if + end if + + ! Get the library's value for the order + if (check_for_node(node_xsdata,"order")) then + call get_node_value(node_xsdata,"order",order) + else + call fatal_error("Order Must Be Provided!") + end if + + ! Before retrieving the data, store the dimensionality of the data in + ! order_dim. For Legendre data, we usually refer to it as Pn where + ! n is the order. However Pn has n+1 sets of points (since you need to + ! the count the P0 moment). Adjust for that. Histogram and Tabular + ! formats dont need this adjustment. + if (this % scatt_type == ANGLE_LEGENDRE) then + order_dim = order + 1 + else + order_dim = order + end if + + ! The input is gathered in the more user-friendly facing format of + ! Gout x Gin x Order x Azi x Pol. We will get it in that format in + ! input_scatt, but then need to convert it to a more useful ordering + ! for processing (Order x Gout x Gin x Azi x Pol). + allocate(input_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"scatter")) then + allocate(temp_arr(groups * groups * order_dim * this % n_azi * & + this % n_pol)) + call get_node_array(node_xsdata,"scatter",temp_arr) + input_scatt = reshape(temp_arr,(/groups,groups,order_dim,this % n_azi, & + this % n_pol/)) + deallocate(temp_arr) + + ! Compare the number of orders given with the maximum order of the + ! problem. Strip off the supefluous orders if needed. + if (this % scatt_type == ANGLE_LEGENDRE) then + order = min(order_dim - 1, max_order) + order_dim = order + 1 + end if + + allocate(temp_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) + temp_scatt(:,:,:,:,:) = input_scatt(:,:,1:order_dim,:,:) + + ! Take input format (groups, groups, order) and convert to + ! the more useful format needed for scattdata: (order, groups, groups) + ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was + ! provided as Legendre coefficients), and the user requested that + ! these legendres be converted to tabular form (note this is also + ! the default behavior), convert that now. + if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then + + ! Convert input parameters to what we need for the rest. + this % scatt_type = ANGLE_TABULAR + order_dim = legendre_mu_points + order = order_dim + dmu = TWO / real(order - 1,8) + + allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, groups + do gout = 1, groups + norm = ZERO + do imu = 1, order_dim + if (imu == 1) then + mu = -ONE + else if (imu == order_dim) then + mu = ONE + else + mu = -ONE + real(imu - 1,8) * dmu + end if + scatt_coeffs(imu,gout,gin,iazi,ipol) = & + evaluate_legendre(temp_scatt(gout,gin,:,iazi,ipol),mu) + ! Ensure positivity of distribution + if (scatt_coeffs(imu,gout,gin,iazi,ipol) < ZERO) & + scatt_coeffs(imu,gout,gin,iazi,ipol) = ZERO + ! And accrue the integral + if (imu > 1) then + norm = norm + HALF * dmu * & + (scatt_coeffs(imu-1,gout,gin,iazi,ipol) + & + scatt_coeffs(imu,gout,gin,iazi,ipol)) + end if + end do + ! Now that we have the integral, lets ensure that the distribution + ! is normalized such that it preserves the original scattering xs + if (norm > ZERO) then + scatt_coeffs(:,gout,gin,iazi,ipol) = & + scatt_coeffs(:,gout,gin,iazi,ipol) * & + temp_scatt(gout,gin,1,iazi,ipol) / norm + end if + end do + end do + end do + end do + else + ! Sticking with current representation, carry forward but change + ! the array ordering + allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, groups + do gout = 1, groups + do l = 1, order_dim + scatt_coeffs(l,gout,gin,iazi,ipol) = & + temp_scatt(gout,gin,l,iazi,ipol) + end do + end do + end do + end do + end do + end if + deallocate(temp_scatt) + else + call fatal_error("Must provide scatter!") + end if + + allocate(this % scatter(this % n_azi, this % n_pol)) + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + ! Allocate and initialize our ScattData Object. + if (this % scatt_type == ANGLE_HISTOGRAM) then + allocate(ScattDataHistogram :: this % scatter(iazi,ipol) % obj) + else if (this % scatt_type == ANGLE_TABULAR) then + allocate(ScattDataTabular :: this % scatter(iazi,ipol) % obj) + else if (this % scatt_type == ANGLE_LEGENDRE) then + allocate(ScattDataLegendre :: this % scatter(iazi,ipol) % obj) + end if + + ! Initialize the ScattData Object + call this % scatter(iazi,ipol) % obj % init(& + temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) + end do + end do + ! Deallocate temporaries for the next material + deallocate(input_scatt,scatt_coeffs,temp_mult) + + allocate(this % total(groups,this % n_azi,this % n_pol)) + if (check_for_node(node_xsdata,"total")) then + allocate(temp_arr(groups * this % n_azi * this % n_pol)) + call get_node_array(node_xsdata,"total",temp_arr) + this % total = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + deallocate(temp_arr) + else + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + this % total(:,iazi,ipol) = this % absorption(:,iazi,ipol) + & + this % scatter(iazi,ipol) % obj % scattxs(:) + end do + end do + end if + + end subroutine mgxsang_init_file + +!=============================================================================== +! MGXS*_PRINT displays information about a continuous-energy neutron +! cross_section table and its reactions and secondary angle/energy distributions +!=============================================================================== + + subroutine mgxs_print(this, unit_) + class(Mgxs), intent(in) :: this + integer, intent(in) :: unit_ + + character(MAX_LINE_LEN) :: temp_str + + ! Basic nuclide information + write(unit_,*) 'MGXS Entry ' // trim(this % name) + if (this % zaid > 0) then + ! Dont print if data was macroscopic and thus zaid & AWR would be nonsense + write(unit_,*) ' zaid = ' // trim(to_str(this % zaid)) + write(unit_,*) ' awr = ' // trim(to_str(this % awr)) + end if + write(unit_,*) ' kT = ' // trim(to_str(this % kT)) + if (this % scatt_type == ANGLE_LEGENDRE) then + temp_str = "Legendre" + write(unit_,*) ' Scattering Type = ' // trim(temp_str) + select type(this) + type is (MgxsIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1) + end select + write(unit_,*) ' Scattering Order = ' // trim(temp_str) + else if (this % scatt_type == ANGLE_HISTOGRAM) then + temp_str = "Histogram" + write(unit_,*) ' Scattering Type = ' // trim(temp_str) + select type(this) + type is (MgxsIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) + end select + write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) + else if (this % scatt_type == ANGLE_TABULAR) then + temp_str = "Tabular" + write(unit_,*) ' Scattering Type = ' // trim(temp_str) + select type(this) + type is (MgxsIso) + temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) + end select + write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) + end if + write(unit_,*) ' Fissionable = ', this % fissionable + + end subroutine mgxs_print + + subroutine mgxsiso_print(this, unit) + + class(MgxsIso), intent(in) :: this + integer, optional, intent(in) :: unit + + integer :: unit_ ! unit to write to + integer :: size_total, size_scattmat, size_mgxs + integer :: gin + + ! set default unit for writing information + if (present(unit)) then + unit_ = unit + else + unit_ = OUTPUT_UNIT + end if + + ! Write Basic Nuclide Information + call mgxs_print(this, unit_) + + ! Determine size of mgxs and scattering matrices + size_scattmat = 0 + do gin = 1, size(this % scatter % energy) + size_scattmat = size_scattmat + & + 2 * size(this % scatter % energy(gin) % data) + & + size(this % scatter % dist(gin) % data) + end do + size_scattmat = size_scattmat + size(this % scatter % scattxs) + size_scattmat = size_scattmat * 8 + + size_mgxs = size(this % total) + size(this % absorption) + & + size(this % nu_fission) + size(this % k_fission) + & + size(this % fission) + size(this % chi) + size_mgxs = size_mgxs * 8 + + ! Calculate total memory + size_total = size_scattmat + size_mgxs + + ! Write memory used + write(unit_,*) ' Memory Requirements' + write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' + write(unit_,*) ' Scattering Matrices = ' // & + trim(to_str(size_scattmat)) // ' bytes' + write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' + + ! Blank line at end of nuclide + write(unit_,*) + + end subroutine mgxsiso_print + + subroutine mgxsang_print(this, unit) + + class(MgxsAngle), intent(in) :: this + integer, optional, intent(in) :: unit + + integer :: unit_ ! unit to write to + integer :: size_total, size_scattmat, size_mgxs + integer :: ipol, iazi, gin + + ! set default unit for writing information + if (present(unit)) then + unit_ = unit + else + unit_ = OUTPUT_UNIT + end if + + ! Write Basic Nuclide Information + call mgxs_print(this, unit_) + + write(unit_,*) ' # of Polar Angles = ' // trim(to_str(this % n_pol)) + write(unit_,*) ' # of Azimuthal Angles = ' // trim(to_str(this % n_azi)) + + ! Determine size of mgxs and scattering matrices + size_scattmat = 0 + do ipol = 1, this % n_pol + do iazi = 1, this % n_azi + do gin = 1, size(this % scatter(iazi,ipol) % obj % energy) + size_scattmat = size_scattmat + & + 2 * size(this % scatter(iazi,ipol) % obj % energy(gin) % data) + & + size(this % scatter(iazi,ipol) % obj % dist(gin) % data) + end do + size_scattmat = size_scattmat + & + size(this % scatter(iazi,ipol) % obj % scattxs) + end do + end do + size_scattmat = size_scattmat * 8 + + size_mgxs = size(this % total) + size(this % absorption) + & + size(this % nu_fission) + size(this % k_fission) + & + size(this % fission) + size(this % chi) + size_mgxs = size_mgxs * 8 + + ! Calculate total memory + size_total = size_scattmat + size_mgxs + + ! Write memory used + write(unit_,*) ' Memory Requirements' + write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' + write(unit_,*) ' Scattering Matrices = ' // & + trim(to_str(size_scattmat)) // ' bytes' + write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' + + ! Blank line at end of nuclide + write(unit_,*) + end subroutine mgxsang_print + +!=============================================================================== +! MGXS*_GET_XS returns the requested data cross section data +!=============================================================================== + + function mgxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) + class(MgxsIso), intent(in) :: this ! The MacroXS to initialize + character(*) , intent(in) :: xstype ! Type of xs requested + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Energy group + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle + real(8) :: xs ! Requested x/s + + select case(xstype) + case('total') + xs = this % total(gin) + case('absorption') + xs = this % absorption(gin) + case('fission') + if (allocated(this % fission)) then + xs = this % fission(gin) + else + xs = ZERO + end if + case('kappa_fission') + if (allocated(this % k_fission)) then + xs = this % k_fission(gin) + else + xs = ZERO + end if + case('nu_fission') + xs = this % nu_fission(gin) + case('chi') + if (present(gout)) then + xs = this % chi(gout,gin) + else + ! Not sure youd want a 1 or a 0, but here you go! + xs = sum(this % chi(:,gin)) + end if + case('scatter') + if (present(gout)) then + xs = this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data(gout) + else + xs = this % scatter % scattxs(gin) + end if + case('mult') + if (present(gout)) then + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % mult(gin) % data(gout) + end if + else + xs = dot_product(this % scatter % mult(gin) % data, & + this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data) + xs = xs / this % scatter % scattxs(gin) + end if + case('f_mu', 'f_mu/mult') + if (present(gout) .and. present(mu)) then + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % calc_f(gin, gout, mu) + if (xstype == 'f_mu/mult') then + xs = xs / this % scatter % mult(gin) % data(gout) + end if + end if + else + xs = ZERO + ! TODO (Not likely needed) + ! (asking for f_mu without asking for a group or mu would mean the + ! user of this code wants the complete 1-outgoing group distribution + ! which Im not sure what they would do with that. + end if + case default + xs = ZERO + end select + + end function mgxsiso_get_xs + + function mgxsang_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) + class(MgxsAngle), intent(in) :: this ! The MacroXS to initialize + character(*) , intent(in) :: xstype ! Type of xs requested + integer, intent(in) :: gin ! Incoming Energy group + integer, optional, intent(in) :: gout ! Outgoing Energy group + real(8), optional, intent(in) :: uvw(3) ! Requested Angle + real(8), optional, intent(in) :: mu ! Change in angle + real(8) :: xs ! Requested x/s + + integer :: iazi, ipol + + if (present(uvw)) then + call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) + select case(xstype) + case('total') + xs = this % total(gin,iazi,ipol) + case('absorption') + xs = this % absorption(gin,iazi,ipol) + case('fission') + if (allocated(this % fission)) then + xs = this % fission(gin,iazi,ipol) + else + xs = ZERO + end if + case('kappa_fission') + if (allocated(this % k_fission)) then + xs = this % k_fission(gin,iazi,ipol) + else + xs = ZERO + end if + case('nu_fission') + xs = this % nu_fission(gin,iazi,ipol) + case('chi') + if (present(gout)) then + xs = this % chi(gout,gin,iazi,ipol) + else + ! Not sure youd want a 1 or a 0, but here you go! + xs = sum(this % chi(:,gin,iazi,ipol)) + end if + case('scatter') + if (present(gout)) then + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + else + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) + end if + case('mult') + if (present(gout)) then + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if + else + xs = dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & + this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data) + xs = xs / this % scatter(iazi,ipol) % obj % scattxs(gin) + end if + case('f_mu', 'f_mu/mult') + if (present(gout) .and. present(mu)) then + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % calc_f(gin, gout, mu) + if (xstype == 'f_mu/mult') then + xs = xs / & + this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if + end if + else + xs = ZERO + ! TODO (Not likely needed) + ! (asking for f_mu without asking for a group or mu would mean the + ! user of this code wants the complete 1-outgoing group distribution + ! which Im not sure what they would do with that. + end if + case default + xs = ZERO + end select + else + xs = ZERO + end if + + end function mgxsang_get_xs + +!=============================================================================== +! MACROXS*_COMBINE Builds a macroscopic Mgxs object from microscopic Mgxs +! objects +!=============================================================================== + + subroutine mgxsiso_combine(this, mat, nuclides, groups, get_kfiss, get_fiss, & + max_order, scatt_type) + class(MgxsIso), intent(inout) :: this ! The MacroXS to initialize + type(Material), pointer, intent(in) :: mat ! base material + type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: scatt_type ! How is data presented + + integer :: i ! loop index over nuclides + integer :: gin, gout ! group indices + real(8) :: atom_density ! atom density of a nuclide + real(8) :: norm + integer :: mat_max_order, order, order_dim, nuc_order_dim + real(8), allocatable :: temp_mult(:,:) + real(8), allocatable :: scatt_coeffs(:,:,:) + + ! Determine the scattering type of our data and ensure all scattering orders + ! are the same. + select type(nuc => nuclides(mat % nuclide(1)) % obj) + type is (MgxsIso) + order = size(nuc % scatter % dist(1) % data, dim=1) + end select + ! If we have tabular only data, then make sure all datasets have same size + if (scatt_type == ANGLE_HISTOGRAM) then + ! Check all scattering data to ensure it is the same size + ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) + do i = 2, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsIso) + if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & + call fatal_error("All Histogram Scattering Entries Must Be& + & Same Length!") + end select + end do + ! Ok, got our order, store the dimensionality + order_dim = order + + ! Set our Scatter Object Type + allocate(ScattDataHistogram :: this % scatter) + + else if (scatt_type == ANGLE_TABULAR) then + ! Check all scattering data to ensure it is the same size + do i = 2, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsIso) + if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & + call fatal_error("All Tabular Scattering Entries Must Be& + & Same Length!") + end select + end do + ! Ok, got our order, store the dimensionality + order_dim = order + + ! Set our Scatter Object Type + allocate(ScattDataTabular :: this % scatter) + + else if (scatt_type == ANGLE_LEGENDRE) then + ! Need to determine the maximum scattering order of all data in this material + mat_max_order = 0 + do i = 1, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsIso) + if (size(nuc % scatter % dist(1) % data,dim=1) > mat_max_order) & + mat_max_order = size(nuc % scatter % dist(1) % data,dim=1) + end select + end do + + ! Now need to compare this material maximum scattering order with + ! the problem wide max scatt order and use whichever is lower + order = min(mat_max_order, max_order) + ! Ok, got our order, store the dimensionality + order_dim = order + 1 + + ! Set our Scatter Object Type + allocate(ScattDataLegendre :: this % scatter) + end if + + ! Allocate and initialize data needed for macro_xs(i_mat) object + allocate(this % total(groups)) + this % total = ZERO + allocate(this % absorption(groups)) + this % absorption = ZERO + if (get_fiss) then + allocate(this % fission(groups)) + this % fission = ZERO + end if + if (get_kfiss) then + allocate(this % k_fission(groups)) + this % k_fission = ZERO + end if + allocate(this % nu_fission(groups)) + this % nu_fission = ZERO + allocate(this % chi(groups,groups)) + this % chi = ZERO + allocate(temp_mult(groups,groups)) + temp_mult = ZERO + allocate(scatt_coeffs(order_dim,groups,groups)) + scatt_coeffs = ZERO + + ! Add contribution from each nuclide in material + do i = 1, mat % n_nuclides + ! Copy atom density of nuclide in material + atom_density = mat % atom_density(i) + + ! Perform our operations which depend upon the type + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsIso) + ! Add contributions to total, absorption, and fission data (if necessary) + this % total = this % total + atom_density * nuc % total + this % absorption = this % absorption + & + atom_density * nuc % absorption + if (nuc % fissionable) then + this % chi = this % chi + atom_density * nuc % chi + this % nu_fission = this % nu_fission + atom_density * & + nuc % nu_fission + if (get_fiss) then + this % fission = this % fission + atom_density * nuc % fission + end if + if (get_kfiss) then + this % k_fission = this % k_fission + atom_density * nuc % k_fission + end if + end if + + ! Get the multiplication matrix + do gin = 1, groups + do gout = nuc % scatter % gmin(gin), nuc % scatter % gmax(gin) + temp_mult(gout,gin) = temp_mult(gout,gin) + atom_density * & + nuc % scatter % mult(gin) % data(gout) + end do + end do + + ! Get the complete scattering matrix + nuc_order_dim = size(nuc % scatter % dist(1) % data,dim=1) + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) + & + atom_density * & + nuc % scatter % get_matrix(min(nuc_order_dim,order_dim)) + + type is (MgxsAngle) + call fatal_error("Invalid Passing of MgxsAngle to MacroXSIso Object") + end select + end do + + ! Initialize the ScattData Object + call this % scatter % init(temp_mult,scatt_coeffs) + + ! Now normalize chi + if (mat % fissionable) then + do gin = 1, groups + norm = sum(this % chi(:,gin)) + if (norm > ZERO) then + this % chi(:,gin) = this % chi(:,gin) / norm + end if + end do + end if + + ! Deallocate temporaries + deallocate(scatt_coeffs, temp_mult) + + end subroutine mgxsiso_combine + + subroutine mgxsang_combine(this, mat, nuclides, groups, get_kfiss, get_fiss, & + max_order, scatt_type) + class(MgxsAngle), intent(inout) :: this ! The MacroXS to initialize + type(Material), pointer, intent(in) :: mat ! base material + type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? + + integer :: i ! loop index over nuclides + integer :: gin, gout ! group indices + real(8) :: atom_density ! atom density of a nuclide + integer :: ipol, iazi, n_pol, n_azi + real(8) :: norm + integer :: mat_max_order, order, order_dim, nuc_order_dim + real(8), allocatable :: temp_mult(:,:,:,:) + real(8), allocatable :: scatt_coeffs(:,:,:,:,:) + + ! Get the number of each polar and azi angles and make sure all the + ! NuclideAngle types have the same number of these angles + n_pol = -1 + n_azi = -1 + do i = 1, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsAngle) + if (n_pol == -1) then + n_pol = nuc % n_pol + n_azi = nuc % n_azi + allocate(this % polar(n_pol)) + this % polar = nuc % polar + allocate(this % azimuthal(n_azi)) + this % azimuthal = nuc % azimuthal + else + if ((n_pol /= nuc % n_pol) .or. (n_azi /= nuc % n_azi)) then + call fatal_error("All Angular Data Must Be Same Length!") + end if + end if + end select + end do + + ! Determine the scattering type of our data and ensure all scattering orders + ! are the same. + select type(nuc => nuclides(mat % nuclide(1)) % obj) + type is (MgxsAngle) + order = size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1) + end select + ! If we have tabular only data, then make sure all datasets have same size + if (scatt_type == ANGLE_HISTOGRAM) then + ! Check all scattering data to ensure it is the same size + ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) + do i = 2, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsAngle) + if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + call fatal_error("All Histogram Scattering Entries Must Be& + & Same Length!") + end select + end do + ! Ok, got our order, store the dimensionality + order_dim = order + + ! Set our Scatter Object Type + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi + allocate(ScattDataHistogram :: this % scatter(iazi, ipol) % obj) + end do + end do + + else if (scatt_type == ANGLE_TABULAR) then + ! Check all scattering data to ensure it is the same size + do i = 2, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsAngle) + if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + call fatal_error("All Tabular Scattering Entries Must Be& + & Same Length!") + end select + end do + ! Ok, got our order, store the dimensionality + order_dim = order + + ! Set our Scatter Object Type + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi + allocate(ScattDataTabular :: this % scatter(iazi, ipol) % obj) + end do + end do + + else if (scatt_type == ANGLE_LEGENDRE) then + ! Need to determine the maximum scattering order of all data in this material + mat_max_order = 0 + do i = 1, mat % n_nuclides + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsAngle) + if (size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) > mat_max_order) & + mat_max_order = size(nuc % scatter(1,1) % obj% dist(1) % data,dim=1) + end select + end do + + ! Now need to compare this material maximum scattering order with + ! the problem wide max scatt order and use whichever is lower + order = min(mat_max_order, max_order) + ! Ok, got our order, store the dimensionality + order_dim = order + 1 + + ! Set our Scatter Object Type + allocate(this % scatter(n_azi, n_pol)) + do ipol = 1, n_pol + do iazi = 1, n_azi + allocate(ScattDataLegendre :: this % scatter(iazi, ipol) % obj) + end do + end do + end if + + ! Allocate and initialize data within macro_xs(i_mat) object + allocate(this % total(groups,n_azi,n_pol)) + this % total = ZERO + allocate(this % absorption(groups,n_azi,n_pol)) + this % absorption = ZERO + if (get_fiss) then + allocate(this % fission(groups,n_azi,n_pol)) + this % fission = ZERO + end if + if (get_kfiss) then + allocate(this % k_fission(groups,n_azi,n_pol)) + this % k_fission = ZERO + end if + allocate(this % nu_fission(groups,n_azi,n_pol)) + this % nu_fission = ZERO + allocate(this % chi(groups,groups,n_azi,n_pol)) + this % chi = ZERO + allocate(temp_mult(groups,groups,n_azi,n_pol)) + temp_mult = ZERO + allocate(scatt_coeffs(order_dim,groups,groups,n_azi,n_pol)) + scatt_coeffs = ZERO + + ! Add contribution from each nuclide in material + do i = 1, mat % n_nuclides + ! Copy atom density of nuclide in material + atom_density = mat % atom_density(i) + + ! Perform our operations which depend upon the type + select type(nuc => nuclides(mat % nuclide(i)) % obj) + type is (MgxsIso) + call fatal_error("Invalid Passing of MgxsIso to MacroXSAngle Object") + type is (MgxsAngle) + ! Add contributions to total, absorption, and fission data (if necessary) + this % total = this % total + atom_density * nuc % total + this % absorption = this % absorption + & + atom_density * nuc % absorption + if (nuc % fissionable) then + this % chi = this % chi + atom_density * nuc % chi + this % nu_fission = this % nu_fission + atom_density * & + nuc % nu_fission + if (get_fiss) then + this % fission = this % fission + atom_density * nuc % fission + end if + if (get_kfiss) then + this % k_fission = this % k_fission + atom_density * nuc % k_fission + end if + end if + + ! Get the multiplication matrix + do ipol = 1, n_pol + do iazi = 1, n_azi + do gin = 1, groups + do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & + nuc % scatter(iazi,ipol) % obj % gmax(gin) + temp_mult(gout,gin,iazi,ipol) = temp_mult(gout,gin,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end do + end do + end do + end do + + ! Get the complete scattering matrix + nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) + do ipol = 1, n_pol + do iazi = 1, n_azi + scatt_coeffs(1:min(nuc_order_dim,order_dim),:,:,iazi,ipol) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) + & + atom_density * & + nuc % scatter(iazi,ipol) % obj % get_matrix(& + min(nuc_order_dim,order_dim)) + end do + end do + end select + end do + + ! Initialize the ScattData Object + do ipol = 1, n_pol + do iazi = 1, n_azi + call this % scatter(iazi,ipol) % obj % init( & + temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) + end do + end do + + ! Now normalize chi + if (mat % fissionable) then + do ipol = 1, n_pol + do iazi = 1, n_azi + do gin = 1, groups + norm = sum(this % chi(:,gin,iazi,ipol)) + if (norm > ZERO) then + this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / norm + end if + end do + end do + end do + end if + + ! Deallocate temporaries for the next material + deallocate(scatt_coeffs, temp_mult) + + end subroutine mgxsang_combine + +!=============================================================================== +! MGXS*_SAMPLE_FISSION_ENERGY samples the outgoing energy from a fission event +!=============================================================================== + + function mgxsiso_sample_fission_energy(this, gin, uvw) result(gout) + class(MgxsIso), intent(in) :: this ! Data to work with + integer, intent(in) :: gin ! Incoming energy group + real(8), intent(in) :: uvw(3) ! Particle Direction + integer :: gout ! Sampled outgoing group + real(8) :: xi ! Our random number + real(8) :: prob ! Running probability + + xi = prn() + gout = 1 + prob = this % chi(gout,gin) + + do while (prob < xi) + gout = gout + 1 + prob = prob + this % chi(gout,gin) + end do + + end function mgxsiso_sample_fission_energy + + function mgxsang_sample_fission_energy(this, gin, uvw) result(gout) + class(MgxsAngle), intent(in) :: this ! Data to work with + integer, intent(in) :: gin ! Incoming energy group + real(8), intent(in) :: uvw(3) ! Particle Direction + integer :: gout ! Sampled outgoing group + real(8) :: xi ! Our random number + real(8) :: prob ! Running probability + integer :: iazi, ipol + + call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) + + xi = prn() + gout = 1 + prob = this % chi(gout,gin,iazi,ipol) + + do while (prob < xi) + gout = gout + 1 + prob = prob + this % chi(gout,gin,iazi,ipol) + end do + + end function mgxsang_sample_fission_energy + +!=============================================================================== +! MGXS*_SAMPLE_SCATTER Selects outgoing energy and angle after a scatter event +!=============================================================================== + + subroutine mgxsiso_sample_scatter(this, uvw, gin, gout, mu, wgt) + class(MgxsIso), intent(in) :: this + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + integer, intent(in) :: gin ! Incoming neutron group + integer, intent(out) :: gout ! Sampled outgoin group + real(8), intent(out) :: mu ! Sampled change in angle + real(8), intent(inout) :: wgt ! Particle weight + + call this % scatter % sample(gin, gout, mu, wgt) + + end subroutine mgxsiso_sample_scatter + + subroutine mgxsang_sample_scatter(this, uvw, gin, gout, mu, wgt) + class(MgxsAngle), intent(in) :: this + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + integer, intent(in) :: gin ! Incoming neutron group + integer, intent(out) :: gout ! Sampled outgoin group + real(8), intent(out) :: mu ! Sampled change in angle + real(8), intent(inout) :: wgt ! Particle weight + + integer :: iazi, ipol ! Angular indices + + call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) + call this % scatter(iazi,ipol) % obj % sample(gin,gout,mu,wgt) + + end subroutine mgxsang_sample_scatter + +!=============================================================================== +! MGXS*_CALCULATE_XS determines the multi-group cross sections +! for the material the particle is currently traveling through. +!=============================================================================== + + subroutine mgxsiso_calculate_xs(this, gin, uvw, xs) + class(MgxsIso), intent(in) :: this + integer, intent(in) :: gin ! Incoming neutron group + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data + + xs % total = this % total(gin) + xs % elastic = this % scatter % scattxs(gin) + xs % absorption = this % absorption(gin) + xs % nu_fission = this % nu_fission(gin) + + end subroutine mgxsiso_calculate_xs + + subroutine mgxsang_calculate_xs(this, gin, uvw, xs) + class(MgxsAngle), intent(in) :: this + integer, intent(in) :: gin ! Incoming neutron group + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data + + integer :: iazi, ipol + + call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) + xs % total = this % total(gin,iazi,ipol) + xs % elastic = this % scatter(iazi,ipol) % obj % scattxs(gin) + xs % absorption = this % absorption(gin,iazi,ipol) + xs % nu_fission = this % nu_fission(gin,iazi,ipol) + + end subroutine mgxsang_calculate_xs + +!!!TODO: +! Move find_angle from math to here after we fully implement this and are ready +! to delete macroxs_header and relevant portions from nuclide_header. end module mgxs_header \ No newline at end of file From 03bca3db4bbd973b513e55e82a491a5b58ad13e0 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 13 Mar 2016 12:54:48 -0400 Subject: [PATCH 018/147] Removed NuclideMG and MacroXS data types and completely replaced with the new Mgxs types. Also cleaned up some output related to the new type --- src/ace.F90 | 18 +- src/cross_section.F90 | 6 +- src/energy_grid.F90 | 6 +- src/fission.F90 | 10 +- src/global.F90 | 8 +- src/macroxs_header.F90 | 768 ---------------------------- src/mgxs_data.F90 | 27 +- src/mgxs_header.F90 | 203 +++++--- src/nuclide_header.F90 | 1099 +--------------------------------------- src/output.F90 | 13 +- src/physics.F90 | 18 +- src/physics_mg.F90 | 4 +- src/tracking.F90 | 1 - 13 files changed, 199 insertions(+), 1982 deletions(-) delete mode 100644 src/macroxs_header.F90 diff --git a/src/ace.F90 b/src/ace.F90 index fbc1b7ee7..8652e8ce8 100644 --- a/src/ace.F90 +++ b/src/ace.F90 @@ -54,7 +54,7 @@ contains character(12) :: name ! name of isotope, e.g. 92235.03c character(12) :: alias ! alias of nuclide, e.g. U-235.03c type(Material), pointer :: mat - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc type(SAlphaBeta), pointer :: sab type(SetChar) :: already_read @@ -265,7 +265,7 @@ contains character(10) :: mat ! material identifier character(70) :: comment ! comment for ACE table character(MAX_FILE_LEN) :: filename ! path to ACE cross section library - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc type(SAlphaBeta), pointer :: sab type(XsListing), pointer :: listing @@ -422,7 +422,7 @@ contains !=============================================================================== subroutine read_esz(nuc, data_0K) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc logical, intent(in) :: data_0K ! are we reading 0K data? integer :: NE ! number of energy points for total and elastic cross sections @@ -510,7 +510,7 @@ contains !=============================================================================== subroutine read_nu_data(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: i ! loop index integer :: JXS2 ! location for fission nu data @@ -714,7 +714,7 @@ contains !=============================================================================== subroutine read_reactions(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: i ! loop indices integer :: i_fission ! index in nuc % index_fission @@ -894,7 +894,7 @@ contains !=============================================================================== subroutine read_angular_dist(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: LOCB ! location of angular distribution for given MT integer :: NE ! number of incoming energies @@ -998,7 +998,7 @@ contains !=============================================================================== subroutine read_energy_dist(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: i ! loop index integer :: n @@ -1386,7 +1386,7 @@ contains !=============================================================================== subroutine read_unr_res(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: JXS23 ! location of URR data integer :: lc ! locator @@ -1474,7 +1474,7 @@ contains !=============================================================================== subroutine generate_nu_fission(nuc) - type(NuclideCE), intent(inout) :: nuc + type(Nuclide), intent(inout) :: nuc integer :: i ! index on nuclide energy grid real(8) :: E ! energy diff --git a/src/cross_section.F90 b/src/cross_section.F90 index 2f2e7fd7e..e29215f08 100644 --- a/src/cross_section.F90 +++ b/src/cross_section.F90 @@ -148,7 +148,7 @@ contains integer :: i_low ! lower logarithmic mapping index integer :: i_high ! upper logarithmic mapping index real(8) :: f ! interp factor on nuclide energy grid - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc type(Material), pointer :: mat ! Set pointer to nuclide and material @@ -364,7 +364,7 @@ contains real(8) :: fission ! fission cross section real(8) :: inelastic ! inelastic cross section type(UrrData), pointer :: urr - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc micro_xs(i_nuclide) % use_ptable = .true. @@ -520,7 +520,7 @@ contains pure function elastic_xs_0K(E, nuc) result(xs_out) real(8), intent(in) :: E ! trial energy - type(NuclideCE), intent(in) :: nuc ! target nuclide at temperature + type(Nuclide), intent(in) :: nuc ! target nuclide at temperature real(8) :: xs_out ! 0K xs at trial energy integer :: i_grid ! index on nuclide energy grid diff --git a/src/energy_grid.F90 b/src/energy_grid.F90 index 248462f70..66419f83c 100644 --- a/src/energy_grid.F90 +++ b/src/energy_grid.F90 @@ -27,7 +27,7 @@ contains integer :: i ! index in nuclides array integer :: j ! index in materials array type(ListReal) :: list - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc type(Material), pointer :: mat call write_message("Creating unionized energy grid...", 5) @@ -70,7 +70,7 @@ contains real(8) :: E_max ! Maximum energy in MeV real(8) :: E_min ! Minimum energy in MeV real(8), allocatable :: umesh(:) ! Equally log-spaced energy grid - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc ! Set minimum/maximum energies E_max = energy_max_neutron @@ -179,7 +179,7 @@ contains integer :: index_e ! index on union energy grid real(8) :: union_energy ! energy on union grid real(8) :: energy ! energy on nuclide grid - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc type(Material), pointer :: mat do k = 1, n_materials diff --git a/src/fission.F90 b/src/fission.F90 index 77ee64178..3a0b9348f 100644 --- a/src/fission.F90 +++ b/src/fission.F90 @@ -1,6 +1,6 @@ module fission - use nuclide_header, only: NuclideCE + use nuclide_header, only: Nuclide use constants use error, only: fatal_error use interpolation, only: interpolate_tab1 @@ -16,7 +16,7 @@ contains !=============================================================================== pure function nu_total(nuc, E) result(nu) - type(NuclideCE), intent(in) :: nuc ! nuclide from which to find nu + type(Nuclide), intent(in) :: nuc ! nuclide from which to find nu real(8), intent(in) :: E ! energy of incoming neutron real(8) :: nu ! number of total neutrons emitted per fission @@ -49,7 +49,7 @@ contains !=============================================================================== pure function nu_prompt(nuc, E) result(nu) - type(NuclideCE), intent(in) :: nuc ! nuclide from which to find nu + type(Nuclide), intent(in) :: nuc ! nuclide from which to find nu real(8), intent(in) :: E ! energy of incoming neutron real(8) :: nu ! number of prompt neutrons emitted per fission @@ -86,7 +86,7 @@ contains !=============================================================================== pure function nu_delayed(nuc, E) result(nu) - type(NuclideCE), intent(in) :: nuc ! nuclide from which to find nu + type(Nuclide), intent(in) :: nuc ! nuclide from which to find nu real(8), intent(in) :: E ! energy of incoming neutron real(8) :: nu ! number of delayed neutrons emitted per fission @@ -109,7 +109,7 @@ contains !=============================================================================== pure function yield_delayed(nuc, E, g) result(yield) - type(NuclideCE), intent(in) :: nuc ! nuclide from which to find nu + type(Nuclide), intent(in) :: nuc ! nuclide from which to find nu real(8), intent(in) :: E ! energy of incoming neutron real(8) :: yield ! delayed neutron precursor yield integer, intent(in) :: g ! the delayed neutron precursor group diff --git a/src/global.F90 b/src/global.F90 index 6befa828f..bb7bf50ef 100644 --- a/src/global.F90 +++ b/src/global.F90 @@ -5,9 +5,9 @@ module global use constants use dict_header, only: DictCharInt, DictIntInt use geometry_header, only: Cell, Universe, Lattice, LatticeContainer - use macroxs_header, only: MacroXSContainer use material_header, only: Material use mesh_header, only: RegularMesh + use mgxs_header, only: Mgxs, MgxsContainer use nuclide_header use plot_header, only: ObjectPlot use sab_header, only: SAlphaBeta @@ -86,7 +86,7 @@ module global ! CONTINUOUS-ENERGY CROSS SECTION RELATED VARIABLES ! Cross section arrays - type(NuclideCE), allocatable, target :: nuclides(:) ! Nuclide cross-sections + type(Nuclide), allocatable, target :: nuclides(:) ! Nuclide cross-sections type(SAlphaBeta), allocatable, target :: sab_tables(:) ! S(a,b) tables integer :: n_sab_tables ! Number of S(a,b) thermal scattering tables @@ -112,10 +112,10 @@ module global ! MULTI-GROUP CROSS SECTION RELATED VARIABLES ! Cross section arrays - type(NuclideMGContainer), allocatable, target :: nuclides_MG(:) + type(MgxsContainer), allocatable, target :: nuclides_MG(:) ! Cross section caches - type(MacroXSContainer), target, allocatable :: macro_xs(:) + type(MgxsContainer), target, allocatable :: macro_xs(:) ! Number of energy groups integer :: energy_groups diff --git a/src/macroxs_header.F90 b/src/macroxs_header.F90 deleted file mode 100644 index ff04d8a4e..000000000 --- a/src/macroxs_header.F90 +++ /dev/null @@ -1,768 +0,0 @@ -module macroxs_header - - use constants, only: MAX_FILE_LEN, ZERO, ONE, TWO, PI - use error, only: fatal_error - use list_header, only: ListInt - use material_header, only: material - use math, only: calc_pn, calc_rn, expand_harmonic, find_angle - use nuclide_header - use random_lcg, only: prn - use scattdata_header - - implicit none - -!=============================================================================== -! MACROXS_* contains cached macroscopic cross sections for the material a -! particle is traveling through -!=============================================================================== - - type, abstract :: MacroXS - contains - procedure(macroxs_init_), deferred :: init ! initializes object - procedure(macroxs_get_xs_), deferred :: get_xs ! Return xs - ! Sample the outgoing energy from a fission event - procedure(macroxs_sample_fission_), deferred :: sample_fission_energy - ! Sample the outgoing energy and angle from a scatter event - procedure(macroxs_sample_scatter_), deferred :: sample_scatter - ! Calculate the material specific MGXS data from the nuclides - procedure(macroxs_calculate_xs_), deferred :: calculate_xs - end type MacroXS - - abstract interface - subroutine macroxs_init_(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - import MacroXS, Material, NuclideMGContainer, MAX_LINE_LEN - class(MacroXS), intent(inout) :: this ! The MacroXS to initialize - type(Material), pointer, intent(in) :: mat ! base material - type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order - integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? - end subroutine macroxs_init_ - - function macroxs_get_xs_(this, xstype, gin, gout, uvw, mu) result(xs) - import MacroXS - class(MacroXS), intent(in) :: this ! The MacroXS to initialize - character(*) , intent(in) :: xstype ! Cross Section Type - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Energy group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - real(8) :: xs ! Resultant xs - end function macroxs_get_xs_ - - function macroxs_sample_fission_(this, gin, uvw) result(gout) - import MacroXS - class(MacroXS), intent(in) :: this ! Data to work with - integer, intent(in) :: gin ! Incoming energy group - real(8), intent(in) :: uvw(3) ! Particle Direction - integer :: gout ! Sampled outgoing group - - end function macroxs_sample_fission_ - - subroutine macroxs_sample_scatter_(this, uvw, gin, gout, mu, wgt) - import MacroXS - class(MacroXS), intent(in) :: this - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - integer, intent(in) :: gin ! Incoming neutron group - integer, intent(out) :: gout ! Sampled outgoin group - real(8), intent(out) :: mu ! Sampled change in angle - real(8), intent(inout) :: wgt ! Particle weight - end subroutine macroxs_sample_scatter_ - - subroutine macroxs_calculate_xs_(this, gin, uvw, xs) - import MacroXS, MaterialMacroXS - class(MacroXS), intent(in) :: this - integer, intent(in) :: gin ! Incoming neutron group - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs - end subroutine macroxs_calculate_xs_ - end interface - - type, extends(MacroXS) :: MacroXSIso - ! Microscopic cross sections - real(8), allocatable :: total(:) ! total cross section - real(8), allocatable :: absorption(:) ! absorption cross section - class(ScattData), allocatable :: scatter ! scattering information - real(8), allocatable :: nu_fission(:) ! nu-fission - real(8), allocatable :: k_fission(:) ! kappa-fission - real(8), allocatable :: fission(:) ! fission x/s - real(8), allocatable :: chi(:,:) ! fission spectra - - contains - procedure :: init => macroxsiso_init ! inits object - procedure :: get_xs => macroxsiso_get_xs ! Returns xs - procedure :: sample_fission_energy => macroxsiso_sample_fission_energy - procedure :: sample_scatter => macroxsiso_sample_scatter - procedure :: calculate_xs => macroxsiso_calculate_xs - end type MacroXSIso - - type, extends(MacroXS) :: MacroXSAngle - ! Macroscopic cross sections - real(8), allocatable :: total(:,:,:) ! total cross section - real(8), allocatable :: absorption(:,:,:) ! absorption cross section - type(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information - real(8), allocatable :: nu_fission(:,:,:) ! nu-fission - real(8), allocatable :: k_fission(:,:,:) ! kappa-fission - real(8), allocatable :: fission(:,:,:) ! fission x/s - real(8), allocatable :: chi(:,:,:,:) ! fission spectra - real(8), allocatable :: polar(:) ! polar angles - real(8), allocatable :: azimuthal(:) ! azimuthal angles - - contains - procedure :: init => macroxsangle_init ! inits object - procedure :: get_xs => macroxsangle_get_xs ! Returns xs - procedure :: sample_fission_energy => macroxsangle_sample_fission_energy - procedure :: sample_scatter => macroxsangle_sample_scatter - procedure :: calculate_xs => macroxsangle_calculate_xs - end type MacroXSAngle - -!=============================================================================== -! MACROXSCONTAINER pointer array for storing MacroXS objects. -!=============================================================================== - - type MacroXSContainer - class(MacroXS), allocatable :: obj - end type MacroXSContainer - -contains - -!=============================================================================== -! MACROXS*_INIT sets the MacroXS Data -!=============================================================================== - - subroutine macroxsiso_init(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - class(MacroXSIso), intent(inout) :: this ! The MacroXS to initialize - type(Material), pointer, intent(in) :: mat ! base material - type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order - integer, intent(in) :: scatt_type ! How is data presented - - integer :: i ! loop index over nuclides - integer :: gin, gout ! group indices - real(8) :: atom_density ! atom density of a nuclide - real(8) :: norm - integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:) - real(8), allocatable :: scatt_coeffs(:,:,:) - - ! Determine the scattering type of our data and ensure all scattering orders - ! are the same. - select type(nuc => nuclides(mat % nuclide(1)) % obj) - type is (NuclideIso) - order = size(nuc % scatter % dist(1) % data, dim=1) - end select - ! If we have tabular only data, then make sure all datasets have same size - if (scatt_type == ANGLE_HISTOGRAM) then - ! Check all scattering data to ensure it is the same size - ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) - do i = 2, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideIso) - if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & - call fatal_error("All Histogram Scattering Entries Must Be& - & Same Length!") - end select - end do - ! Ok, got our order, store the dimensionality - order_dim = order - - ! Set our Scatter Object Type - allocate(ScattDataHistogram :: this % scatter) - - else if (scatt_type == ANGLE_TABULAR) then - ! Check all scattering data to ensure it is the same size - do i = 2, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideIso) - if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & - call fatal_error("All Tabular Scattering Entries Must Be& - & Same Length!") - end select - end do - ! Ok, got our order, store the dimensionality - order_dim = order - - ! Set our Scatter Object Type - allocate(ScattDataTabular :: this % scatter) - - else if (scatt_type == ANGLE_LEGENDRE) then - ! Need to determine the maximum scattering order of all data in this material - mat_max_order = 0 - do i = 1, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideIso) - if (size(nuc % scatter % dist(1) % data,dim=1) > mat_max_order) & - mat_max_order = size(nuc % scatter % dist(1) % data,dim=1) - end select - end do - - ! Now need to compare this material maximum scattering order with - ! the problem wide max scatt order and use whichever is lower - order = min(mat_max_order, max_order) - ! Ok, got our order, store the dimensionality - order_dim = order + 1 - - ! Set our Scatter Object Type - allocate(ScattDataLegendre :: this % scatter) - end if - - ! Allocate and initialize data needed for macro_xs(i_mat) object - allocate(this % total(groups)) - this % total = ZERO - allocate(this % absorption(groups)) - this % absorption = ZERO - if (get_fiss) then - allocate(this % fission(groups)) - this % fission = ZERO - end if - if (get_kfiss) then - allocate(this % k_fission(groups)) - this % k_fission = ZERO - end if - allocate(this % nu_fission(groups)) - this % nu_fission = ZERO - allocate(this % chi(groups,groups)) - this % chi = ZERO - allocate(temp_mult(groups,groups)) - temp_mult = ZERO - allocate(scatt_coeffs(order_dim,groups,groups)) - scatt_coeffs = ZERO - - ! Add contribution from each nuclide in material - do i = 1, mat % n_nuclides - ! Copy atom density of nuclide in material - atom_density = mat % atom_density(i) - - ! Perform our operations which depend upon the type - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideIso) - ! Add contributions to total, absorption, and fission data (if necessary) - this % total = this % total + atom_density * nuc % total - this % absorption = this % absorption + & - atom_density * nuc % absorption - if (nuc % fissionable) then - if (allocated(nuc % chi)) then - do gin = 1, groups - do gout = 1, groups - this % chi(gout,gin) = this % chi(gout,gin) + atom_density * & - nuc % chi(gout) * nuc % nu_fission(1,gin) - end do - end do - this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission(1,:) - else - this % chi = this % chi + atom_density * nuc % nu_fission - do gin = 1, groups - this % nu_fission(gin) = this % nu_fission(gin) + atom_density * & - sum(nuc % nu_fission(:,gin)) - end do - end if - if (get_fiss) then - this % fission = this % fission + atom_density * nuc % fission - end if - if (get_kfiss) then - this % k_fission = this % k_fission + atom_density * nuc % k_fission - end if - end if - - ! Get the multiplication matrix - do gin = 1, groups - do gout = nuc % scatter % gmin(gin), nuc % scatter % gmax(gin) - temp_mult(gout,gin) = temp_mult(gout,gin) + atom_density * & - nuc % scatter % mult(gin) % data(gout) - end do - end do - - ! Get the complete scattering matrix - nuc_order_dim = size(nuc % scatter % dist(1) % data,dim=1) - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) = & - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) + & - atom_density * & - nuc % scatter % get_matrix(min(nuc_order_dim,order_dim)) - - type is (NuclideAngle) - call fatal_error("Invalid Passing of NuclideAngle to MacroXSIso Object") - end select - end do - - ! Initialize the ScattData Object - call this % scatter % init(temp_mult,scatt_coeffs) - - ! Now normalize chi - if (mat % fissionable) then - do gin = 1, groups - norm = sum(this % chi(:,gin)) - if (norm > ZERO) then - this % chi(:,gin) = this % chi(:,gin) / norm - end if - end do - end if - - ! Deallocate temporaries - deallocate(scatt_coeffs, temp_mult) - - end subroutine macroxsiso_init - - subroutine macroxsangle_init(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - class(MacroXSAngle), intent(inout) :: this ! The MacroXS to initialize - type(Material), pointer, intent(in) :: mat ! base material - type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order - integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? - - integer :: i ! loop index over nuclides - integer :: gin, gout ! group indices - real(8) :: atom_density ! atom density of a nuclide - integer :: ipol, iazi, n_pol, n_azi - real(8) :: norm - integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:,:,:) - real(8), allocatable :: scatt_coeffs(:,:,:,:,:) - - ! Get the number of each polar and azi angles and make sure all the - ! NuclideAngle types have the same number of these angles - n_pol = -1 - n_azi = -1 - do i = 1, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideAngle) - if (n_pol == -1) then - n_pol = nuc % n_pol - n_azi = nuc % n_azi - allocate(this % polar(n_pol)) - this % polar = nuc % polar - allocate(this % azimuthal(n_azi)) - this % azimuthal = nuc % azimuthal - else - if ((n_pol /= nuc % n_pol) .or. (n_azi /= nuc % n_azi)) then - call fatal_error("All Angular Data Must Be Same Length!") - end if - end if - end select - end do - - ! Determine the scattering type of our data and ensure all scattering orders - ! are the same. - select type(nuc => nuclides(mat % nuclide(1)) % obj) - type is (NuclideAngle) - order = size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1) - end select - ! If we have tabular only data, then make sure all datasets have same size - if (scatt_type == ANGLE_HISTOGRAM) then - ! Check all scattering data to ensure it is the same size - ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) - do i = 2, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideAngle) - if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & - call fatal_error("All Histogram Scattering Entries Must Be& - & Same Length!") - end select - end do - ! Ok, got our order, store the dimensionality - order_dim = order - - ! Set our Scatter Object Type - allocate(this % scatter(n_azi, n_pol)) - do ipol = 1, n_pol - do iazi = 1, n_azi - allocate(ScattDataHistogram :: this % scatter(iazi, ipol) % obj) - end do - end do - - else if (scatt_type == ANGLE_TABULAR) then - ! Check all scattering data to ensure it is the same size - do i = 2, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideAngle) - if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & - call fatal_error("All Tabular Scattering Entries Must Be& - & Same Length!") - end select - end do - ! Ok, got our order, store the dimensionality - order_dim = order - - ! Set our Scatter Object Type - allocate(this % scatter(n_azi, n_pol)) - do ipol = 1, n_pol - do iazi = 1, n_azi - allocate(ScattDataTabular :: this % scatter(iazi, ipol) % obj) - end do - end do - - else if (scatt_type == ANGLE_LEGENDRE) then - ! Need to determine the maximum scattering order of all data in this material - mat_max_order = 0 - do i = 1, mat % n_nuclides - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideAngle) - if (size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) > mat_max_order) & - mat_max_order = size(nuc % scatter(1,1) % obj% dist(1) % data,dim=1) - end select - end do - - ! Now need to compare this material maximum scattering order with - ! the problem wide max scatt order and use whichever is lower - order = min(mat_max_order, max_order) - ! Ok, got our order, store the dimensionality - order_dim = order + 1 - - ! Set our Scatter Object Type - allocate(this % scatter(n_azi, n_pol)) - do ipol = 1, n_pol - do iazi = 1, n_azi - allocate(ScattDataLegendre :: this % scatter(iazi, ipol) % obj) - end do - end do - end if - - ! Allocate and initialize data within macro_xs(i_mat) object - allocate(this % total(groups,n_azi,n_pol)) - this % total = ZERO - allocate(this % absorption(groups,n_azi,n_pol)) - this % absorption = ZERO - if (get_fiss) then - allocate(this % fission(groups,n_azi,n_pol)) - this % fission = ZERO - end if - if (get_kfiss) then - allocate(this % k_fission(groups,n_azi,n_pol)) - this % k_fission = ZERO - end if - allocate(this % nu_fission(groups,n_azi,n_pol)) - this % nu_fission = ZERO - allocate(this % chi(groups, groups,n_azi,n_pol)) - this % chi = ZERO - allocate(temp_mult(groups,groups,n_azi,n_pol)) - temp_mult = ZERO - allocate(scatt_coeffs(order_dim,groups,groups,n_azi,n_pol)) - scatt_coeffs = ZERO - - ! Add contribution from each nuclide in material - do i = 1, mat % n_nuclides - ! Copy atom density of nuclide in material - atom_density = mat % atom_density(i) - - ! Perform our operations which depend upon the type - select type(nuc => nuclides(mat % nuclide(i)) % obj) - type is (NuclideIso) - call fatal_error("Invalid Passing of NuclideIso to MacroXSAngle Object") - type is (NuclideAngle) - ! Add contributions to total, absorption, and fission data (if necessary) - this % total = this % total + atom_density * nuc % total - this % absorption = this % absorption + & - atom_density * nuc % absorption - if (nuc % fissionable) then - if (allocated(nuc % chi)) then - do gin = 1, groups - do gout = 1, groups - this % chi(gout,gin,:,:) = this % chi(gout,gin,:,:) + atom_density * & - nuc % chi(gout,:,:) * nuc % nu_fission(1,gin,:,:) - end do - end do - this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission(1,:,:,:) - else - this % chi = this % chi + atom_density * nuc % nu_fission - do gin = 1, groups - this % nu_fission(gin,:,:) = this % nu_fission(gin,:,:) + atom_density * & - sum(nuc % nu_fission(:,gin,:,:),dim=1) - end do - end if - if (get_fiss) then - this % fission = this % fission + atom_density * nuc % fission - end if - if (get_kfiss) then - this % k_fission = this % k_fission + atom_density * nuc % k_fission - end if - end if - - ! Get the multiplication matrix - do ipol = 1, n_pol - do iazi = 1, n_azi - do gin = 1, groups - do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & - nuc % scatter(iazi,ipol) % obj % gmax(gin) - temp_mult(gout,gin,iazi,ipol) = temp_mult(gout,gin,iazi,ipol) + & - atom_density * & - nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - end do - end do - end do - end do - - ! Get the complete scattering matrix - nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) - do ipol = 1, n_pol - do iazi = 1, n_azi - scatt_coeffs(1:min(nuc_order_dim,order_dim),:,:,iazi,ipol) = & - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) + & - atom_density * & - nuc % scatter(iazi,ipol) % obj % get_matrix(& - min(nuc_order_dim,order_dim)) - end do - end do - end select - end do - - ! Initialize the ScattData Object - do ipol = 1, n_pol - do iazi = 1, n_azi - call this % scatter(iazi,ipol) % obj % init( & - temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) - end do - end do - - ! Now normalize chi - if (mat % fissionable) then - do ipol = 1, n_pol - do iazi = 1, n_azi - do gin = 1, groups - norm = sum(this % chi(:,gin,iazi,ipol)) - if (norm > ZERO) then - this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / norm - end if - end do - end do - end do - end if - - ! Deallocate temporaries for the next material - deallocate(scatt_coeffs, temp_mult) - - end subroutine macroxsangle_init - -!=============================================================================== -! MACROXS_*_GET_XS returns the requested data type -!=============================================================================== - - function macroxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) - class(MacroXSIso), intent(in) :: this ! The MacroXS to initialize - character(*) , intent(in) :: xstype ! Type of xs requested - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Energy group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - real(8) :: xs ! Requested x/s - - select case(xstype) - case('total') - xs = this % total(gin) - case('absorption') - xs = this % absorption(gin) - case('fission') - xs = this % fission(gin) - case('kappa_fission') - xs = this % k_fission(gin) - case('nu_fission') - xs = this % nu_fission(gin) - case('scatter') - xs = this % scatter % scattxs(gin) - case('mult') - if (present(gout)) then - if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then - xs = ZERO - else - xs = this % scatter % mult(gin) % data(gout) - end if - else - xs = dot_product(this % scatter % mult(gin) % data, & - this % scatter % scattxs(gin) * & - this % scatter % energy(gin) % data) - xs = xs / this % scatter % scattxs(gin) - end if - case('f_mu', 'f_mu/mult') - if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then - xs = ZERO - else - xs = this % scatter % calc_f(gin, gout, mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter % mult(gin) % data(gout) - end if - end if - end select - - end function macroxsiso_get_xs - - function macroxsangle_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) - class(MacroXSAngle), intent(in) :: this ! The MacroXS to initialize - character(*) , intent(in) :: xstype ! Type of xs requested - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Energy group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - real(8) :: xs ! Requested x/s - - integer :: iazi, ipol - - if (present(uvw)) then - call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - select case(xstype) - case('total') - xs = this % total(gin,iazi,ipol) - case('absorption') - xs = this % absorption(gin,iazi,ipol) - case('fission') - xs = this % fission(gin,iazi,ipol) - case('kappa_fission') - xs = this % k_fission(gin,iazi,ipol) - case('nu_fission') - xs = this % nu_fission(gin,iazi,ipol) - case('scatter') - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) - case('mult') - if (present(gout)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then - xs = ZERO - else - xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - end if - else - xs = dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & - this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data) - xs = xs / this % scatter(iazi,ipol) % obj % scattxs(gin) - end if - case('f_mu', 'f_mu/mult') - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then - xs = ZERO - else - xs = this % scatter(iazi,ipol) % obj % calc_f(gin,gout,mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - end if - end if - end select - end if - - end function macroxsangle_get_xs - -!=============================================================================== -! MACROXS_*_SAMPLE_FISSION_ENERGY samples the outgoing energy from a fission -! event -!=============================================================================== - - function macroxsiso_sample_fission_energy(this, gin, uvw) result(gout) - class(MacroXSIso), intent(in) :: this ! Data to work with - integer, intent(in) :: gin ! Incoming energy group - real(8), intent(in) :: uvw(3) ! Particle Direction - integer :: gout ! Sampled outgoing group - real(8) :: xi ! Our random number - real(8) :: prob ! Running probability - - xi = prn() - gout = 1 - prob = this % chi(gout,gin) - - do while (prob < xi) - gout = gout + 1 - prob = prob + this % chi(gout,gin) - end do - - end function macroxsiso_sample_fission_energy - - function macroxsangle_sample_fission_energy(this, gin, uvw) result(gout) - class(MacroXSAngle), intent(in) :: this ! Data to work with - integer, intent(in) :: gin ! Incoming energy group - real(8), intent(in) :: uvw(3) ! Particle Direction - integer :: gout ! Sampled outgoing group - real(8) :: xi ! Our random number - real(8) :: prob ! Running probability - integer :: iazi, ipol - - call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - - xi = prn() - gout = 1 - prob = this % chi(gout,gin,iazi,ipol) - - do while (prob < xi) - gout = gout + 1 - prob = prob + this % chi(gout,gin,iazi,ipol) - end do - - end function macroxsangle_sample_fission_energy - -!=============================================================================== -! MACROXS*_SAMPLE_SCATTER Selects outgoing energy and angle after a scatter -! event -!=============================================================================== - - subroutine macroxsiso_sample_scatter(this, uvw, gin, gout, mu, wgt) - class(MacroXSIso), intent(in) :: this - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - integer, intent(in) :: gin ! Incoming neutron group - integer, intent(out) :: gout ! Sampled outgoin group - real(8), intent(out) :: mu ! Sampled change in angle - real(8), intent(inout) :: wgt ! Particle weight - - call this % scatter % sample(gin, gout, mu, wgt) - - end subroutine macroxsiso_sample_scatter - - subroutine macroxsangle_sample_scatter(this, uvw, gin, gout, mu, wgt) - class(MacroXSAngle), intent(in) :: this - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - integer, intent(in) :: gin ! Incoming neutron group - integer, intent(out) :: gout ! Sampled outgoin group - real(8), intent(out) :: mu ! Sampled change in angle - real(8), intent(inout) :: wgt ! Particle weight - - integer :: iazi, ipol ! Angular indices - - call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - call this % scatter(iazi,ipol) % obj % sample(gin,gout,mu,wgt) - - end subroutine macroxsangle_sample_scatter - -!=============================================================================== -! MACROXS*_CALCULATE_XS determines the multi-group macroscopic cross sections -! for the material the particle is currently traveling through. -!=============================================================================== - - subroutine macroxsiso_calculate_xs(this, gin, uvw, xs) - class(MacroXSIso), intent(in) :: this - integer, intent(in) :: gin ! Incoming neutron group - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data - - xs % total = this % total(gin) - xs % elastic = this % scatter % scattxs(gin) - xs % absorption = this % absorption(gin) - xs % nu_fission = this % nu_fission(gin) - - end subroutine macroxsiso_calculate_xs - - subroutine macroxsangle_calculate_xs(this, gin, uvw, xs) - class(MacroXSAngle), intent(in) :: this - integer, intent(in) :: gin ! Incoming neutron group - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data - - integer :: iazi, ipol - - call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - xs % total = this % total(gin,iazi,ipol) - xs % elastic = this % scatter(iazi,ipol) % obj % scattxs(gin) - xs % absorption = this % absorption(gin,iazi,ipol) - xs % nu_fission = this % nu_fission(gin,iazi,ipol) - - end subroutine macroxsangle_calculate_xs - -end module macroxs_header diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index db2b14936..283024e29 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -3,9 +3,8 @@ module mgxs_data use constants use error, only: fatal_error use global - use macroxs_header use material_header, only: Material - use nuclide_header + use mgxs_header use output, only: write_message use set_header, only: SetChar use string, only: to_lower @@ -118,17 +117,14 @@ contains ! Now allocate accordingly select case(representation) case(MGXS_ISOTROPIC) - allocate(NuclideIso :: nuclides_MG(i_nuclide) % obj) + allocate(MgxsIso :: nuclides_MG(i_nuclide) % obj) case(MGXS_ANGLE) - allocate(NuclideAngle :: nuclides_MG(i_nuclide) % obj) + allocate(MgxsAngle :: nuclides_MG(i_nuclide) % obj) end select ! Now read in the data specific to the type we just declared - call nuclides_MG(i_nuclide) % obj % init(node_xsdata, energy_groups, & - get_kfiss, get_fiss, max_order) - - ! Keep track of what listing is associated with this nuclide - nuclides_MG(i_nuclide) % obj % listing = i_listing + call nuclides_MG(i_nuclide) % obj % init_file(node_xsdata, & + energy_groups,get_kfiss,get_fiss,max_order,i_listing) ! Add name and alias to dictionary call already_read % add(name) @@ -202,14 +198,13 @@ contains ! how we allocate the scatter object within macroxs scatt_type = nuclides_MG(mat % nuclide(1)) % obj % scatt_type select type(nuc => nuclides_MG(mat % nuclide(1)) % obj) - type is (NuclideIso) - allocate(MacroXSIso :: macro_xs(i_mat) % obj) - type is (NuclideAngle) - allocate(MacroXSAngle :: macro_xs(i_mat) % obj) + type is (MgxsIso) + allocate(MgxsIso :: macro_xs(i_mat) % obj) + type is (MgxsAngle) + allocate(MgxsAngle :: macro_xs(i_mat) % obj) end select - call macro_xs(i_mat) % obj % init(mat, nuclides_MG, energy_groups, & - get_kfiss, get_fiss, max_order, & - scatt_type) + call macro_xs(i_mat) % obj % combine(mat,nuclides_MG,energy_groups, & + get_kfiss,get_fiss,max_order,scatt_type,i_mat) end do end subroutine create_macro_xs diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 36e3964da..c87b37ce2 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -7,7 +7,7 @@ module mgxs_header use material_header, only: material use math, only: calc_pn, calc_rn, expand_harmonic, & evaluate_legendre, find_angle - use nuclide_header, only: NuclideMGContainer, MaterialMacroXS + use nuclide_header, only: MaterialMacroXS use random_lcg, only: prn use scattdata_header use string @@ -18,11 +18,11 @@ module mgxs_header !=============================================================================== type, abstract :: Mgxs - character(12) :: name ! name of dataset, e.g. 92235.03c - integer :: zaid ! Z and A identifier, e.g. 92235 - real(8) :: awr ! Atomic Weight Ratio - integer :: listing ! index in xs_listings - real(8) :: kT ! temperature in MeV (k*T) + character(len=104) :: name ! name of dataset, e.g. 92235.03c + integer :: zaid ! Z and A identifier, e.g. 92235 + real(8) :: awr ! Atomic Weight Ratio + integer :: listing ! index in xs_listings + real(8) :: kT ! temperature in MeV (k*T) ! Fission information logical :: fissionable ! mgxs object is fissionable? @@ -32,25 +32,38 @@ module mgxs_header procedure(mgxs_init_file_), deferred :: init_file ! Initialize the data procedure(mgxs_print_), deferred :: print ! Writes object info procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs - ! procedure(mgxs_combine_), deferred :: combine ! initializes object - ! ! Sample the outgoing energy from a fission event + procedure(mgxs_combine_), deferred :: combine ! initializes object + ! Sample the outgoing energy from a fission event procedure(mgxs_sample_fission_), deferred :: sample_fission_energy - ! ! Sample the outgoing energy and angle from a scatter event + ! Sample the outgoing energy and angle from a scatter event procedure(mgxs_sample_scatter_), deferred :: sample_scatter - ! ! Calculate the material specific MGXS data from the nuclides + ! Calculate the material specific MGXS data from the nuclides procedure(mgxs_calculate_xs_), deferred :: calculate_xs end type Mgxs +!=============================================================================== +! MGXSCONTAINER pointer array for storing Nuclides +!=============================================================================== + + type MgxsContainer + class(Mgxs), pointer :: obj + end type MgxsContainer + +!=============================================================================== +! Interfaces for MGXS +!=============================================================================== + abstract interface - subroutine mgxs_init_file_(this, node_xsdata, groups, get_kfiss, get_fiss, & - max_order) + subroutine mgxs_init_file_(this,node_xsdata,groups,get_kfiss,get_fiss, & + max_order,i_listing) import Mgxs, Node class(Mgxs), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: i_listing ! Index of listings array end subroutine mgxs_init_file_ subroutine mgxs_print_(this, unit) @@ -59,7 +72,7 @@ module mgxs_header integer, optional, intent(in) :: unit end subroutine mgxs_print_ - function mgxs_get_xs_(this, xstype, gin, gout, uvw, mu) result(xs) + function mgxs_get_xs_(this,xstype,gin,gout,uvw,mu) result(xs) import Mgxs class(Mgxs), intent(in) :: this character(*), intent(in) :: xstype ! Cross Section Type @@ -70,7 +83,7 @@ module mgxs_header real(8) :: xs ! Resultant xs end function mgxs_get_xs_ - pure function mgxs_calc_f_(this, gin, gout, mu, uvw, iazi, ipol) result(f) + pure function mgxs_calc_f_(this,gin,gout,mu,uvw,iazi,ipol) result(f) import Mgxs class(Mgxs), intent(in) :: this integer, intent(in) :: gin ! Incoming Energy Group @@ -83,17 +96,18 @@ module mgxs_header end function mgxs_calc_f_ - subroutine mgxs_combine_(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - import Mgxs, Material, NuclideMGContainer, MAX_LINE_LEN + subroutine mgxs_combine_(this,mat,nuclides,groups,get_kfiss,get_fiss, & + max_order,scatt_type,i_listing) + import Mgxs, Material, MgxsContainer class(Mgxs), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material - type(NuclideMGContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order + type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? + integer, intent(in) :: i_listing ! Index in listings end subroutine mgxs_combine_ function mgxs_sample_fission_(this, gin, uvw) result(gout) @@ -118,9 +132,9 @@ module mgxs_header subroutine mgxs_calculate_xs_(this, gin, uvw, xs) import Mgxs, MaterialMacroXS class(Mgxs), intent(in) :: this - integer, intent(in) :: gin ! Incoming neutron group - real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs + integer, intent(in) :: gin ! Incoming neutron group + real(8), intent(in) :: uvw(3) ! Incoming neutron direction + type(MaterialMacroXS), intent(inout) :: xs ! Resultant Mgxs Data end subroutine mgxs_calculate_xs_ end interface @@ -144,7 +158,7 @@ module mgxs_header procedure :: init_file => mgxsiso_init_file ! Initialize Nuclidic MGXS Data procedure :: print => mgxsiso_print ! Writes nuclide info procedure :: get_xs => mgxsiso_get_xs ! Gets Size of Data w/in Object - ! procedure :: combine => mgxsiso_combine ! inits object + procedure :: combine => mgxsiso_combine ! inits object procedure :: sample_fission_energy => mgxsiso_sample_fission_energy procedure :: sample_scatter => mgxsiso_sample_scatter procedure :: calculate_xs => mgxsiso_calculate_xs @@ -175,20 +189,12 @@ module mgxs_header procedure :: init_file => mgxsang_init_file ! Initialize Nuclidic MGXS Data procedure :: print => mgxsang_print ! Writes nuclide info procedure :: get_xs => mgxsang_get_xs ! Gets Size of Data w/in Object - ! procedure :: combine => mgxsang_combine ! inits object + procedure :: combine => mgxsang_combine ! inits object procedure :: sample_fission_energy => mgxsang_sample_fission_energy procedure :: sample_scatter => mgxsang_sample_scatter procedure :: calculate_xs => mgxsang_calculate_xs end type MgxsAngle -!=============================================================================== -! MGXSCONTAINER pointer array for storing Nuclides -!=============================================================================== - - type MgxsContainer - class(Mgxs), pointer :: obj - end type MgxsContainer - contains !=============================================================================== @@ -197,9 +203,10 @@ module mgxs_header ! the xsdata object node itself. !=============================================================================== - subroutine mgxs_init_file(this, node_xsdata) + subroutine mgxs_init_file(this,node_xsdata,i_listing) class(Mgxs), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml + integer, intent(in) :: i_listing ! Index in listings array character(MAX_LINE_LEN) :: temp_str @@ -214,7 +221,7 @@ module mgxs_header if (check_for_node(node_xsdata, "zaid")) then call get_node_value(node_xsdata, "zaid", this % zaid) else - this % zaid = -1 + this % zaid = 0 end if if (check_for_node(node_xsdata, "scatt_type")) then call get_node_value(node_xsdata, "scatt_type", temp_str) @@ -244,15 +251,20 @@ module mgxs_header call fatal_error("Fissionable element must be set!") end if + ! Keep track of what listing is associated with this nuclide + this % listing = i_listing + end subroutine mgxs_init_file - subroutine mgxsiso_init_file(this,node_xsdata,groups,get_kfiss,get_fiss,max_order) + subroutine mgxsiso_init_file(this,node_xsdata,groups,get_kfiss,get_fiss, & + max_order,i_listing) class(MgxsIso), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Need fiss data? integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: i_listing ! Index in listings array type(Node), pointer :: node_legendre_mu character(MAX_LINE_LEN) :: temp_str @@ -267,7 +279,7 @@ module mgxs_header integer :: legendre_mu_points, imu ! Call generic data gathering routine (will populate the metadata) - call mgxs_init_file(this, node_xsdata) + call mgxs_init_file(this,node_xsdata,i_listing) ! Load the more specific data allocate(this % nu_fission(groups)) @@ -530,13 +542,15 @@ module mgxs_header end subroutine mgxsiso_init_file - subroutine mgxsang_init_file(this,node_xsdata,groups,get_kfiss,get_fiss,max_order) + subroutine mgxsang_init_file(this,node_xsdata,groups,get_kfiss,get_fiss, & + max_order,i_listing) class(MgxsAngle), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups logical, intent(in) :: get_kfiss ! Need Kappa-Fission? logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: i_listing ! Index in listings array type(Node), pointer :: node_legendre_mu character(MAX_LINE_LEN) :: temp_str @@ -551,7 +565,7 @@ module mgxs_header integer :: legendre_mu_points, imu, ipol, iazi ! Call generic data gathering routine (will populate the metadata) - call mgxs_init_file(this, node_xsdata) + call mgxs_init_file(this,node_xsdata,i_listing) if (check_for_node(node_xsdata, "num_polar")) then call get_node_value(node_xsdata, "num_polar", this % n_pol) @@ -927,13 +941,18 @@ module mgxs_header character(MAX_LINE_LEN) :: temp_str ! Basic nuclide information - write(unit_,*) 'MGXS Entry ' // trim(this % name) + write(unit_,*) 'MGXS Entry: ' // trim(this % name) if (this % zaid > 0) then - ! Dont print if data was macroscopic and thus zaid & AWR would be nonsense - write(unit_,*) ' zaid = ' // trim(to_str(this % zaid)) - write(unit_,*) ' awr = ' // trim(to_str(this % awr)) + write(unit_,*) ' ZAID = ' // trim(to_str(this % zaid)) + else if (this % zaid < 0) then + write(unit_,*) ' Material id = ' // trim(to_str(-this % zaid)) + end if + if (this % awr > ZERO) then + write(unit_,*) ' AWR = ' // trim(to_str(this % awr)) + end if + if (this % kT > ZERO) then + write(unit_,*) ' kT = ' // trim(to_str(this % kT)) end if - write(unit_,*) ' kT = ' // trim(to_str(this % kT)) if (this % scatt_type == ANGLE_LEGENDRE) then temp_str = "Legendre" write(unit_,*) ' Scattering Type = ' // trim(temp_str) @@ -941,7 +960,7 @@ module mgxs_header type is (MgxsIso) temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1) end select - write(unit_,*) ' Scattering Order = ' // trim(temp_str) + write(unit_,*) ' Scattering Order = ' // trim(temp_str) else if (this % scatt_type == ANGLE_HISTOGRAM) then temp_str = "Histogram" write(unit_,*) ' Scattering Type = ' // trim(temp_str) @@ -949,7 +968,7 @@ module mgxs_header type is (MgxsIso) temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) end select - write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) + write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) else if (this % scatt_type == ANGLE_TABULAR) then temp_str = "Tabular" write(unit_,*) ' Scattering Type = ' // trim(temp_str) @@ -957,7 +976,7 @@ module mgxs_header type is (MgxsIso) temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) end select - write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) + write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) end if write(unit_,*) ' Fissionable = ', this % fissionable @@ -1073,7 +1092,7 @@ module mgxs_header !=============================================================================== function mgxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) - class(MgxsIso), intent(in) :: this ! The MacroXS to initialize + class(MgxsIso), intent(in) :: this ! The Mgxs to initialize character(*) , intent(in) :: xstype ! Type of xs requested integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group @@ -1117,7 +1136,7 @@ module mgxs_header case('mult') if (present(gout)) then if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then + gout > this % scatter % gmax(gin)) then xs = ZERO else xs = this % scatter % mult(gin) % data(gout) @@ -1131,7 +1150,7 @@ module mgxs_header case('f_mu', 'f_mu/mult') if (present(gout) .and. present(mu)) then if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then + gout > this % scatter % gmax(gin)) then xs = ZERO else xs = this % scatter % calc_f(gin, gout, mu) @@ -1153,7 +1172,7 @@ module mgxs_header end function mgxsiso_get_xs function mgxsang_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) - class(MgxsAngle), intent(in) :: this ! The MacroXS to initialize + class(MgxsAngle), intent(in) :: this ! The Mgxs to initialize character(*) , intent(in) :: xstype ! Type of xs requested integer, intent(in) :: gin ! Incoming Energy group integer, optional, intent(in) :: gout ! Outgoing Energy group @@ -1201,7 +1220,7 @@ module mgxs_header case('mult') if (present(gout)) then if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then xs = ZERO else xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) @@ -1215,7 +1234,7 @@ module mgxs_header case('f_mu', 'f_mu/mult') if (present(gout) .and. present(mu)) then if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then xs = ZERO else xs = this % scatter(iazi,ipol) % obj % calc_f(gin, gout, mu) @@ -1245,16 +1264,41 @@ module mgxs_header ! objects !=============================================================================== - subroutine mgxsiso_combine(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - class(MgxsIso), intent(inout) :: this ! The MacroXS to initialize + subroutine mgxs_combine(this,mat,scatt_type,i_listing) + class(Mgxs), intent(inout) :: this ! The Mgxs to initialize + type(Material), pointer, intent(in) :: mat ! base material + integer, intent(in) :: scatt_type ! How is data presented + integer, intent(in) :: i_listing ! Index in listings + + ! Fill in meta-data from material information + if (mat % name == "") then + this % name = trim(to_str(mat % id)) + else + this % name = mat % name + end if + this % zaid = -mat % id + this % listing = i_listing + this % fissionable = mat % fissionable + this % scatt_type = scatt_type + + ! The following info we should initialize, but we dont need it nor + ! does it have guaranteed meaning. + this % awr = -ONE + this % kT = -ONE + + end subroutine mgxs_combine + + subroutine mgxsiso_combine(this,mat,nuclides,groups,get_kfiss,get_fiss, & + max_order,scatt_type,i_listing) + class(MgxsIso), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! How is data presented + integer, intent(in) :: i_listing ! Index in listings integer :: i ! loop index over nuclides integer :: gin, gout ! group indices @@ -1264,6 +1308,9 @@ module mgxs_header real(8), allocatable :: temp_mult(:,:) real(8), allocatable :: scatt_coeffs(:,:,:) + ! Set the meta-data + call mgxs_combine(this,mat,scatt_type,i_listing) + ! Determine the scattering type of our data and ensure all scattering orders ! are the same. select type(nuc => nuclides(mat % nuclide(1)) % obj) @@ -1387,7 +1434,7 @@ module mgxs_header nuc % scatter % get_matrix(min(nuc_order_dim,order_dim)) type is (MgxsAngle) - call fatal_error("Invalid Passing of MgxsAngle to MacroXSIso Object") + call fatal_error("Invalid Passing of MgxsAngle to MgxsIso Object") end select end do @@ -1409,16 +1456,17 @@ module mgxs_header end subroutine mgxsiso_combine - subroutine mgxsang_combine(this, mat, nuclides, groups, get_kfiss, get_fiss, & - max_order, scatt_type) - class(MgxsAngle), intent(inout) :: this ! The MacroXS to initialize + subroutine mgxsang_combine(this,mat,nuclides,groups,get_kfiss,get_fiss, & + max_order,scatt_type,i_listing) + class(MgxsAngle), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from - integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order + integer, intent(in) :: groups ! Number of E groups + logical, intent(in) :: get_kfiss ! Should we get kfiss data? + logical, intent(in) :: get_fiss ! Should we get fiss data? + integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? + integer, intent(in) :: i_listing ! Index in listings integer :: i ! loop index over nuclides integer :: gin, gout ! group indices @@ -1429,6 +1477,9 @@ module mgxs_header real(8), allocatable :: temp_mult(:,:,:,:) real(8), allocatable :: scatt_coeffs(:,:,:,:,:) + ! Set the meta-data + call mgxs_combine(this,mat,scatt_type,i_listing) + ! Get the number of each polar and azi angles and make sure all the ! NuclideAngle types have the same number of these angles n_pol = -1 @@ -1557,7 +1608,7 @@ module mgxs_header ! Perform our operations which depend upon the type select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) - call fatal_error("Invalid Passing of MgxsIso to MacroXSAngle Object") + call fatal_error("Invalid Passing of MgxsIso to MgxsAngle Object") type is (MgxsAngle) ! Add contributions to total, absorption, and fission data (if necessary) this % total = this % total + atom_density * nuc % total @@ -1712,10 +1763,10 @@ module mgxs_header !=============================================================================== subroutine mgxsiso_calculate_xs(this, gin, uvw, xs) - class(MgxsIso), intent(in) :: this + class(MgxsIso), intent(in) :: this integer, intent(in) :: gin ! Incoming neutron group real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data + type(MaterialMacroXS), intent(inout) :: xs ! Resultant Mgxs Data xs % total = this % total(gin) xs % elastic = this % scatter % scattxs(gin) @@ -1725,10 +1776,10 @@ module mgxs_header end subroutine mgxsiso_calculate_xs subroutine mgxsang_calculate_xs(this, gin, uvw, xs) - class(MgxsAngle), intent(in) :: this + class(MgxsAngle), intent(in) :: this integer, intent(in) :: gin ! Incoming neutron group real(8), intent(in) :: uvw(3) ! Incoming neutron direction - type(MaterialMacroXS), intent(inout) :: xs ! Resultant MacroXS Data + type(MaterialMacroXS), intent(inout) :: xs ! Resultant Mgxs Data integer :: iazi, ipol diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index e964e970d..9600e6739 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -7,7 +7,6 @@ module nuclide_header use endf, only: reaction_name use error, only: fatal_error use list_header, only: ListInt - use math, only: evaluate_legendre, find_angle use scattdata_header use string use xml_interface @@ -15,12 +14,12 @@ module nuclide_header implicit none !=============================================================================== -! Nuclide contains the base nuclidic data for a nuclide, which does not depend -! upon how the nuclear data is represented (i.e., CE, or any variant of MG). -! The extended types, NuclideCE and NuclideMG deal with the rest +! Nuclide contains the base nuclidic data for a nuclide described as needed +! for continuous-energy neutron transport. !=============================================================================== - type, abstract :: Nuclide + type :: Nuclide + ! Nuclide meta-data character(12) :: name ! name of nuclide, e.g. 92235.03c integer :: zaid ! Z and A identifier, e.g. 92235 real(8) :: awr ! Atomic Weight Ratio @@ -30,19 +29,6 @@ module nuclide_header ! Fission information logical :: fissionable ! nuclide is fissionable? - contains - procedure(nuclide_print_), deferred :: print ! Writes nuclide info - end type Nuclide - - abstract interface - subroutine nuclide_print_(this, unit) - import Nuclide - class(Nuclide),intent(in) :: this - integer, optional, intent(in) :: unit - end subroutine nuclide_print_ - end interface - - type, extends(Nuclide) :: NuclideCE ! Energy grid information integer :: n_grid ! # of nuclide grid points integer, allocatable :: grid_index(:) ! log grid mapping indices @@ -99,120 +85,13 @@ module nuclide_header ! array; used at tally-time contains - procedure :: clear => nuclidece_clear - procedure :: print => nuclidece_print - end type NuclideCE - - type, abstract, extends(Nuclide) :: NuclideMG - integer :: scatt_type ! either legendre, histogram, or tabular. - contains - procedure(nuclidemg_init_), deferred :: init ! Initialize the data - procedure(nuclidemg_get_xs_), deferred :: get_xs ! Get the requested xs - end type NuclideMG - - abstract interface - - subroutine nuclidemg_init_(this, node_xsdata, groups, get_kfiss, get_fiss, & - max_order) - import NuclideMG, Node - class(NuclideMG), intent(inout) :: this ! Working Object - type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml - integer, intent(in) :: groups ! Number of Energy groups - logical, intent(in) :: get_kfiss ! Need Kappa-Fission? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order - end subroutine nuclidemg_init_ - - function nuclidemg_get_xs_(this, xstype, gin, gout, uvw, mu, iazi, ipol) & - result(xs) - import NuclideMG - class(NuclideMG), intent(in) :: this - character(*), intent(in) :: xstype ! Cross Section Type - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index - real(8) :: xs ! Resultant xs - end function nuclidemg_get_xs_ - - pure function nuclidemg_calc_f_(this, gin, gout, mu, uvw, iazi, ipol) result(f) - import NuclideMG - class(NuclideMG), intent(in) :: this - integer, intent(in) :: gin ! Incoming Energy Group - integer, intent(in) :: gout ! Outgoing Energy Group - real(8), intent(in) :: mu ! Angle of interest - real(8), intent(in), optional :: uvw(3) ! Direction vector - integer, intent(in), optional :: iazi ! Incoming Energy Group - integer, intent(in), optional :: ipol ! Outgoing Energy Group - real(8) :: f ! Return value of f(mu) - - end function nuclidemg_calc_f_ - end interface - -!=============================================================================== -! NuclideIso contains the base MGXS data for a nuclide specifically for -! isotropically weighted MGXS -!=============================================================================== - - type, extends(NuclideMG) :: NuclideIso - - ! Microscopic cross sections - real(8), allocatable :: total(:) ! total cross section - real(8), allocatable :: absorption(:) ! absorption cross section - class(ScattData), allocatable :: scatter ! scattering information - real(8), allocatable :: nu_fission(:,:) ! fission matrix (Gout x Gin) - real(8), allocatable :: k_fission(:) ! kappa-fission - real(8), allocatable :: fission(:) ! neutron production - real(8), allocatable :: chi(:) ! Fission Spectra - - contains - procedure :: init => nuclideiso_init ! Initialize Nuclidic MGXS Data - procedure :: print => nuclideiso_print ! Writes nuclide info - procedure :: get_xs => nuclideiso_get_xs ! Gets Size of Data w/in Object - end type NuclideIso - -!=============================================================================== -! NuclideAngle contains the base MGXS data for a nuclide specifically for -! explicit angle-dependent weighted MGXS -!=============================================================================== - - type, extends(NuclideMG) :: NuclideAngle - - ! Microscopic cross sections. Dimensions are: (n_pol, n_azi, Nl, Ng, Ng) - real(8), allocatable :: total(:,:,:) ! total cross section - real(8), allocatable :: absorption(:,:,:) ! absorption cross section - type(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information - real(8), allocatable :: nu_fission(:,:,:,:) ! fission matrix (Gout x Gin) - real(8), allocatable :: k_fission(:,:,:) ! kappa-fission - real(8), allocatable :: fission(:,:,:) ! neutron production - real(8), allocatable :: chi(:,:,:) ! Fission Spectra - real(8), allocatable :: mult(:,:,:,:) ! Scatter multiplicity (Gout x Gin) - - ! In all cases, right-most indices are theta, phi - integer :: n_pol ! Number of polar angles - integer :: n_azi ! Number of azimuthal angles - real(8), allocatable :: polar(:) ! polar angles - real(8), allocatable :: azimuthal(:) ! azimuthal angles - - contains - procedure :: init => nuclideangle_init ! Initialize Nuclidic MGXS Data - procedure :: print => nuclideangle_print ! Gets Size of Data w/in Object - procedure :: get_xs => nuclideangle_get_xs ! Gets Size of Data w/in Object - end type NuclideAngle - -!=============================================================================== -! NUCLIDEMGCONTAINER pointer array for storing Nuclides -!=============================================================================== - - type NuclideMGContainer - class(NuclideMG), pointer :: obj - end type NuclideMGContainer + procedure :: clear => nuclide_clear + procedure :: print => nuclide_print + end type Nuclide !=============================================================================== ! NUCLIDE0K temporarily contains all 0K cross section data and other parameters -! needed to treat resonance scattering before transferring them to NuclideCE +! needed to treat resonance scattering before transferring them to Nuclide !=============================================================================== type Nuclide0K @@ -285,667 +164,13 @@ module nuclide_header contains !=============================================================================== -! NUCLIDE_*_INIT reads in the data from the XML file, as already accessed -!=============================================================================== - - subroutine nuclidemg_init(this, node_xsdata) - class(NuclideMG), intent(inout) :: this ! Working Object - type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml - - character(MAX_LINE_LEN) :: temp_str - - ! Load the nuclide metadata - call get_node_value(node_xsdata, "name", this % name) - this % name = to_lower(this % name) - if (check_for_node(node_xsdata, "kT")) then - call get_node_value(node_xsdata, "kT", this % kT) - else - this % kT = ZERO - end if - if (check_for_node(node_xsdata, "zaid")) then - call get_node_value(node_xsdata, "zaid", this % zaid) - else - this % zaid = -1 - end if - if (check_for_node(node_xsdata, "scatt_type")) then - call get_node_value(node_xsdata, "scatt_type", temp_str) - temp_str = trim(to_lower(temp_str)) - if (temp_str == 'legendre') then - this % scatt_type = ANGLE_LEGENDRE - else if (temp_str == 'histogram') then - this % scatt_type = ANGLE_HISTOGRAM - else if (temp_str == 'tabular') then - this % scatt_type = ANGLE_TABULAR - else - call fatal_error("Invalid Scatt Type Option!") - end if - else - this % scatt_type = ANGLE_LEGENDRE - end if - - if (check_for_node(node_xsdata, "fissionable")) then - call get_node_value(node_xsdata, "fissionable", temp_str) - temp_str = to_lower(temp_str) - if (trim(temp_str) == 'true' .or. trim(temp_str) == '1') then - this % fissionable = .true. - else - this % fissionable = .false. - end if - else - call fatal_error("Fissionable element must be set!") - end if - - end subroutine nuclidemg_init - - subroutine nuclideiso_init(this, node_xsdata, groups, get_kfiss, get_fiss, & - max_order) - class(NuclideIso), intent(inout) :: this ! Working Object - type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml - integer, intent(in) :: groups ! Number of Energy groups - logical, intent(in) :: get_kfiss ! Need Kappa-Fission? - logical, intent(in) :: get_fiss ! Need fiss data? - integer, intent(in) :: max_order ! Maximum requested order - - type(Node), pointer :: node_legendre_mu - character(MAX_LINE_LEN) :: temp_str - logical :: enable_leg_mu - real(8), allocatable :: temp_arr(:) - real(8), allocatable :: temp_mult(:,:) - real(8), allocatable :: scatt_coeffs(:,:,:) - real(8), allocatable :: input_scatt(:,:,:) - real(8), allocatable :: temp_scatt(:,:,:) - real(8) :: dmu, mu, norm - integer :: order, order_dim, gin, gout, l, arr_len - integer :: legendre_mu_points, imu - - ! Call generic data gathering routine (will populate the metadata) - call nuclidemg_init(this, node_xsdata) - - ! Load the more specific data - if (this % fissionable) then - - if (check_for_node(node_xsdata,"chi")) then - ! Get chi - allocate(this % chi(groups)) - call get_node_array(node_xsdata,"chi",this % chi) - - ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata,"nu_fission")) then - allocate(temp_arr(1 * groups)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(this % nu_fission(1,groups)) - this % nu_fission = reshape(temp_arr,(/1,groups/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if - - else - ! Get nu_fission (as a matrix) - if (check_for_node(node_xsdata,"nu_fission")) then - - allocate(temp_arr(groups*groups)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(this % nu_fission(groups, groups)) - this % nu_fission = reshape(temp_arr,(/groups,groups/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if - end if - ! If we have a need* for the fission and kappa-fission x/s, get them - ! (*Need is defined as will be using it to tally) - if (get_fiss) then - allocate(this % fission(groups)) - if (check_for_node(node_xsdata,"fission")) then - call get_node_array(node_xsdata,"fission",this % fission) - else - call fatal_error("Fission data missing, required due to fission& - & tallies in tallies.xml file!") - end if - end if - if (get_kfiss) then - allocate(this % k_fission(groups)) - if (check_for_node(node_xsdata,"kappa_fission")) then - call get_node_array(node_xsdata,"kappa_fission",this % k_fission) - else - call fatal_error("kappa_fission data missing, required due to & - &kappa-fission tallies in tallies.xml file!") - end if - end if - end if - - allocate(this % absorption(groups)) - if (check_for_node(node_xsdata,"absorption")) then - call get_node_array(node_xsdata,"absorption",this % absorption) - else - call fatal_error("Must provide absorption!") - end if - - ! Get multiplication data if present - allocate(temp_mult(groups, groups)) - if (check_for_node(node_xsdata,"multiplicity")) then - arr_len = get_arraysize_double(node_xsdata,"multiplicity") - if (arr_len == groups * groups) then - allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata,"multiplicity",temp_arr) - temp_mult = reshape(temp_arr, (/groups, groups/)) - deallocate(temp_arr) - else - call fatal_error("Multiplicity length not same as number of groups& - & squared!") - end if - else - temp_mult = ONE - end if - - ! Get scattering treatment information - ! Tabular_legendre tells us if we are to treat the provided - ! Legendre polynomials as tabular data (if enable is true) or leaving - ! them as Legendres (if enable is false, or the default) - - ! Set the default (leave as Legendre polynomials) - enable_leg_mu = .false. - if (check_for_node(node_xsdata,"tabular_legendre")) then - call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) - if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu,"enable",temp_str) - temp_str = trim(to_lower(temp_str)) - if (temp_str == 'true' .or. temp_str == '1') then - enable_leg_mu = .true. - elseif (temp_str == 'false' .or. temp_str == '0') then - enable_leg_mu = .false. - else - call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) - end if - end if - ! Ok, so if we need to convert to a tabular form, get the user provided - ! number of points - if (enable_leg_mu) then - if (check_for_node(node_legendre_mu,"num_points")) then - call get_node_value(node_legendre_mu,"num_points", & - legendre_mu_points) - if (legendre_mu_points <= 0) & - call fatal_error("num_points element must be positive& - & and non-zero!") - else - ! Set the default number of points (0.0625 spacing) - legendre_mu_points = 33 - end if - end if - end if - - ! Get the library's value for the order - if (check_for_node(node_xsdata,"order")) then - call get_node_value(node_xsdata,"order",order) - else - call fatal_error("Order Must Be Provided!") - end if - - ! Before retrieving the data, store the dimensionality of the data in - ! order_dim. For Legendre data, we usually refer to it as Pn where - ! n is the order. However Pn has n+1 sets of points (since you need to - ! the count the P0 moment). Adjust for that. Histogram and Tabular - ! formats dont need this adjustment. - if (this % scatt_type == ANGLE_LEGENDRE) then - order_dim = order + 1 - else - order_dim = order - end if - - ! The input is gathered in the more user-friendly facing format of - ! Gout x Gin x Order. We will get it in that format in input_scatt, - ! but then need to convert it to a more useful ordering for processing - ! (Order x Gout x Gin). - allocate(input_scatt(groups, groups, order_dim)) - if (check_for_node(node_xsdata,"scatter")) then - allocate(temp_arr(groups * groups * order_dim)) - call get_node_array(node_xsdata,"scatter",temp_arr) - input_scatt = reshape(temp_arr,(/groups,groups,order_dim/)) - deallocate(temp_arr) - - ! Compare the number of orders given with the maximum order of the - ! problem. Strip off the supefluous orders if needed. - if (this % scatt_type == ANGLE_LEGENDRE) then - order = min(order_dim - 1, max_order) - order_dim = order + 1 - end if - allocate(temp_scatt(groups,groups,order_dim)) - temp_scatt(:,:,:) = input_scatt(:,:,1:order_dim) - - ! Take input format (groups, groups, order) and convert to - ! the more useful format needed for scattdata: (order, groups, groups) - ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was - ! provided as Legendre coefficients), and the user requested that - ! these legendres be converted to tabular form (note this is also - ! the default behavior), convert that now. - if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then - ! Convert input parameters to what we need for the rest. - this % scatt_type = ANGLE_TABULAR - order_dim = legendre_mu_points - order = order_dim - dmu = TWO / real(order - 1,8) - - allocate(scatt_coeffs(order_dim,groups,groups)) - do gin = 1, groups - do gout = 1, groups - norm = ZERO - do imu = 1, order_dim - if (imu == 1) then - mu = -ONE - else if (imu == order_dim) then - mu = ONE - else - mu = -ONE + real(imu - 1,8) * dmu - end if - scatt_coeffs(imu,gout,gin) = & - evaluate_legendre(temp_scatt(gout,gin,:),mu) - ! Ensure positivity of distribution - if (scatt_coeffs(imu,gout,gin) < ZERO) & - scatt_coeffs(imu,gout,gin) = ZERO - ! And accrue the integral - if (imu > 1) then - norm = norm + HALF * dmu * (scatt_coeffs(imu-1,gout,gin) + & - scatt_coeffs(imu,gout,gin)) - end if - end do - ! Now that we have the integral, lets ensure that the distribution - ! is normalized such that it preserves the original scattering xs - if (norm > ZERO) then - scatt_coeffs(:,gout,gin) = scatt_coeffs(:,gout,gin) * & - temp_scatt(gout,gin,1) / norm - end if - end do - end do - else - ! Sticking with current representation, carry forward but change - ! the array ordering - allocate(scatt_coeffs(order_dim,groups,groups)) - do gin = 1, groups - do gout = 1, groups - do l = 1, order_dim - scatt_coeffs(l,gout,gin) = temp_scatt(gout,gin,l) - end do - end do - end do - end if - deallocate(temp_scatt) - else - call fatal_error("Must provide scatter!") - end if - - ! Allocate and initialize our ScattData Object. - if (this % scatt_type == ANGLE_HISTOGRAM) then - allocate(ScattDataHistogram :: this % scatter) - else if (this % scatt_type == ANGLE_TABULAR) then - allocate(ScattDataTabular :: this % scatter) - else if (this % scatt_type == ANGLE_LEGENDRE) then - allocate(ScattDataLegendre :: this % scatter) - end if - - ! Initialize the ScattData Object - call this % scatter % init(temp_mult, scatt_coeffs) - - ! Get, or infer, total xs data. - allocate(this % total(groups)) - if (check_for_node(node_xsdata,"total")) then - call get_node_array(node_xsdata,"total",this % total) - else - this % total = this % absorption + this % scatter % scattxs - end if - - ! Deallocate temporaries for the next material - deallocate(input_scatt,scatt_coeffs,temp_mult) - - end subroutine nuclideiso_init - - subroutine nuclideangle_init(this, node_xsdata, groups, get_kfiss, get_fiss, & - max_order) - class(NuclideAngle), intent(inout) :: this ! Working Object - type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml - integer, intent(in) :: groups ! Number of Energy groups - logical, intent(in) :: get_kfiss ! Need Kappa-Fission? - logical, intent(in) :: get_fiss ! Should we get fiss data? - integer, intent(in) :: max_order ! Maximum requested order - - type(Node), pointer :: node_legendre_mu - character(MAX_LINE_LEN) :: temp_str - logical :: enable_leg_mu - real(8), allocatable :: temp_arr(:) - real(8), allocatable :: temp_mult(:,:,:,:) - real(8), allocatable :: scatt_coeffs(:,:,:,:,:) - real(8), allocatable :: input_scatt(:,:,:,:,:) - real(8), allocatable :: temp_scatt(:,:,:,:,:) - real(8) :: dmu, mu, norm, dangle - integer :: order, order_dim, gin, gout, l, arr_len - integer :: legendre_mu_points, imu, ipol, iazi - - ! Call generic data gathering routine (will populate the metadata) - call nuclidemg_init(this, node_xsdata) - - if (check_for_node(node_xsdata, "num_polar")) then - call get_node_value(node_xsdata, "num_polar", this % n_pol) - else - call fatal_error("num_polar Must Be Provided!") - end if - - if (check_for_node(node_xsdata, "num_azimuthal")) then - call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) - else - call fatal_error("num_azimuthal Must Be Provided!") - end if - - ! Load angle data, if present (else equally spaced) - allocate(this % polar(this % n_pol)) - allocate(this % azimuthal(this % n_azi)) - if (check_for_node(node_xsdata, "polar")) then - call fatal_error("User-Specified polar angle bins not yet supported!") - ! When this feature is supported, this line will be activated - call get_node_array(node_xsdata, "polar", this % polar) - else - dangle = PI / real(this % n_pol,8) - do ipol = 1, this % n_pol - this % polar(ipol) = (real(ipol,8) - HALF) * dangle - end do - end if - if (check_for_node(node_xsdata, "azimuthal")) then - call fatal_error("User-Specified azimuthal angle bins not yet supported!") - ! When this feature is supported, this line will be activated - call get_node_array(node_xsdata, "azimuthal", this % azimuthal) - else - dangle = TWO * PI / real(this % n_azi,8) - do iazi = 1, this % n_azi - this % azimuthal(iazi) = -PI + (real(iazi,8) - HALF) * dangle - end do - end if - - ! Load the more specific data - if (this % fissionable) then - - if (check_for_node(node_xsdata,"chi")) then - ! Get chi - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"chi",temp_arr) - allocate(this % chi(groups,this % n_azi,this % n_pol)) - this % chi = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) - deallocate(temp_arr) - - ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata,"nu_fission")) then - allocate(temp_arr(1 * groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"nu_fission", temp_arr) - allocate(this % nu_fission(1,groups,this % n_azi,this % n_pol)) - this % nu_fission = reshape(temp_arr, (/1,groups,this % n_azi, & - this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if - - else - ! Get nu_fission (as a matrix) - if (check_for_node(node_xsdata,"nu_fission")) then - - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(this % nu_fission(groups,groups,this % n_azi,this % n_pol)) - this % nu_fission = reshape(temp_arr,(/groups,groups, & - this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("If fissionable, must provide nu_fission!") - end if - end if - ! If we have a need* for the fission and kappa-fission x/s, get them - ! (*Need is defined as will be using it to tally) - if (get_fiss) then - if (check_for_node(node_xsdata,"fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"fission",temp_arr) - allocate(this % fission(groups,this % n_azi,this % n_pol)) - this % fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Fission data missing, required due to fission& - & tallies in tallies.xml file!") - end if - end if - if (get_kfiss) then - if (check_for_node(node_xsdata,"kappa_fission")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"kappa_fission",temp_arr) - allocate(this % k_fission(groups,this % n_azi,this % n_pol)) - this % k_fission = reshape(temp_arr,(/groups, this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("kappa_fission data missing, required due to & - &kappa-fission tallies in tallies.xml file!") - end if - end if - end if - - if (check_for_node(node_xsdata,"absorption")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"absorption",temp_arr) - allocate(this % absorption(groups,this % n_azi,this % n_pol)) - this % absorption = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Must provide absorption!") - end if - - ! Get multiplication data if present - allocate(temp_mult(groups,groups,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"multiplicity")) then - arr_len = get_arraysize_double(node_xsdata,"multiplicity") - if (arr_len == groups * groups * this % n_azi * this % n_pol) then - allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata,"multiplicity",temp_arr) - temp_mult = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - call fatal_error("Multiplicity length not same as number of groups& - & squared!") - end if - else - temp_mult = ONE - end if - - ! Get scattering treatment information - ! Tabular_legendre tells us if we are to treat the provided - ! Legendre polynomials as tabular data (if enable is true) or leaving - ! them as Legendres (if enable is false, or the default) - - ! Set the default (leave as Legendre polynomials) - enable_leg_mu = .false. - if (check_for_node(node_xsdata,"tabular_legendre")) then - call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) - if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu,"enable",temp_str) - temp_str = trim(to_lower(temp_str)) - if (temp_str == 'true' .or. temp_str == '1') then - enable_leg_mu = .true. - elseif (temp_str == 'false' .or. temp_str == '0') then - enable_leg_mu = .false. - else - call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) - end if - end if - ! Ok, so if we need to convert to a tabular form, get the user provided - ! number of points - if (enable_leg_mu) then - if (check_for_node(node_legendre_mu,"num_points")) then - call get_node_value(node_legendre_mu,"num_points", & - legendre_mu_points) - if (legendre_mu_points <= 0) & - call fatal_error("num_points element must be positive& - & and non-zero!") - else - ! Set the default number of points (0.0625 spacing) - legendre_mu_points = 33 - end if - end if - end if - - ! Get the library's value for the order - if (check_for_node(node_xsdata,"order")) then - call get_node_value(node_xsdata,"order",order) - else - call fatal_error("Order Must Be Provided!") - end if - - ! Before retrieving the data, store the dimensionality of the data in - ! order_dim. For Legendre data, we usually refer to it as Pn where - ! n is the order. However Pn has n+1 sets of points (since you need to - ! the count the P0 moment). Adjust for that. Histogram and Tabular - ! formats dont need this adjustment. - if (this % scatt_type == ANGLE_LEGENDRE) then - order_dim = order + 1 - else - order_dim = order - end if - - ! The input is gathered in the more user-friendly facing format of - ! Gout x Gin x Order x Azi x Pol. We will get it in that format in - ! input_scatt, but then need to convert it to a more useful ordering - ! for processing (Order x Gout x Gin x Azi x Pol). - allocate(input_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"scatter")) then - allocate(temp_arr(groups * groups * order_dim * this % n_azi * & - this % n_pol)) - call get_node_array(node_xsdata,"scatter",temp_arr) - input_scatt = reshape(temp_arr,(/groups,groups,order_dim,this % n_azi, & - this % n_pol/)) - deallocate(temp_arr) - - ! Compare the number of orders given with the maximum order of the - ! problem. Strip off the supefluous orders if needed. - if (this % scatt_type == ANGLE_LEGENDRE) then - order = min(order_dim - 1, max_order) - order_dim = order + 1 - end if - - allocate(temp_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) - temp_scatt(:,:,:,:,:) = input_scatt(:,:,1:order_dim,:,:) - - ! Take input format (groups, groups, order) and convert to - ! the more useful format needed for scattdata: (order, groups, groups) - ! However, if scatt_type was ANGLE_LEGENDRE (i.e., the data was - ! provided as Legendre coefficients), and the user requested that - ! these legendres be converted to tabular form (note this is also - ! the default behavior), convert that now. - if (this % scatt_type == ANGLE_LEGENDRE .and. enable_leg_mu) then - - ! Convert input parameters to what we need for the rest. - this % scatt_type = ANGLE_TABULAR - order_dim = legendre_mu_points - order = order_dim - dmu = TWO / real(order - 1,8) - - allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - do gin = 1, groups - do gout = 1, groups - norm = ZERO - do imu = 1, order_dim - if (imu == 1) then - mu = -ONE - else if (imu == order_dim) then - mu = ONE - else - mu = -ONE + real(imu - 1,8) * dmu - end if - scatt_coeffs(imu,gout,gin,iazi,ipol) = & - evaluate_legendre(temp_scatt(gout,gin,:,iazi,ipol),mu) - ! Ensure positivity of distribution - if (scatt_coeffs(imu,gout,gin,iazi,ipol) < ZERO) & - scatt_coeffs(imu,gout,gin,iazi,ipol) = ZERO - ! And accrue the integral - if (imu > 1) then - norm = norm + HALF * dmu * & - (scatt_coeffs(imu-1,gout,gin,iazi,ipol) + & - scatt_coeffs(imu,gout,gin,iazi,ipol)) - end if - end do - ! Now that we have the integral, lets ensure that the distribution - ! is normalized such that it preserves the original scattering xs - if (norm > ZERO) then - scatt_coeffs(:,gout,gin,iazi,ipol) = & - scatt_coeffs(:,gout,gin,iazi,ipol) * & - temp_scatt(gout,gin,1,iazi,ipol) / norm - end if - end do - end do - end do - end do - else - ! Sticking with current representation, carry forward but change - ! the array ordering - allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - do gin = 1, groups - do gout = 1, groups - do l = 1, order_dim - scatt_coeffs(l,gout,gin,iazi,ipol) = & - temp_scatt(gout,gin,l,iazi,ipol) - end do - end do - end do - end do - end do - end if - deallocate(temp_scatt) - else - call fatal_error("Must provide scatter!") - end if - - allocate(this % scatter(this % n_azi, this % n_pol)) - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - ! Allocate and initialize our ScattData Object. - if (this % scatt_type == ANGLE_HISTOGRAM) then - allocate(ScattDataHistogram :: this % scatter(iazi,ipol) % obj) - else if (this % scatt_type == ANGLE_TABULAR) then - allocate(ScattDataTabular :: this % scatter(iazi,ipol) % obj) - else if (this % scatt_type == ANGLE_LEGENDRE) then - allocate(ScattDataLegendre :: this % scatter(iazi,ipol) % obj) - end if - - ! Initialize the ScattData Object - call this % scatter(iazi,ipol) % obj % init(& - temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) - end do - end do - ! Deallocate temporaries for the next material - deallocate(input_scatt,scatt_coeffs,temp_mult) - - allocate(this % total(groups,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"total")) then - allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"total",temp_arr) - this % total = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) - deallocate(temp_arr) - else - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - this % total(:,iazi,ipol) = this % absorption(:,iazi,ipol) + & - this % scatter(iazi,ipol) % obj % scattxs(:) - end do - end do - end if - - end subroutine nuclideangle_init - -!=============================================================================== -! NUCLIDECE_CLEAR resets and deallocates data in Nuclide, NuclideIso +! NUCLIDE_CLEAR resets and deallocates data in Nuclide, NuclideIso ! or NuclideAngle !=============================================================================== - subroutine nuclidece_clear(this) + subroutine nuclide_clear(this) - class(NuclideCE), intent(inout) :: this ! The Nuclide object to clear + class(Nuclide), intent(inout) :: this ! The Nuclide object to clear integer :: i ! Loop counter @@ -959,15 +184,15 @@ module nuclide_header call this % reaction_index % clear() - end subroutine nuclidece_clear + end subroutine nuclide_clear !=============================================================================== -! NUCLIDE*_PRINT displays information about a continuous-energy neutron +! NUCLIDE_PRINT displays information about a continuous-energy neutron ! cross_section table and its reactions and secondary angle/energy distributions !=============================================================================== - subroutine nuclidece_print(this, unit) - class(NuclideCE), intent(in) :: this + subroutine nuclide_print(this, unit) + class(Nuclide), intent(in) :: this integer, intent(in), optional :: unit integer :: i ! loop index over nuclides @@ -1040,298 +265,6 @@ module nuclide_header ! Blank line at end of nuclide write(unit_,*) - end subroutine nuclidece_print - - subroutine nuclidemg_print(this, unit_) - class(NuclideMG), intent(in) :: this - integer, intent(in) :: unit_ - - character(MAX_LINE_LEN) :: temp_str - - ! Basic nuclide information - write(unit_,*) 'Nuclide ' // trim(this % name) - if (this % zaid > 0) then - ! Dont print if data was macroscopic and thus zaid & AWR would be nonsense - write(unit_,*) ' zaid = ' // trim(to_str(this % zaid)) - write(unit_,*) ' awr = ' // trim(to_str(this % awr)) - end if - write(unit_,*) ' kT = ' // trim(to_str(this % kT)) - if (this % scatt_type == ANGLE_LEGENDRE) then - temp_str = "Legendre" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (NuclideIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1) - end select - write(unit_,*) ' Scattering Order = ' // trim(temp_str) - else if (this % scatt_type == ANGLE_HISTOGRAM) then - temp_str = "Histogram" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (NuclideIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) - end select - write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) - else if (this % scatt_type == ANGLE_TABULAR) then - temp_str = "Tabular" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (NuclideIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) - end select - write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) - end if - write(unit_,*) ' Fissionable = ', this % fissionable - - end subroutine nuclidemg_print - - subroutine nuclideiso_print(this, unit) - - class(NuclideIso), intent(in) :: this - integer, optional, intent(in) :: unit - - integer :: unit_ ! unit to write to - integer :: size_total, size_scattmat, size_mgxs - integer :: gin - - ! set default unit for writing information - if (present(unit)) then - unit_ = unit - else - unit_ = OUTPUT_UNIT - end if - - ! Write Basic Nuclide Information - call nuclidemg_print(this, unit_) - - ! Determine size of mgxs and scattering matrices - size_scattmat = 0 - do gin = 1, size(this % scatter % energy) - size_scattmat = size_scattmat + & - 2 * size(this % scatter % energy(gin) % data) + & - size(this % scatter % dist(gin) % data) - end do - size_scattmat = size_scattmat + size(this % scatter % scattxs) - size_scattmat = size_scattmat * 8 - - size_mgxs = size(this % total) + size(this % absorption) + & - size(this % nu_fission) + size(this % k_fission) + & - size(this % fission) + size(this % chi) - size_mgxs = size_mgxs * 8 - - ! Calculate total memory - size_total = size_scattmat + size_mgxs - - ! Write memory used - write(unit_,*) ' Memory Requirements' - write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' - write(unit_,*) ' Scattering Matrices = ' // & - trim(to_str(size_scattmat)) // ' bytes' - write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' - - ! Blank line at end of nuclide - write(unit_,*) - - end subroutine nuclideiso_print - - subroutine nuclideangle_print(this, unit) - - class(NuclideAngle), intent(in) :: this - integer, optional, intent(in) :: unit - - integer :: unit_ ! unit to write to - integer :: size_total, size_scattmat, size_mgxs - integer :: ipol, iazi, gin - - ! set default unit for writing information - if (present(unit)) then - unit_ = unit - else - unit_ = OUTPUT_UNIT - end if - - ! Write Basic Nuclide Information - call nuclidemg_print(this, unit_) - write(unit_,*) ' # of Polar Angles = ' // trim(to_str(this % n_pol)) - write(unit_,*) ' # of Azimuthal Angles = ' // trim(to_str(this % n_azi)) - - ! Determine size of mgxs and scattering matrices - size_scattmat = 0 - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - do gin = 1, size(this % scatter(iazi,ipol) % obj % energy) - size_scattmat = size_scattmat + & - 2 * size(this % scatter(iazi,ipol) % obj % energy(gin) % data) + & - size(this % scatter(iazi,ipol) % obj % dist(gin) % data) - end do - size_scattmat = size_scattmat + & - size(this % scatter(iazi,ipol) % obj % scattxs) - end do - end do - size_scattmat = size_scattmat * 8 - - size_scattmat = (size(this % scatter) + size(this % mult)) * 8 - size_mgxs = size(this % total) + size(this % absorption) + & - size(this % nu_fission) + size(this % k_fission) + & - size(this % fission) + size(this % chi) - size_mgxs = size_mgxs * 8 - - ! Calculate total memory - size_total = size_scattmat + size_mgxs - - ! Write memory used - write(unit_,*) ' Memory Requirements' - write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' - write(unit_,*) ' Scattering Matrices = ' // & - trim(to_str(size_scattmat)) // ' bytes' - write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' - - ! Blank line at end of nuclide - write(unit_,*) - - - end subroutine nuclideangle_print - -!=============================================================================== -! NUCLIDE*_GET_XS Returns the requested data type -!=============================================================================== - - function nuclideiso_get_xs(this, xstype, gin, gout, uvw, mu, iazi, ipol) & - result(xs) - class(NuclideIso), intent(in) :: this - character(*), intent(in) :: xstype ! Cross Section Type - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index - real(8) :: xs ! Resultant xs - - xs = ZERO - - if ((xstype == 'nu_fission' .or. xstype == 'fission' .or. xstype =='chi' & - .or. xstype =='kappa_fission') .and. (.not. this % fissionable)) then - return - end if - - if (present(gout)) then - select case(xstype) - case('mult') - xs = this % scatter % mult(gin) % data(gout) - case('nu_fission') - xs = this % nu_fission(gout,gin) - case('f_mu', 'f_mu/mult') - if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then - xs = ZERO - else - xs = this % scatter % calc_f(gin, gout, mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter % mult(gin) % data(gout) - end if - end if - end select - else - select case(xstype) - case('total') - xs = this % total(gin) - case('absorption') - xs = this % absorption(gin) - case('nu_fission') - xs = sum(this % nu_fission(:,gin)) - case('fission') - xs = this % fission(gin) - case('kappa_fission') - if (allocated(this % k_fission)) then - xs = this % k_fission(gin) - end if - case('chi') - xs = this % chi(gin) - case('scatter') - xs = this % scatter % scattxs(gin) - case('mult') - xs = dot_product(this % scatter % mult(gin) % data, & - this % scatter % scattxs(gin) * & - this % scatter % energy(gin) % data) - xs = xs / this % scatter % scattxs(gin) - end select - end if - end function nuclideiso_get_xs - - function nuclideangle_get_xs(this, xstype, gin, gout, uvw, mu, iazi, ipol) & - result(xs) - class(NuclideAngle), intent(in) :: this - character(*), intent(in) :: xstype ! Cross Section Type - integer, intent(in) :: gin ! Incoming Energy group - integer, optional, intent(in) :: gout ! Outgoing Group - real(8), optional, intent(in) :: uvw(3) ! Requested Angle - real(8), optional, intent(in) :: mu ! Change in angle - integer, optional, intent(in) :: iazi ! Azimuthal Index - integer, optional, intent(in) :: ipol ! Polar Index - real(8) :: xs ! Resultant xs - - integer :: iazi_, ipol_ - - xs = ZERO - - if ((xstype == 'nu_fission' .or. xstype == 'fission' .or. xstype =='chi' & - .or. xstype =='kappa_fission') .and. (.not. this % fissionable)) then - return - end if - - if (present(iazi) .and. present(ipol)) then - iazi_ = iazi - ipol_ = ipol - else - call find_angle(this % polar, this % azimuthal, uvw, iazi_, ipol_) - end if - - if (present(gout)) then - select case(xstype) - case('mult') - xs = this % scatter(iazi_,ipol_) % obj % mult(gin) % data(gout) - case('nu_fission') - xs = this % nu_fission(gout,gin,iazi_,ipol_) - case('chi') - xs = this % chi(gout,iazi_,ipol_) - case('f_mu', 'f_mu/mult') - if (gout < this % scatter(iazi_,ipol_) % obj % gmin(gin) .or. & - gout > this % scatter(iazi_,ipol_) % obj % gmax(gin)) then - xs = ZERO - else - xs = this % scatter(iazi_,ipol_) % obj % calc_f(gin,gout,mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter(iazi_,ipol_) % obj % mult(gin) % data(gout) - end if - end if - end select - else - select case(xstype) - case('total') - xs = this % total(gin,iazi_,ipol_) - case('absorption') - xs = this % absorption(gin,iazi_,ipol_) - case('nu_fission') - xs = sum(this % nu_fission(:,gin,iazi_,ipol_)) - case('fission') - xs = this % fission(gin,iazi_,ipol_) - case('kappa_fission') - if (allocated(this % k_fission)) then - xs = this % k_fission(gin,iazi_,ipol_) - end if - case('chi') - xs = this % chi(gin,iazi_,ipol_) - case('scatter') - xs = this % scatter(iazi_,ipol_) % obj % scattxs(gin) - case('mult') - xs = dot_product(this % scatter(iazi_,ipol_) % obj % mult(gin) % data, & - this % scatter(iazi_,ipol_) % obj % scattxs(gin) * & - this % scatter(iazi_,ipol_) % obj % energy(gin) % data) - xs = xs / this % scatter(iazi_,ipol_) % obj % scattxs(gin) - end select - end if - - end function nuclideangle_get_xs + end subroutine nuclide_print end module nuclide_header diff --git a/src/output.F90 b/src/output.F90 index 768f19775..1b4145800 100644 --- a/src/output.F90 +++ b/src/output.F90 @@ -336,10 +336,10 @@ contains ! Open log file for writing open(NEWUNIT=unit_xs, FILE=path, STATUS='replace', ACTION='write') - ! Write header - call header("CROSS SECTION TABLES", unit=unit_xs) - if (run_CE) then + ! Write header + call header("CROSS SECTION TABLES", unit=unit_xs) + NUCLIDE_LOOP: do i = 1, n_nuclides_total ! Print information about nuclide call nuclides(i) % print(unit=unit_xs) @@ -350,10 +350,17 @@ contains call sab_tables(i) % print(unit=unit_xs) end do SAB_TABLES_LOOP else + ! Write header + call header("MGXS LIBRARY TABLES", unit=unit_xs) NuclideMG_LOOP: do i = 1, n_nuclides_total ! Print information about nuclide call nuclides_mg(i) % obj % print(unit=unit_xs) end do NuclideMG_LOOP + call header("MATERIAL MGXS TABLES", unit=unit_xs) + MATERIAL_LOOP: do i = 1, n_materials + ! Print information about Materials + call macro_xs(i) % obj % print(unit=unit_xs) + end do MATERIAL_LOOP end if ! Close cross section summary file diff --git a/src/physics.F90 b/src/physics.F90 index 6fda4c393..38d73348a 100644 --- a/src/physics.F90 +++ b/src/physics.F90 @@ -82,7 +82,7 @@ contains integer :: i_nuclide ! index in nuclides array integer :: i_nuc_mat ! index in material's nuclides array integer :: i_reaction ! index in nuc % reactions array - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc call sample_nuclide(p, 'total ', i_nuclide, i_nuc_mat) @@ -205,7 +205,7 @@ contains real(8) :: f real(8) :: prob real(8) :: cutoff - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc ! Get pointer to nuclide nuc => nuclides(i_nuclide) @@ -303,7 +303,7 @@ contains real(8) :: uvw_new(3) ! outgoing uvw for iso-in-lab scattering real(8) :: uvw_old(3) ! incoming uvw for iso-in-lab scattering real(8) :: phi ! azimuthal angle for iso-in-lab scattering - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc ! copy incoming direction uvw_old(:) = p % coord(1) % uvw @@ -418,7 +418,7 @@ contains real(8) :: v_cm(3) ! velocity of center-of-mass real(8) :: v_t(3) ! velocity of target nucleus real(8) :: uvw_cm(3) ! directional cosines in center-of-mass - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc ! get pointer to nuclide nuc => nuclides(i_nuclide) @@ -744,7 +744,7 @@ contains !=============================================================================== subroutine sample_target_velocity(nuc, v_target, E, uvw, v_neut, wgt, xs_eff) - type(NuclideCE), intent(in) :: nuc ! target nuclide at temperature T + type(Nuclide), intent(in) :: nuc ! target nuclide at temperature T real(8), intent(out) :: v_target(3) ! target velocity real(8), intent(in) :: v_neut(3) ! neutron velocity real(8), intent(in) :: E ! particle energy @@ -989,7 +989,7 @@ contains !=============================================================================== subroutine sample_cxs_target_velocity(nuc, v_target, E, uvw) - type(NuclideCE), intent(in) :: nuc ! target nuclide at temperature + type(Nuclide), intent(in) :: nuc ! target nuclide at temperature real(8), intent(out) :: v_target(3) real(8), intent(in) :: E real(8), intent(in) :: uvw(3) @@ -1077,7 +1077,7 @@ contains real(8) :: phi ! fission neutron azimuthal angle real(8) :: weight ! weight adjustment for ufs method logical :: in_mesh ! source site in ufs mesh? - type(NuclideCE), pointer :: nuc + type(Nuclide), pointer :: nuc ! Get pointers nuc => nuclides(i_nuclide) @@ -1187,7 +1187,7 @@ contains function sample_fission_energy(nuc, rxn, p) result(E_out) - type(NuclideCE), intent(in) :: nuc + type(Nuclide), intent(in) :: nuc type(Reaction), intent(in) :: rxn type(Particle), intent(inout) :: p ! Particle causing fission real(8) :: E_out ! outgoing energy of fission neutron @@ -1300,7 +1300,7 @@ contains !=============================================================================== subroutine inelastic_scatter(nuc, rxn, p) - type(NuclideCE), intent(in) :: nuc + type(Nuclide), intent(in) :: nuc type(Reaction), intent(in) :: rxn type(Particle), intent(inout) :: p diff --git a/src/physics_mg.F90 b/src/physics_mg.F90 index 209808dc9..a72b3878d 100644 --- a/src/physics_mg.F90 +++ b/src/physics_mg.F90 @@ -5,9 +5,9 @@ module physics_mg use constants use error, only: fatal_error, warning use global - use macroxs_header, only: MacroXS, MacroXSContainer use material_header, only: Material use math, only: rotate_angle + use mgxs_header, only: Mgxs, MgxsContainer use mesh, only: get_mesh_indices use output, only: write_message use particle_header, only: Particle @@ -179,7 +179,7 @@ contains real(8) :: phi ! fission neutron azimuthal angle real(8) :: weight ! weight adjustment for ufs method logical :: in_mesh ! source site in ufs mesh? - class(MacroXS), pointer :: xs + class(Mgxs), pointer :: xs ! Get Pointers xs => macro_xs(p % material) % obj diff --git a/src/tracking.F90 b/src/tracking.F90 index e634112bc..dc9497389 100644 --- a/src/tracking.F90 +++ b/src/tracking.F90 @@ -7,7 +7,6 @@ module tracking cross_lattice, check_cell_overlap use geometry_header, only: Universe, BASE_UNIVERSE use global - use macroxs_header, only: MacroXS use output, only: write_message use particle_header, only: LocalCoord, Particle use physics, only: collision From ed6a91753daaa8dbe30c40105443ac900192cb2e Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Mon, 14 Mar 2016 20:53:48 -0400 Subject: [PATCH 019/147] Finished tallying code, i hope, cleaned up some code --- src/mgxs_data.F90 | 23 +---- src/mgxs_header.F90 | 66 ++++++------ src/particle_header.F90 | 2 +- src/tally.F90 | 223 ++++++++++++++++++++-------------------- src/tracking.F90 | 1 + 5 files changed, 153 insertions(+), 162 deletions(-) diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index 283024e29..def214d67 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -70,7 +70,8 @@ contains if (tallies(i) % score_bins(l) == SCORE_KAPPA_FISSION) then get_kfiss = .true. end if - if (tallies(i) % score_bins(l) == SCORE_FISSION) then + if (tallies(i) % score_bins(l) == SCORE_FISSION .or. & + tallies(i) % score_bins(l) == SCORE_NU_FISSION) then get_fiss = .true. end if end do @@ -166,26 +167,8 @@ contains integer :: i ! loop index over nuclides integer :: l ! Loop over score bins type(Material), pointer :: mat ! current material - logical :: get_kfiss, get_fiss integer :: scatt_type - ! Find out if we need fission & kappa fission - ! (i.e., are there any SCORE_FISSION or SCORE_KAPPA_FISSION tallies?) - get_kfiss = .false. - get_fiss = .false. - do i = 1, n_tallies - do l = 1, tallies(i) % n_score_bins - if (tallies(i) % score_bins(l) == SCORE_KAPPA_FISSION) then - get_kfiss = .true. - end if - if (tallies(i) % score_bins(l) == SCORE_FISSION) then - get_fiss = .true. - end if - end do - if (get_kfiss .and. get_fiss) & - exit - end do - allocate(macro_xs(n_materials)) do i_mat = 1, n_materials @@ -204,7 +187,7 @@ contains allocate(MgxsAngle :: macro_xs(i_mat) % obj) end select call macro_xs(i_mat) % obj % combine(mat,nuclides_MG,energy_groups, & - get_kfiss,get_fiss,max_order,scatt_type,i_mat) + max_order,scatt_type,i_mat) end do end subroutine create_macro_xs diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index c87b37ce2..908f19c8b 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -96,15 +96,13 @@ module mgxs_header end function mgxs_calc_f_ - subroutine mgxs_combine_(this,mat,nuclides,groups,get_kfiss,get_fiss, & - max_order,scatt_type,i_listing) + subroutine mgxs_combine_(this,mat,nuclides,groups,max_order,scatt_type, & + i_listing) import Mgxs, Material, MgxsContainer class(Mgxs), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? integer, intent(in) :: i_listing ! Index in listings @@ -529,6 +527,13 @@ module mgxs_header ! Initialize the ScattData Object call this % scatter % init(temp_mult, scatt_coeffs) + ! Check sigA to ensure it is not 0 since it is + ! often divided by in the tally routines + ! (This may happen with Helium data) + do gin = 1, groups + if (this % absorption(gin) == ZERO) this % absorption(gin) = 1E-10_8 + end do + ! Get, or infer, total xs data. allocate(this % total(groups)) if (check_for_node(node_xsdata,"total")) then @@ -540,6 +545,13 @@ module mgxs_header ! Deallocate temporaries for the next material deallocate(input_scatt,scatt_coeffs,temp_mult) + ! Finally, check sigT to ensure it is not 0 since it is + ! often divided by in the tally routines + do gin = 1, groups + if (this % total(gin) == ZERO) this % total(gin) = 1E-10_8 + end do + + end subroutine mgxsiso_init_file subroutine mgxsang_init_file(this,node_xsdata,groups,get_kfiss,get_fiss, & @@ -1288,14 +1300,12 @@ module mgxs_header end subroutine mgxs_combine - subroutine mgxsiso_combine(this,mat,nuclides,groups,get_kfiss,get_fiss, & - max_order,scatt_type,i_listing) + subroutine mgxsiso_combine(this,mat,nuclides,groups,max_order,scatt_type, & + i_listing) class(MgxsIso), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! How is data presented integer, intent(in) :: i_listing ! Index in listings @@ -1377,14 +1387,10 @@ module mgxs_header this % total = ZERO allocate(this % absorption(groups)) this % absorption = ZERO - if (get_fiss) then - allocate(this % fission(groups)) - this % fission = ZERO - end if - if (get_kfiss) then - allocate(this % k_fission(groups)) - this % k_fission = ZERO - end if + allocate(this % fission(groups)) + this % fission = ZERO + allocate(this % k_fission(groups)) + this % k_fission = ZERO allocate(this % nu_fission(groups)) this % nu_fission = ZERO allocate(this % chi(groups,groups)) @@ -1410,10 +1416,10 @@ module mgxs_header this % chi = this % chi + atom_density * nuc % chi this % nu_fission = this % nu_fission + atom_density * & nuc % nu_fission - if (get_fiss) then + if (allocated(nuc % fission)) then this % fission = this % fission + atom_density * nuc % fission end if - if (get_kfiss) then + if (allocated(nuc % k_fission)) then this % k_fission = this % k_fission + atom_density * nuc % k_fission end if end if @@ -1456,14 +1462,12 @@ module mgxs_header end subroutine mgxsiso_combine - subroutine mgxsang_combine(this,mat,nuclides,groups,get_kfiss,get_fiss, & - max_order,scatt_type,i_listing) + subroutine mgxsang_combine(this,mat,nuclides,groups,max_order,scatt_type,& + i_listing) class(MgxsAngle), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material type(MgxsContainer), intent(in) :: nuclides(:) ! List of nuclides to harvest from integer, intent(in) :: groups ! Number of E groups - logical, intent(in) :: get_kfiss ! Should we get kfiss data? - logical, intent(in) :: get_fiss ! Should we get fiss data? integer, intent(in) :: max_order ! Maximum requested order integer, intent(in) :: scatt_type ! Legendre or Tabular Scatt? integer, intent(in) :: i_listing ! Index in listings @@ -1583,14 +1587,10 @@ module mgxs_header this % total = ZERO allocate(this % absorption(groups,n_azi,n_pol)) this % absorption = ZERO - if (get_fiss) then - allocate(this % fission(groups,n_azi,n_pol)) - this % fission = ZERO - end if - if (get_kfiss) then - allocate(this % k_fission(groups,n_azi,n_pol)) - this % k_fission = ZERO - end if + allocate(this % fission(groups,n_azi,n_pol)) + this % fission = ZERO + allocate(this % k_fission(groups,n_azi,n_pol)) + this % k_fission = ZERO allocate(this % nu_fission(groups,n_azi,n_pol)) this % nu_fission = ZERO allocate(this % chi(groups,groups,n_azi,n_pol)) @@ -1618,10 +1618,10 @@ module mgxs_header this % chi = this % chi + atom_density * nuc % chi this % nu_fission = this % nu_fission + atom_density * & nuc % nu_fission - if (get_fiss) then + if (allocated(nuc % fission)) then this % fission = this % fission + atom_density * nuc % fission end if - if (get_kfiss) then + if (allocated(nuc % k_fission)) then this % k_fission = this % k_fission + atom_density * nuc % k_fission end if end if @@ -1771,6 +1771,7 @@ module mgxs_header xs % total = this % total(gin) xs % elastic = this % scatter % scattxs(gin) xs % absorption = this % absorption(gin) + xs % fission = this % fission(gin) xs % nu_fission = this % nu_fission(gin) end subroutine mgxsiso_calculate_xs @@ -1787,6 +1788,7 @@ module mgxs_header xs % total = this % total(gin,iazi,ipol) xs % elastic = this % scatter(iazi,ipol) % obj % scattxs(gin) xs % absorption = this % absorption(gin,iazi,ipol) + xs % fission = this % fission(gin,iazi,ipol) xs % nu_fission = this % nu_fission(gin,iazi,ipol) end subroutine mgxsang_calculate_xs diff --git a/src/particle_header.F90 b/src/particle_header.F90 index 8544cb38b..6b2972768 100644 --- a/src/particle_header.F90 +++ b/src/particle_header.F90 @@ -232,7 +232,7 @@ contains this % n_secondary = n this % secondary_bank(this % n_secondary) % E = this % E if (.not. run_CE) then - this % secondary_bank(this % n_secondary) % E = real(this % g, 8) + this % secondary_bank(this % n_secondary) % E = real(this % g,8) end if end subroutine create_secondary diff --git a/src/tally.F90 b/src/tally.F90 index d23cd8691..a69af2260 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -810,10 +810,9 @@ contains integer :: score_bin ! scoring bin, e.g. SCORE_FLUX integer :: score_index ! scoring bin index real(8) :: score ! analog tally score - real(8) :: macro_total ! material macro total xs - real(8) :: macro_scatt ! material macro scatt xs - real(8) :: micro_abs ! nuclidic microscopic abs real(8) :: p_uvw(3) ! Particle's current uvw + class(Mgxs), pointer :: matxs + class(Mgxs), pointer :: nucxs ! Set the direction to use with get_xs if (t % estimator == ESTIMATOR_ANALOG) then @@ -822,6 +821,14 @@ contains p_uvw = p % coord(p % n_coord) % uvw end if + ! To significantly reduce de-referencing, point matxs to the + ! macroscopic Mgxs for the material of interest + matxs => macro_xs(p % material) % obj + ! Do same for nucxs, point it to the microscopic nuclide data of interest + if (i_nuclide > 0) then + nucxs => nuclides_MG(i_nuclide) % obj + end if + i = 0 SCORE_LOOP: do q = 1, t % n_user_score_bins i = i + 1 @@ -867,16 +874,23 @@ contains ! We need to account for the fact that some weight was already ! absorbed score = p % last_wgt + p % absorb_wgt + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('total',p % last_g,UVW=p_uvw) / & + matxs % get_xs('total',p % last_g,UVW=p_uvw) + end if else score = p % last_wgt + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('total',p % g,UVW=p_uvw) / & + matxs % get_xs('total',p % g,UVW=p_uvw) + end if end if else if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('total',p % g,UVW=p_uvw) * & - atom_density * flux - end associate + score = nucxs % get_xs('total',p % g,UVW=p_uvw) * atom_density * flux else score = material_xs % total * flux end if @@ -921,28 +935,22 @@ contains score = p % last_wgt if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu',p % last_g,p % g, & - UVW=p_uvw,MU=p % mu) / & - macro_xs(p % material) % obj % get_xs('f_mu',p % last_g, & - p % g, UVW=p_uvw, & - MU=p % mu) - end associate + score = score * atom_density * & + nucxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & + matxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) end if else ! Note SCORE_SCATTER_N not available for tracklength/collision. if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('scatter',p % g,UVW=p_uvw) * & - atom_density * flux / & - nuc % get_xs('mult',p % g,UVW=p_uvw) - end associate + score = nucxs % get_xs('scatter',p % g,UVW=p_uvw) * & + atom_density * flux / & + nucxs % get_xs('mult',p % g,UVW=p_uvw) else ! Get the scattering x/s (stored in % elastic) and take away ! the multiplication baked in to sigS score = material_xs % elastic * flux / & - macro_xs(p % material) % obj % get_xs('mult',p % g,UVW=p_uvw) + matxs % get_xs('mult',p % g,UVW=p_uvw) end if end if @@ -966,22 +974,16 @@ contains score = p % wgt if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = score * nuc % get_xs('f_mu',p % last_g,p % g, & - UVW=p_uvw,MU=p % mu) / & - macro_xs(p % material) % obj % get_xs('f_mu',p % last_g, & - p % g, UVW=p_uvw, & - MU=p % mu) - end associate + score = score * atom_density * & + nucxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & + matxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) end if else ! Note SCORE_NU_SCATTER_* not available for tracklength/collision. if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('scatter',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('scatter',p % g,UVW=p_uvw) * & atom_density * flux - end associate else ! Get the scattering x/s (stored in % elastic) and take away ! the multiplication baked in to sigS @@ -994,14 +996,14 @@ contains ! Only analog estimators are available. ! Skip any event where the particle didn't scatter if (p % event /= EVENT_SCATTER) cycle SCORE_LOOP - ! get material macros - macro_total = material_xs % total - macro_scatt = material_xs % elastic ! Score total rate - p1 scatter rate Note estimator needs to be ! adjusted since tallying is only occuring when a scatter has ! happened. Effectively this means multiplying the estimator by ! total/scatter macro - score = (macro_total - p % mu * macro_scatt) * (ONE / macro_scatt) + score = (material_xs % total - p % mu * material_xs % elastic) + if (material_xs % elastic /= ZERO) then + score = score / material_xs % elastic + end if case (SCORE_ABSORPTION) @@ -1010,20 +1012,28 @@ contains ! No absorption events actually occur if survival biasing is on -- ! just use weight absorbed in survival biasing score = p % absorb_wgt + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('absorption',p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + end if else ! Skip any event where the particle wasn't absorbed if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission and absorption events will contribute here, so we ! can just use the particle's weight entering the collision score = p % last_wgt + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('absorption',p % g,UVW=p_uvw) / & + material_xs % absorption + end if end if else if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('absorption',p % g,UVW=p_uvw) & - * atom_density * flux - end associate + score = nucxs % get_xs('absorption',p % g,UVW=p_uvw) * & + atom_density * flux else score = material_xs % absorption * flux end if @@ -1036,15 +1046,15 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! fission - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('fission',p % g,UVW=p_uvw) / micro_abs - else - score = ZERO - end if - end associate + if (i_nuclide > 0) then + score = p % absorb_wgt * atom_density * & + nucxs % get_xs('fission', p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + else + score = p % absorb_wgt * & + matxs % get_xs('fission', p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + end if else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP @@ -1052,32 +1062,22 @@ contains ! particle's weight entering the collision as the estimate for the ! fission reaction rate if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = p % last_wgt * & - nuc % get_xs('fission',p % g,UVW=p_uvw) * & - atom_density / & - macro_xs(p % material) % obj % get_xs('absorption',& - p % g,UVW=p_uvw) - end associate + score = p % last_wgt * atom_density * & + nucxs % get_xs('fission', p % g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % g,UVW=p_uvw) else score = p % last_wgt * & - macro_xs(p % material) % obj % get_xs('fission', & - p % g,UVW=p_uvw) * & - atom_density / & - macro_xs(p % material) % obj % get_xs('absorption', & - p % g,UVW=p_uvw) + matxs % get_xs('fission', p % g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % g,UVW=p_uvw) end if end if else if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('fission',p % g,UVW=p_uvw) * & - atom_density * flux - end associate + score = nucxs % get_xs('fission',p % g,UVW=p_uvw) * & + atom_density * flux else - score = flux * macro_xs(p % material) % obj % get_xs('fission', & - p % g,UVW=p_uvw) + score = flux * material_xs % fission end if end if @@ -1092,7 +1092,7 @@ contains ! neutrons were emitted with different energies, multiple ! outgoing energy bins may have been scored to. The following ! logic treats this special case and results to multiple bins - call score_fission_eout_mg(p, t, score_index) + call score_fission_eout_mg(p,t,score_index,i_nuclide,atom_density) cycle SCORE_LOOP end if end if @@ -1101,15 +1101,13 @@ contains ! calculate fraction of absorptions that would have resulted in ! nu-fission if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('nu_fission',p % g,UVW=p_uvw) / micro_abs - else - score = ZERO - end if - end associate + score = p % absorb_wgt * atom_density * & + nucxs % get_xs('nu_fission',p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + else + score = p % absorb_wgt * & + matxs % get_xs('nu_fission',p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) end if else ! Skip any non-fission events @@ -1120,14 +1118,17 @@ contains ! bank. Since this was weighted by 1/keff, we multiply by keff ! to get the proper score. score = keff * p % wgt_bank + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('fission',p % g,UVW=p_uvw) / & + matxs % get_xs('fission',p % g,UVW=p_uvw) + end if end if else if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('nu_fission',p % g,UVW=p_uvw) * & - atom_density * flux - end associate + score = nucxs % get_xs('nu_fission',p % g,UVW=p_uvw) * & + atom_density * flux else score = material_xs % nu_fission * flux end if @@ -1140,15 +1141,15 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! fission - associate (nuc => nuclides_MG(i_nuclide) % obj) - micro_abs = nuc % get_xs('absorption',p % g,UVW=p_uvw) - if (micro_abs > ZERO) then - score = p % absorb_wgt * & - nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) / micro_abs - else - score = ZERO - end if - end associate + if (i_nuclide > 0) then + score = p % absorb_wgt * atom_density * & + nucxs % get_xs('kappa_fission',p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + else + score = p % absorb_wgt * & + matxs % get_xs('kappa_fission',p % last_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + end if else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP @@ -1156,32 +1157,22 @@ contains ! particle's weight entering the collision as the estimate for the ! fission reaction rate if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = p % last_wgt * & - nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) * & - atom_density / & - macro_xs(p % material) % obj % get_xs('absorption',& - p % g,UVW=p_uvw) - end associate + score = p % last_wgt * & + nucxs % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + atom_density / material_xs % absorption else score = p % last_wgt * & - macro_xs(p % material) % obj % get_xs('kappa_fission', & - p % g,UVW=p_uvw) * & - atom_density / & - macro_xs(p % material) % obj % get_xs('absorption', & - p % g,UVW=p_uvw) + matxs % get_xs('kappa_fission',p % g,UVW=p_uvw) / & + material_xs % absorption end if end if else if (i_nuclide > 0) then - associate (nuc => nuclides_MG(i_nuclide) % obj) - score = nuc % get_xs('kappa_fission',p % g,UVW=p_uvw) * & - atom_density * flux - end associate + score = flux * nucxs % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + atom_density else - score = flux * macro_xs(p % material) % obj % get_xs('kappa_fission', & - p % g,UVW=p_uvw) + score = flux * matxs % get_xs('kappa_fission',p % g,UVW=p_uvw) end if end if @@ -1199,6 +1190,8 @@ contains score, i) end do SCORE_LOOP + + nullify(matxs,nucxs) end subroutine score_general_mg !=============================================================================== @@ -1607,10 +1600,12 @@ contains end subroutine score_fission_eout_ce - subroutine score_fission_eout_mg(p, t, i_score) + subroutine score_fission_eout_mg(p, t, i_score, i_nuclide, atom_density) type(Particle), intent(in) :: p type(TallyObject), intent(inout) :: t - integer, intent(in) :: i_score ! index for score + integer, intent(in) :: i_score ! index for score + integer, intent(in) :: i_nuclide ! index for nuclide + real(8), intent(in) :: atom_density integer :: i ! index of outgoing energy filter integer :: n ! number of energies on filter @@ -1637,6 +1632,16 @@ contains do k = 1, p % n_bank ! determine score based on bank site weight and keff score = keff * fission_bank(n_bank - p % n_bank + k) % wgt + if (i_nuclide > 0) then + if (survival_biasing) then + gout = p % g + else + gout = p % last_g + end if + score = score * atom_density * & + nuclides_MG(i_nuclide) % obj % get_xs('fission',gout,UVW=p % last_uvw) / & + macro_xs(p % material) % obj % get_xs('fission',gout,UVW=p % last_uvw) + end if if (t % energyout_matches_groups) then ! determine outgoing energy from fission bank @@ -1646,7 +1651,7 @@ contains matching_bins(i) = gout else ! determine outgoing energy from fission bank - E_out = fission_bank(n_bank - p % n_bank + k) % E + E_out = energy_bin_avg(int(fission_bank(n_bank - p % n_bank + k) % E)) ! check if outgoing energy is within specified range on filter if (E_out < t % filters(i) % real_bins(1) .or. & diff --git a/src/tracking.F90 b/src/tracking.F90 index dc9497389..d52b09a75 100644 --- a/src/tracking.F90 +++ b/src/tracking.F90 @@ -97,6 +97,7 @@ contains material_xs % total = ZERO material_xs % elastic = ZERO material_xs % absorption = ZERO + material_xs % fission = ZERO material_xs % nu_fission = ZERO end if end if From dd3a7c670a4113888bfd176659cbcba346539017 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 16 Mar 2016 05:15:52 -0400 Subject: [PATCH 020/147] fixed inverse_velocities determination --- src/input_xml.F90 | 2 +- src/tally.F90 | 7 ++++--- 2 files changed, 5 insertions(+), 4 deletions(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 557cfb670..4a1ebfacf 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -4585,7 +4585,7 @@ contains ! If not given, estimate them by using average energy in group which is ! assumed to be the midpoint do i = 1, energy_groups - inverse_velocities(i) = & + inverse_velocities(i) = ONE / & (sqrt(TWO * energy_bin_avg(i) / (MASS_NEUTRON_MEV)) * & C_LIGHT * 100.0_8) end do diff --git a/src/tally.F90 b/src/tally.F90 index a69af2260..b0c13a28e 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -898,7 +898,8 @@ contains case (SCORE_INVERSE_VELOCITY) - if (t % estimator == ESTIMATOR_ANALOG) then + if (t % estimator == ESTIMATOR_ANALOG .or. & + t % estimator == ESTIMATOR_COLLISION) then ! All events score to an inverse velocity bin. We actually use a ! collision estimator in place of an analog one since there is no way ! to count 'events' exactly for the inverse velocity @@ -909,11 +910,11 @@ contains else score = p % last_wgt end if - score = score * inverse_velocities(p % last_g) + score = score * inverse_velocities(p % last_g) / material_xs % total else ! For inverse velocity, we need no cross section - score = score * inverse_velocities(p % g) + score = flux * inverse_velocities(p % g) end if From de67e61558c4eb43af98a5fea3f27129b29085a9 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 17 Mar 2016 06:58:17 -0400 Subject: [PATCH 021/147] Simplified p % g and p % last_g selection in tallying MG data --- src/tally.F90 | 118 ++++++++++++++++++++++++++++++-------------------- 1 file changed, 72 insertions(+), 46 deletions(-) diff --git a/src/tally.F90 b/src/tally.F90 index b0c13a28e..4d57f44ca 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -811,14 +811,39 @@ contains integer :: score_index ! scoring bin index real(8) :: score ! analog tally score real(8) :: p_uvw(3) ! Particle's current uvw + integer :: p_g ! Particle group to use for getting info + ! to tally with. class(Mgxs), pointer :: matxs class(Mgxs), pointer :: nucxs - ! Set the direction to use with get_xs - if (t % estimator == ESTIMATOR_ANALOG) then - p_uvw = p % last_uvw + ! Set the direction and group to use with get_xs + ! this only depends on if we + if (t % estimator == ESTIMATOR_ANALOG .or. & + t % estimator == ESTIMATOR_COLLISION) then + if (survival_biasing) then + ! Then we either are alive and had a scatter (and so g changed), + ! or are dead and g did not change + if (p % alive) then + p_uvw = p % last_uvw + p_g = p % last_g + else + p_uvw = p % coord(p % n_coord) % uvw + p_g = p % g + end if + else if (p % event == EVENT_SCATTER) then + ! Then the energy group has been changed by the scattering routine + ! meaning gin is now in p % last_g + p_uvw = p % last_uvw + p_g = p % last_g + else + ! No scatter, no change in g. + p_uvw = p % coord(p % n_coord) % uvw + p_g = p % g + end if else + ! No actual collision so g has not changed. p_uvw = p % coord(p % n_coord) % uvw + p_g = p % g end if ! To significantly reduce de-referencing, point matxs to the @@ -876,21 +901,21 @@ contains score = p % last_wgt + p % absorb_wgt if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('total',p % last_g,UVW=p_uvw) / & - matxs % get_xs('total',p % last_g,UVW=p_uvw) + nucxs % get_xs('total',p_g,UVW=p_uvw) / & + matxs % get_xs('total',p_g,UVW=p_uvw) end if else score = p % last_wgt if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('total',p % g,UVW=p_uvw) / & - matxs % get_xs('total',p % g,UVW=p_uvw) + nucxs % get_xs('total',p_g,UVW=p_uvw) / & + matxs % get_xs('total',p_g,UVW=p_uvw) end if end if else if (i_nuclide > 0) then - score = nucxs % get_xs('total',p % g,UVW=p_uvw) * atom_density * flux + score = nucxs % get_xs('total',p_g,UVW=p_uvw) * atom_density * flux else score = material_xs % total * flux end if @@ -910,11 +935,11 @@ contains else score = p % last_wgt end if - score = score * inverse_velocities(p % last_g) / material_xs % total + score = score * inverse_velocities(p_g) / material_xs % total else ! For inverse velocity, we need no cross section - score = flux * inverse_velocities(p % g) + score = flux * inverse_velocities(p_g) end if @@ -944,14 +969,14 @@ contains else ! Note SCORE_SCATTER_N not available for tracklength/collision. if (i_nuclide > 0) then - score = nucxs % get_xs('scatter',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('scatter',p_g,UVW=p_uvw) * & atom_density * flux / & - nucxs % get_xs('mult',p % g,UVW=p_uvw) + nucxs % get_xs('mult',p_g,UVW=p_uvw) else ! Get the scattering x/s (stored in % elastic) and take away ! the multiplication baked in to sigS score = material_xs % elastic * flux / & - matxs % get_xs('mult',p % g,UVW=p_uvw) + matxs % get_xs('mult',p_g,UVW=p_uvw) end if end if @@ -983,7 +1008,7 @@ contains else ! Note SCORE_NU_SCATTER_* not available for tracklength/collision. if (i_nuclide > 0) then - score = nucxs % get_xs('scatter',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('scatter',p_g,UVW=p_uvw) * & atom_density * flux else ! Get the scattering x/s (stored in % elastic) and take away @@ -1015,8 +1040,8 @@ contains score = p % absorb_wgt if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('absorption',p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) end if else ! Skip any event where the particle wasn't absorbed @@ -1026,14 +1051,14 @@ contains score = p % last_wgt if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('absorption',p % g,UVW=p_uvw) / & + nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & material_xs % absorption end if end if else if (i_nuclide > 0) then - score = nucxs % get_xs('absorption',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('absorption',p_g,UVW=p_uvw) * & atom_density * flux else score = material_xs % absorption * flux @@ -1049,12 +1074,12 @@ contains ! fission if (i_nuclide > 0) then score = p % absorb_wgt * atom_density * & - nucxs % get_xs('fission', p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + nucxs % get_xs('fission', p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) else score = p % absorb_wgt * & - matxs % get_xs('fission', p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + matxs % get_xs('fission', p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) end if else ! Skip any non-absorption events @@ -1064,18 +1089,18 @@ contains ! fission reaction rate if (i_nuclide > 0) then score = p % last_wgt * atom_density * & - nucxs % get_xs('fission', p % g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % g,UVW=p_uvw) + nucxs % get_xs('fission', p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) else score = p % last_wgt * & - matxs % get_xs('fission', p % g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % g,UVW=p_uvw) + matxs % get_xs('fission', p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) end if end if else if (i_nuclide > 0) then - score = nucxs % get_xs('fission',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('fission',p_g,UVW=p_uvw) * & atom_density * flux else score = flux * material_xs % fission @@ -1103,12 +1128,12 @@ contains ! nu-fission if (i_nuclide > 0) then score = p % absorb_wgt * atom_density * & - nucxs % get_xs('nu_fission',p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + nucxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) else score = p % absorb_wgt * & - matxs % get_xs('nu_fission',p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + matxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) end if else ! Skip any non-fission events @@ -1121,14 +1146,14 @@ contains score = keff * p % wgt_bank if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('fission',p % g,UVW=p_uvw) / & - matxs % get_xs('fission',p % g,UVW=p_uvw) + nucxs % get_xs('fission',p_g,UVW=p_uvw) / & + matxs % get_xs('fission',p_g,UVW=p_uvw) end if end if else if (i_nuclide > 0) then - score = nucxs % get_xs('nu_fission',p % g,UVW=p_uvw) * & + score = nucxs % get_xs('nu_fission',p_g,UVW=p_uvw) * & atom_density * flux else score = material_xs % nu_fission * flux @@ -1144,12 +1169,12 @@ contains ! fission if (i_nuclide > 0) then score = p % absorb_wgt * atom_density * & - nucxs % get_xs('kappa_fission',p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption', p_g,UVW=p_uvw) else score = p % absorb_wgt * & - matxs % get_xs('kappa_fission',p % last_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p % last_g,UVW=p_uvw) + matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption', p_g,UVW=p_uvw) end if else ! Skip any non-absorption events @@ -1159,21 +1184,21 @@ contains ! fission reaction rate if (i_nuclide > 0) then score = p % last_wgt * & - nucxs % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) * & atom_density / material_xs % absorption else score = p % last_wgt * & - matxs % get_xs('kappa_fission',p % g,UVW=p_uvw) / & + matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & material_xs % absorption end if end if else if (i_nuclide > 0) then - score = flux * nucxs % get_xs('kappa_fission',p % g,UVW=p_uvw) * & + score = flux * nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) * & atom_density else - score = flux * matxs % get_xs('kappa_fission',p % g,UVW=p_uvw) + score = flux * matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) end if end if @@ -1615,6 +1640,7 @@ contains integer :: i_filter ! index for matching filter bin combination real(8) :: score ! actual score integer :: gout ! energy group of fission bank site + integer :: gin ! energy group of incident particle real(8) :: E_out ! save original outgoing energy bin and score index @@ -1635,13 +1661,13 @@ contains score = keff * fission_bank(n_bank - p % n_bank + k) % wgt if (i_nuclide > 0) then if (survival_biasing) then - gout = p % g + gin = p % g else - gout = p % last_g + gin = p % last_g end if score = score * atom_density * & - nuclides_MG(i_nuclide) % obj % get_xs('fission',gout,UVW=p % last_uvw) / & - macro_xs(p % material) % obj % get_xs('fission',gout,UVW=p % last_uvw) + nuclides_MG(i_nuclide) % obj % get_xs('fission',gin,UVW=p % last_uvw) / & + macro_xs(p % material) % obj % get_xs('fission',gin,UVW=p % last_uvw) end if if (t % energyout_matches_groups) then From bc4cf8026783dd96f5e28b9bb1185515a8d7645f Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 19 Mar 2016 12:23:56 -0400 Subject: [PATCH 022/147] Changes to comments in scattering tallying --- src/tally.F90 | 20 ++++++++++---------- 1 file changed, 10 insertions(+), 10 deletions(-) diff --git a/src/tally.F90 b/src/tally.F90 index 4d57f44ca..6aabed39f 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -949,7 +949,7 @@ contains if (p % event /= EVENT_SCATTER) then if (score_bin == SCORE_SCATTER_PN) then i = i + t % moment_order(i) - else + else if (score_bin == SCORE_SCATTER_YN) then i = i + (t % moment_order(i) + 1)**2 - 1 end if cycle SCORE_LOOP @@ -967,15 +967,16 @@ contains end if else - ! Note SCORE_SCATTER_N not available for tracklength/collision. + ! Note SCORE_SCATTER_*N not available for tracklength/collision. if (i_nuclide > 0) then - score = nucxs % get_xs('scatter',p_g,UVW=p_uvw) * & - atom_density * flux / & + score = atom_density * flux * & + nucxs % get_xs('scatter',p_g,UVW=p_uvw) / & nucxs % get_xs('mult',p_g,UVW=p_uvw) else - ! Get the scattering x/s (stored in % elastic) and take away + ! Get the scattering x/s and take away ! the multiplication baked in to sigS - score = material_xs % elastic * flux / & + score = flux * & + matxs % get_xs('scatter',p_g,UVW=p_uvw) / & matxs % get_xs('mult',p_g,UVW=p_uvw) end if end if @@ -1006,14 +1007,13 @@ contains end if else - ! Note SCORE_NU_SCATTER_* not available for tracklength/collision. + ! Note SCORE_NU_SCATTER_*N not available for tracklength/collision. if (i_nuclide > 0) then score = nucxs % get_xs('scatter',p_g,UVW=p_uvw) * & atom_density * flux else - ! Get the scattering x/s (stored in % elastic) and take away - ! the multiplication baked in to sigS - score = material_xs % elastic * flux + ! Get the scattering x/s, which includes multiplication + score = matxs % get_xs('scatter',p_g,UVW=p_uvw) * flux end if end if From b742275ca3b2a394457d2ae03039741533491eb4 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 19 Mar 2016 13:52:10 -0400 Subject: [PATCH 023/147] Fixed scattering tallying issue. Next is some minor optimizations, then calling it good --- src/mgxs_header.F90 | 91 +++++++++++++++++++++++++++++++++++-- src/tally.F90 | 106 ++++++++++++++++++-------------------------- 2 files changed, 129 insertions(+), 68 deletions(-) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 908f19c8b..75ff3e46a 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -1140,8 +1140,13 @@ module mgxs_header end if case('scatter') if (present(gout)) then - xs = this % scatter % scattxs(gin) * & - this % scatter % energy(gin) % data(gout) + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data(gout) + end if else xs = this % scatter % scattxs(gin) end if @@ -1159,6 +1164,22 @@ module mgxs_header this % scatter % energy(gin) % data) xs = xs / this % scatter % scattxs(gin) end if + case('scatter/mult') + if (present(gout)) then + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data(gout) / & + this % scatter % mult(gin) % data(gout) + end if + else + xs = this % scatter % scattxs(gin) * this % scatter % scattxs(gin) / & + (dot_product(this % scatter % mult(gin) % data, & + this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data)) + end if case('f_mu', 'f_mu/mult') if (present(gout) .and. present(mu)) then if (gout < this % scatter % gmin(gin) .or. & @@ -1177,6 +1198,26 @@ module mgxs_header ! user of this code wants the complete 1-outgoing group distribution ! which Im not sure what they would do with that. end if + case('scatter*f_mu/mult','scatter*f_mu') + if (present(gout)) then + if (gout < this % scatter % gmin(gin) .or. & + gout > this % scatter % gmax(gin)) then + xs = ZERO + else + xs = this % scatter % scattxs(gin) * & + this % scatter % energy(gin) % data(gout) * & + this % scatter % calc_f(gin, gout, mu) + if (xstype == 'scatter*f_mu/mult') then + xs = xs / this % scatter % mult(gin) % data(gout) + end if + end if + else + xs = ZERO + ! TODO (Not likely needed) + ! (asking for f_mu without asking for a group or mu would mean the + ! user of this code wants the complete 1-outgoing group distribution + ! which Im not sure what they would do with that. + end if case default xs = ZERO end select @@ -1224,8 +1265,13 @@ module mgxs_header end if case('scatter') if (present(gout)) then - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + end if else xs = this % scatter(iazi,ipol) % obj % scattxs(gin) end if @@ -1243,6 +1289,23 @@ module mgxs_header this % scatter(iazi,ipol) % obj % energy(gin) % data) xs = xs / this % scatter(iazi,ipol) % obj % scattxs(gin) end if + case('scatter/mult') + if (present(gout)) then + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) / & + this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if + else + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % scattxs(gin) / & + (dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & + this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data)) + end if case('f_mu', 'f_mu/mult') if (present(gout) .and. present(mu)) then if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & @@ -1262,6 +1325,26 @@ module mgxs_header ! user of this code wants the complete 1-outgoing group distribution ! which Im not sure what they would do with that. end if + case('scatter*f_mu/mult','scatter*f_mu') + if (present(gout)) then + if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + xs = ZERO + else + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & + this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + xs = xs * this % scatter(iazi,ipol) % obj % calc_f(gin, gout, mu) + if (xstype == 'scatter*f_mu/mult') then + xs = xs / this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + end if + end if + else + xs = ZERO + ! TODO (Not likely needed) + ! (asking for f_mu without asking for a group or mu would mean the + ! user of this code wants the complete 1-outgoing group distribution + ! which Im not sure what they would do with that. + end if case default xs = ZERO end select diff --git a/src/tally.F90 b/src/tally.F90 index 6aabed39f..b0c71f6dc 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -899,18 +899,13 @@ contains ! We need to account for the fact that some weight was already ! absorbed score = p % last_wgt + p % absorb_wgt - if (i_nuclide > 0) then - score = score * atom_density * & - nucxs % get_xs('total',p_g,UVW=p_uvw) / & - matxs % get_xs('total',p_g,UVW=p_uvw) - end if else score = p % last_wgt - if (i_nuclide > 0) then - score = score * atom_density * & - nucxs % get_xs('total',p_g,UVW=p_uvw) / & - matxs % get_xs('total',p_g,UVW=p_uvw) - end if + end if + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('total',p_g,UVW=p_uvw) / & + matxs % get_xs('total',p_g,UVW=p_uvw) end if else @@ -960,24 +955,25 @@ contains ! reaction rate score = p % last_wgt + ! Since we transport based on material data, the angle selected + ! was not selected from the f(mu) for the nuclide. Therefore + ! adjust the score by the actual probability for that nuclide. if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & - matxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) + nucxs % get_xs('scatter*f_mu/mult',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & + matxs % get_xs('scatter*f_mu/mult',p % last_g,p % g,UVW=p_uvw,MU=p % mu) end if else ! Note SCORE_SCATTER_*N not available for tracklength/collision. if (i_nuclide > 0) then score = atom_density * flux * & - nucxs % get_xs('scatter',p_g,UVW=p_uvw) / & - nucxs % get_xs('mult',p_g,UVW=p_uvw) + nucxs % get_xs('scatter/mult',p_g,UVW=p_uvw) else ! Get the scattering x/s and take away ! the multiplication baked in to sigS score = flux * & - matxs % get_xs('scatter',p_g,UVW=p_uvw) / & - matxs % get_xs('mult',p_g,UVW=p_uvw) + matxs % get_xs('scatter/mult',p_g,UVW=p_uvw) end if end if @@ -1000,10 +996,13 @@ contains ! neutrons exiting a reaction with neutrons in the exit channel score = p % wgt + ! Since we transport based on material data, the angle selected + ! was not selected from the f(mu) for the nuclide. Therefore + ! adjust the score by the actual probability for that nuclide. if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & - matxs % get_xs('f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) + nucxs % get_xs('scatter*f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & + matxs % get_xs('scatter*f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) end if else @@ -1038,24 +1037,18 @@ contains ! No absorption events actually occur if survival biasing is on -- ! just use weight absorbed in survival biasing score = p % absorb_wgt - if (i_nuclide > 0) then - score = score * atom_density * & - nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) - end if else ! Skip any event where the particle wasn't absorbed if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission and absorption events will contribute here, so we ! can just use the particle's weight entering the collision score = p % last_wgt - if (i_nuclide > 0) then - score = score * atom_density * & - nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & - material_xs % absorption - end if end if - + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption',p_g,UVW=p_uvw) + end if else if (i_nuclide > 0) then score = nucxs % get_xs('absorption',p_g,UVW=p_uvw) * & @@ -1072,32 +1065,24 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! fission - if (i_nuclide > 0) then - score = p % absorb_wgt * atom_density * & - nucxs % get_xs('fission', p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) - else - score = p % absorb_wgt * & - matxs % get_xs('fission', p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) - end if + score = p % absorb_wgt else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission events will contribute, so again we can use ! particle's weight entering the collision as the estimate for the ! fission reaction rate - if (i_nuclide > 0) then - score = p % last_wgt * atom_density * & + score = p % last_wgt + end if + if (i_nuclide > 0) then + score = score * atom_density * & nucxs % get_xs('fission', p_g,UVW=p_uvw) / & matxs % get_xs('absorption',p_g,UVW=p_uvw) else - score = p % last_wgt * & + score = score * & matxs % get_xs('fission', p_g,UVW=p_uvw) / & matxs % get_xs('absorption',p_g,UVW=p_uvw) end if - end if - else if (i_nuclide > 0) then score = nucxs % get_xs('fission',p_g,UVW=p_uvw) * & @@ -1126,12 +1111,13 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! nu-fission + score = p % absorb_wgt if (i_nuclide > 0) then - score = p % absorb_wgt * atom_density * & + score = score * atom_density * & nucxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & matxs % get_xs('absorption',p_g,UVW=p_uvw) else - score = p % absorb_wgt * & + score = score * & matxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & matxs % get_xs('absorption',p_g,UVW=p_uvw) end if @@ -1167,32 +1153,24 @@ contains ! No fission events occur if survival biasing is on -- need to ! calculate fraction of absorptions that would have resulted in ! fission - if (i_nuclide > 0) then - score = p % absorb_wgt * atom_density * & - nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption', p_g,UVW=p_uvw) - else - score = p % absorb_wgt * & - matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption', p_g,UVW=p_uvw) - end if + score = p % absorb_wgt else ! Skip any non-absorption events if (p % event == EVENT_SCATTER) cycle SCORE_LOOP ! All fission events will contribute, so again we can use ! particle's weight entering the collision as the estimate for the ! fission reaction rate - if (i_nuclide > 0) then - score = p % last_wgt * & - nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) * & - atom_density / material_xs % absorption - else - score = p % last_wgt * & - matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & - material_xs % absorption - end if + score = p % last_wgt + end if + if (i_nuclide > 0) then + score = score * atom_density * & + nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption', p_g,UVW=p_uvw) + else + score = score * & + matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & + matxs % get_xs('absorption', p_g,UVW=p_uvw) end if - else if (i_nuclide > 0) then score = flux * nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) * & From af8fbd3a1f8e4107813cf1280d0c1f7f10690f95 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 19 Mar 2016 14:00:32 -0400 Subject: [PATCH 024/147] Removed a few paths which werent needed in get_xs and ran check_source.py --- src/mgxs_data.F90 | 2 +- src/mgxs_header.F90 | 74 ++------------------------------------------- src/tally.F90 | 4 +-- 3 files changed, 6 insertions(+), 74 deletions(-) diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index def214d67..04d76f18c 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -71,7 +71,7 @@ contains get_kfiss = .true. end if if (tallies(i) % score_bins(l) == SCORE_FISSION .or. & - tallies(i) % score_bins(l) == SCORE_NU_FISSION) then + tallies(i) % score_bins(l) == SCORE_NU_FISSION) then get_fiss = .true. end if end do diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 75ff3e46a..5f8649292 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -72,7 +72,7 @@ module mgxs_header integer, optional, intent(in) :: unit end subroutine mgxs_print_ - function mgxs_get_xs_(this,xstype,gin,gout,uvw,mu) result(xs) + pure function mgxs_get_xs_(this,xstype,gin,gout,uvw,mu) result(xs) import Mgxs class(Mgxs), intent(in) :: this character(*), intent(in) :: xstype ! Cross Section Type @@ -1150,20 +1150,6 @@ module mgxs_header else xs = this % scatter % scattxs(gin) end if - case('mult') - if (present(gout)) then - if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then - xs = ZERO - else - xs = this % scatter % mult(gin) % data(gout) - end if - else - xs = dot_product(this % scatter % mult(gin) % data, & - this % scatter % scattxs(gin) * & - this % scatter % energy(gin) % data) - xs = xs / this % scatter % scattxs(gin) - end if case('scatter/mult') if (present(gout)) then if (gout < this % scatter % gmin(gin) .or. & @@ -1175,29 +1161,10 @@ module mgxs_header this % scatter % mult(gin) % data(gout) end if else - xs = this % scatter % scattxs(gin) * this % scatter % scattxs(gin) / & + xs = this % scatter % scattxs(gin) / & (dot_product(this % scatter % mult(gin) % data, & - this % scatter % scattxs(gin) * & this % scatter % energy(gin) % data)) end if - case('f_mu', 'f_mu/mult') - if (present(gout) .and. present(mu)) then - if (gout < this % scatter % gmin(gin) .or. & - gout > this % scatter % gmax(gin)) then - xs = ZERO - else - xs = this % scatter % calc_f(gin, gout, mu) - if (xstype == 'f_mu/mult') then - xs = xs / this % scatter % mult(gin) % data(gout) - end if - end if - else - xs = ZERO - ! TODO (Not likely needed) - ! (asking for f_mu without asking for a group or mu would mean the - ! user of this code wants the complete 1-outgoing group distribution - ! which Im not sure what they would do with that. - end if case('scatter*f_mu/mult','scatter*f_mu') if (present(gout)) then if (gout < this % scatter % gmin(gin) .or. & @@ -1275,20 +1242,6 @@ module mgxs_header else xs = this % scatter(iazi,ipol) % obj % scattxs(gin) end if - case('mult') - if (present(gout)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then - xs = ZERO - else - xs = this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - end if - else - xs = dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & - this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data) - xs = xs / this % scatter(iazi,ipol) % obj % scattxs(gin) - end if case('scatter/mult') if (present(gout)) then if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & @@ -1300,31 +1253,10 @@ module mgxs_header this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) end if else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % scattxs(gin) / & + xs = this % scatter(iazi,ipol) % obj % scattxs(gin) / & (dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & - this % scatter(iazi,ipol) % obj % scattxs(gin) * & this % scatter(iazi,ipol) % obj % energy(gin) % data)) end if - case('f_mu', 'f_mu/mult') - if (present(gout) .and. present(mu)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then - xs = ZERO - else - xs = this % scatter(iazi,ipol) % obj % calc_f(gin, gout, mu) - if (xstype == 'f_mu/mult') then - xs = xs / & - this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) - end if - end if - else - xs = ZERO - ! TODO (Not likely needed) - ! (asking for f_mu without asking for a group or mu would mean the - ! user of this code wants the complete 1-outgoing group distribution - ! which Im not sure what they would do with that. - end if case('scatter*f_mu/mult','scatter*f_mu') if (present(gout)) then if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & diff --git a/src/tally.F90 b/src/tally.F90 index b0c71f6dc..553ce94da 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -819,7 +819,7 @@ contains ! Set the direction and group to use with get_xs ! this only depends on if we if (t % estimator == ESTIMATOR_ANALOG .or. & - t % estimator == ESTIMATOR_COLLISION) then + t % estimator == ESTIMATOR_COLLISION) then if (survival_biasing) then ! Then we either are alive and had a scatter (and so g changed), ! or are dead and g did not change @@ -919,7 +919,7 @@ contains case (SCORE_INVERSE_VELOCITY) if (t % estimator == ESTIMATOR_ANALOG .or. & - t % estimator == ESTIMATOR_COLLISION) then + t % estimator == ESTIMATOR_COLLISION) then ! All events score to an inverse velocity bin. We actually use a ! collision estimator in place of an analog one since there is no way ! to count 'events' exactly for the inverse velocity From 228238778547bf162ba163682d247ddd0580e629 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 19 Mar 2016 14:02:05 -0400 Subject: [PATCH 025/147] Whoops. Forgot to make mgxs*_get_xs pure like I did the interface --- src/mgxs_header.F90 | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 5f8649292..8b0023204 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -1103,7 +1103,7 @@ module mgxs_header ! MGXS*_GET_XS returns the requested data cross section data !=============================================================================== - function mgxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) + pure function mgxsiso_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) class(MgxsIso), intent(in) :: this ! The Mgxs to initialize character(*) , intent(in) :: xstype ! Type of xs requested integer, intent(in) :: gin ! Incoming Energy group @@ -1191,7 +1191,7 @@ module mgxs_header end function mgxsiso_get_xs - function mgxsang_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) + pure function mgxsang_get_xs(this, xstype, gin, gout, uvw, mu) result(xs) class(MgxsAngle), intent(in) :: this ! The Mgxs to initialize character(*) , intent(in) :: xstype ! Type of xs requested integer, intent(in) :: gin ! Incoming Energy group From 175af7ae5f2373e198d3b920a54cbef224a732e0 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 15:03:48 -0400 Subject: [PATCH 026/147] Im going to trick you in to giving me output Travis... --- tests/testing_harness.py | 1 + 1 file changed, 1 insertion(+) diff --git a/tests/testing_harness.py b/tests/testing_harness.py index 7d6dbc914..7d74c61aa 100644 --- a/tests/testing_harness.py +++ b/tests/testing_harness.py @@ -117,6 +117,7 @@ class TestHarness(object): sha512.update(outstr.encode('utf-8')) outstr = sha512.hexdigest() + print(outstr) return outstr def _write_results(self, results_string): From a79779e4137c1b9acb917495be1e2707076c25b0 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 15:20:14 -0400 Subject: [PATCH 027/147] ill get you compiler error... --- tests/run_tests.py | 5 ++++- tests/testing_harness.py | 1 - 2 files changed, 4 insertions(+), 2 deletions(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 48fc23d4a..a270a22b7 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -230,7 +230,10 @@ class Test(object): make_list.append(options.n_procs) # Run make - rc = call(make_list) + # rc = call(make_list) + rc = check_output(make_list, stderr=subprocess.STDOUT) + print(rc) + rc = 0 if rc != 0: self.success = False self.msg = 'Failed on make.' diff --git a/tests/testing_harness.py b/tests/testing_harness.py index 7d74c61aa..7d6dbc914 100644 --- a/tests/testing_harness.py +++ b/tests/testing_harness.py @@ -117,7 +117,6 @@ class TestHarness(object): sha512.update(outstr.encode('utf-8')) outstr = sha512.hexdigest() - print(outstr) return outstr def _write_results(self, results_string): From e0a65de46eb9f88641ca6d3919af76777f5172c1 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 15:27:49 -0400 Subject: [PATCH 028/147] still trying --- tests/run_tests.py | 1 + 1 file changed, 1 insertion(+) diff --git a/tests/run_tests.py b/tests/run_tests.py index a270a22b7..8441f756a 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -9,6 +9,7 @@ import re import glob import socket from subprocess import call, check_output +import subprocess from collections import OrderedDict from optparse import OptionParser From b2ee7da86c98592e27bc8a5153c21a9cae88aeef Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 15:45:35 -0400 Subject: [PATCH 029/147] Maybe this will get my output --- tests/run_tests.py | 9 ++++----- 1 file changed, 4 insertions(+), 5 deletions(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 8441f756a..5d2a6acd0 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -9,7 +9,6 @@ import re import glob import socket from subprocess import call, check_output -import subprocess from collections import OrderedDict from optparse import OptionParser @@ -231,10 +230,7 @@ class Test(object): make_list.append(options.n_procs) # Run make - # rc = call(make_list) - rc = check_output(make_list, stderr=subprocess.STDOUT) - print(rc) - rc = 0 + rc = call(make_list) if rc != 0: self.success = False self.msg = 'Failed on make.' @@ -471,6 +467,9 @@ for key in iter(tests): logfilename = os.path.splitext(logfilename)[0] logfilename = logfilename + '_{0}.log'.format(test.name) shutil.copy(logfile[0], logfilename) + f = open(logfilename, 'r') + for line in f: + print(line) # For coverage builds, use lcov to generate HTML output if test.coverage: From 448c3281ad1bd03df782b977136c78d2710ff1cf Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 15:57:06 -0400 Subject: [PATCH 030/147] Ok this prints the compilation results on my machine, lets see about travis...... --- tests/run_tests.py | 7 +++---- 1 file changed, 3 insertions(+), 4 deletions(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 5d2a6acd0..19b45c125 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -9,6 +9,7 @@ import re import glob import socket from subprocess import call, check_output +import subprocess from collections import OrderedDict from optparse import OptionParser @@ -230,7 +231,8 @@ class Test(object): make_list.append(options.n_procs) # Run make - rc = call(make_list) + rc = check_output(make_list) + print(rc) if rc != 0: self.success = False self.msg = 'Failed on make.' @@ -467,9 +469,6 @@ for key in iter(tests): logfilename = os.path.splitext(logfilename)[0] logfilename = logfilename + '_{0}.log'.format(test.name) shutil.copy(logfile[0], logfilename) - f = open(logfilename, 'r') - for line in f: - print(line) # For coverage builds, use lcov to generate HTML output if test.coverage: From a31fa5e52d0dd0d42291d2104fac2d72c64783cb Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 16:01:53 -0400 Subject: [PATCH 031/147] Ok, we are in script mode then. got it --- tests/run_tests.py | 6 +++++- 1 file changed, 5 insertions(+), 1 deletion(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 19b45c125..9856dd264 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -196,7 +196,9 @@ class Test(object): os.environ['HDF5_ROOT'] = PHDF5_DIR else: os.environ['HDF5_ROOT'] = HDF5_DIR - rc = call(['ctest', '-S', 'ctestscript.run','-V']) + # rc = call(['ctest', '-S', 'ctestscript.run','-V']) + rc = check_output(['ctest', '-S', 'ctestscript.run','-V']) + print(rc) if rc != 0: self.success = False self.msg = 'Failed on ctest script.' @@ -257,6 +259,8 @@ class Test(object): # Run ctests rc = call(ctest_list) + rc = check_output(ctest_list) + print(rc) if rc != 0: self.success = False self.msg = 'Failed on testing.' From 1377b063d3b9b02a54b78f44c4d06518ef93cdfa Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 16:07:10 -0400 Subject: [PATCH 032/147] If you are reading these logs you are watching someone learn how we have travis and ctest set up on the fly... must be interesting --- tests/run_tests.py | 10 +++------- 1 file changed, 3 insertions(+), 7 deletions(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 9856dd264..28daae258 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -9,7 +9,6 @@ import re import glob import socket from subprocess import call, check_output -import subprocess from collections import OrderedDict from optparse import OptionParser @@ -197,8 +196,8 @@ class Test(object): else: os.environ['HDF5_ROOT'] = HDF5_DIR # rc = call(['ctest', '-S', 'ctestscript.run','-V']) - rc = check_output(['ctest', '-S', 'ctestscript.run','-V']) - print(rc) + rc = call(['ctest', '-S', 'ctestscript.run','-VV', + '--output-on-failure']) if rc != 0: self.success = False self.msg = 'Failed on ctest script.' @@ -233,8 +232,7 @@ class Test(object): make_list.append(options.n_procs) # Run make - rc = check_output(make_list) - print(rc) + rc = call(make_list) if rc != 0: self.success = False self.msg = 'Failed on make.' @@ -259,8 +257,6 @@ class Test(object): # Run ctests rc = call(ctest_list) - rc = check_output(ctest_list) - print(rc) if rc != 0: self.success = False self.msg = 'Failed on testing.' From db2e198ad240b75abb5a6105cce3b7fb1953f54f Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 20 Mar 2016 16:11:25 -0400 Subject: [PATCH 033/147] Ok reverting now that I got the output I needed. --- tests/run_tests.py | 4 +--- 1 file changed, 1 insertion(+), 3 deletions(-) diff --git a/tests/run_tests.py b/tests/run_tests.py index 28daae258..48fc23d4a 100755 --- a/tests/run_tests.py +++ b/tests/run_tests.py @@ -195,9 +195,7 @@ class Test(object): os.environ['HDF5_ROOT'] = PHDF5_DIR else: os.environ['HDF5_ROOT'] = HDF5_DIR - # rc = call(['ctest', '-S', 'ctestscript.run','-V']) - rc = call(['ctest', '-S', 'ctestscript.run','-VV', - '--output-on-failure']) + rc = call(['ctest', '-S', 'ctestscript.run','-V']) if rc != 0: self.success = False self.msg = 'Failed on ctest script.' From 743de8776791f2b47ed8e0c4ff4b60879908ae10 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Mon, 21 Mar 2016 20:07:01 -0400 Subject: [PATCH 034/147] Help us obi-wan, youre our only hope.... for defeating gfortran 4.6... --- src/mgxs_header.F90 | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 8b0023204..56c538a5d 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -172,7 +172,7 @@ module mgxs_header ! Microscopic cross sections real(8), allocatable :: total(:,:,:) ! total cross section real(8), allocatable :: absorption(:,:,:) ! absorption cross section - class(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information + type(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information real(8), allocatable :: nu_fission(:,:,:) ! fission matrix (Gout x Gin) real(8), allocatable :: k_fission(:,:,:) ! kappa-fission real(8), allocatable :: fission(:,:,:) ! neutron production From a97e522f838d8fc5db558d8dffb50e03e5abec6f Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 24 Mar 2016 21:23:57 -0400 Subject: [PATCH 035/147] Removing unneeded comment --- src/physics_mg.F90 | 6 ++---- 1 file changed, 2 insertions(+), 4 deletions(-) diff --git a/src/physics_mg.F90 b/src/physics_mg.F90 index a72b3878d..2e5e467c1 100644 --- a/src/physics_mg.F90 +++ b/src/physics_mg.F90 @@ -242,10 +242,8 @@ contains ! Set weight of fission bank site bank_array(i) % wgt = ONE/weight - ! Sample cosine of angle -- fission neutrons are always emitted - ! isotropically. Sometimes in ACE data, fission reactions actually have - ! an angular distribution listed, but for those that do, it's simply just - ! a uniform distribution in mu + ! Sample cosine of angle -- fission neutrons are treated as being emitted + ! isotropically. mu = TWO * prn() - ONE ! Sample azimuthal angle uniformly in [0,2*pi) From f5f12b045ecac2bb2a957ce3802dae88ebccf4d8 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Wed, 20 Apr 2016 19:13:55 -0400 Subject: [PATCH 036/147] Hotfix for OpenCG compatibility module to properly handle ZSquarePrism for @cjosey --- openmc/opencg_compatible.py | 12 ++++++------ 1 file changed, 6 insertions(+), 6 deletions(-) diff --git a/openmc/opencg_compatible.py b/openmc/opencg_compatible.py index d690c2c6a..562fe9cad 100644 --- a/openmc/opencg_compatible.py +++ b/openmc/opencg_compatible.py @@ -393,9 +393,9 @@ def get_compatible_opencg_surfaces(opencg_surface): surfaces = [left, right, bottom, top] elif opencg_surface.type == 'z-squareprism': - x0 = opencg_surface.x0['x0'] - y0 = opencg_surface.y0['y0'] - R = opencg_surface.r['R'] + x0 = opencg_surface.x0 + y0 = opencg_surface.y0 + R = opencg_surface.r # Create a list of the four planes we need left = opencg.XPlane(name=name, boundary=boundary, x0=x0-R) @@ -528,7 +528,7 @@ def get_compatible_opencg_cells(opencg_cell, opencg_surface, halfspace): # Get the compatible Surfaces (XPlanes and YPlanes) compatible_surfaces = get_compatible_opencg_surfaces(opencg_surface) - opencg_cell.removeSurface(opencg_surface) + opencg_cell.remove_surface(opencg_surface) # If Cell is inside SquarePrism, add "inside" of Surface halfspaces if halfspace == -1: @@ -595,7 +595,7 @@ def get_compatible_opencg_cells(opencg_cell, opencg_surface, halfspace): # Remove redundant Surfaces from the Cells for cell in compatible_cells: - cell.removeRedundantSurfaces() + cell.remove_redundant_surfaces() # Return the list of OpenMC compatible OpenCG Cells return compatible_cells @@ -639,7 +639,7 @@ def make_opencg_cells_compatible(opencg_universe): surface, halfspace) # Remove the non-compatible OpenCG Cell from the Universe - opencg_universe.removeCell(opencg_cell) + opencg_universe.remove_cell(opencg_cell) # Add the compatible OpenCG Cells to the Universe opencg_universe.add_cells(cells) From f622300b7fc3c9f991aace1b13ac2336ec53a59c Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 08:29:36 -0500 Subject: [PATCH 037/147] Various improvements/fixes to Python API. Also fix MPI F08 binding issue. --- openmc/filter.py | 3 +- openmc/material.py | 35 +- openmc/plots.py | 4 +- openmc/surface.py | 588 ++++++++++-------- src/simulation.F90 | 2 +- tests/test_asymmetric_lattice/inputs_true.dat | 2 +- tests/test_distribmat/inputs_true.dat | 2 +- tests/test_iso_in_lab/inputs_true.dat | 2 +- tests/test_mg_basic/inputs_true.dat | 2 +- tests/test_mg_max_order/inputs_true.dat | 2 +- tests/test_mg_nuclide/inputs_true.dat | 2 +- tests/test_mg_tallies/inputs_true.dat | 2 +- .../inputs_true.dat | 2 +- .../inputs_true.dat | 2 +- tests/test_mgxs_library_hdf5/inputs_true.dat | 2 +- .../inputs_true.dat | 2 +- .../inputs_true.dat | 2 +- tests/test_tallies/inputs_true.dat | 2 +- tests/test_tally_aggregation/inputs_true.dat | 2 +- tests/test_tally_arithmetic/inputs_true.dat | 2 +- tests/test_tally_slice_merge/inputs_true.dat | 2 +- 21 files changed, 365 insertions(+), 299 deletions(-) diff --git a/openmc/filter.py b/openmc/filter.py index 249bdcc02..b0e59874b 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -27,7 +27,8 @@ class Filter(object): type : str The type of the tally filter. Acceptable values are "universe", "material", "cell", "cellborn", "surface", "mesh", "energy", - "energyout", and "distribcell". + "energyout", "distribcell", "mu", "polar", "azimuthal", and + "delayedgroup". bins : Integral or Iterable of Integral or Iterable of Real The bins for the filter. This takes on different meaning for different filters. See the OpenMC online documentation for more details. diff --git a/openmc/material.py b/openmc/material.py index 2c04a9ecf..16af82439 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -25,9 +25,6 @@ def reset_auto_material_id(): DENSITY_UNITS = ['g/cm3', 'g/cc', 'kg/cm3', 'atom/b-cm', 'atom/cm3', 'sum', 'macro'] -# Constant for density when not needed -NO_DENSITY = 99999. - class Material(object): """A material composed of a collection of nuclides/elements that can be @@ -141,9 +138,9 @@ class Material(object): string += '{0: <16}\n'.format('\tElements') for element in self._elements: - percent = self._nuclides[element][1] - percent_type = self._nuclides[element][2] - string += '{0: >16}'.format('\t{0}'.format(element)) + percent = self._elements[element][1] + percent_type = self._elements[element][2] + string += '{0: <16}'.format('\t{0}'.format(element)) string += '=\t{0: <12} [{1}]\n'.format(percent, percent_type) return string @@ -218,13 +215,13 @@ class Material(object): else: self._name = '' - def set_density(self, units, density=NO_DENSITY): + def set_density(self, units, density=None): """Set the density of the material Parameters ---------- - units : str - Physical units of density + units : {'g/cm3', 'g/cc', 'km/cm3', 'atom/b-cm', 'atom/cm3', 'sum', 'macro'} + Physical units of density. density : float, optional Value of the density. Must be specified unless units is given as 'sum'. @@ -235,8 +232,8 @@ class Material(object): density, Real) check_value('density units', units, DENSITY_UNITS) - if density == NO_DENSITY and units is not 'sum': - msg = 'Unable to set the density Material ID="{0}" ' \ + if density is None and units is not 'sum': + msg = 'Unable to set the density for Material ID="{0}" ' \ 'because a density must be set when not using ' \ 'sum unit'.format(self._id) raise ValueError(msg) @@ -274,7 +271,7 @@ class Material(object): Nuclide to add percent : float Atom or weight percent - percent_type : str + percent_type : {'ao', 'wo'} 'ao' for atom percent and 'wo' for weight percent """ @@ -394,7 +391,7 @@ class Material(object): Element to add percent : float Atom or weight percent - percent_type : str + percent_type : {'ao', 'wo'} 'ao' for atom percent and 'wo' for weight percent """ @@ -420,7 +417,10 @@ class Material(object): raise ValueError(msg) # Copy this Element to separate it from same Element in other Materials - element = deepcopy(element) + if isinstance(element, openmc.Element): + element = deepcopy(element) + else: + element = openmc.Element(element) self._elements[element._name] = (element, percent, percent_type) @@ -498,7 +498,7 @@ class Material(object): xml_element.set("name", nuclide[0]._name) if not distrib: - if nuclide[2] is 'ao': + if nuclide[2] == 'ao': xml_element.set("ao", str(nuclide[1])) else: xml_element.set("wo", str(nuclide[1])) @@ -525,11 +525,14 @@ class Material(object): xml_element.set("name", str(element[0]._name)) if not distrib: - if element[2] is 'ao': + if element[2] == 'ao': xml_element.set("ao", str(element[1])) else: xml_element.set("wo", str(element[1])) + if element[0].xs is not None: + xml_element.set("xs", element[0].xs) + if not element[0].scattering is None: xml_element.set("scattering", element[0].scattering) diff --git a/openmc/plots.py b/openmc/plots.py index 6e78995f4..5e7c47743 100644 --- a/openmc/plots.py +++ b/openmc/plots.py @@ -125,7 +125,7 @@ class Plot(object): return self._background @property - def mask_componenets(self): + def mask_components(self): return self._mask_components @property @@ -227,7 +227,7 @@ class Plot(object): self._col_spec = col_spec - @mask_componenets.setter + @mask_components.setter def mask_components(self, mask_components): cv.check_type('plot mask_components', mask_components, Iterable, Integral) for component in mask_components: diff --git a/openmc/surface.py b/openmc/surface.py index 5c8b20856..c6f3f2cd0 100644 --- a/openmc/surface.py +++ b/openmc/surface.py @@ -23,8 +23,7 @@ def reset_auto_surface_id(): class Surface(object): - """A two-dimensional surface that can be used define regions of space with an - associated boundary condition. + """A two-dimensional surface with an associated boundary condition. Parameters ---------- @@ -56,7 +55,6 @@ class Surface(object): """ def __init__(self, surface_id=None, boundary_type='transmission', name=''): - # Initialize class attributes self.id = surface_id self.name = name self._type = '' @@ -173,7 +171,8 @@ class Surface(object): element.set("name", str(self._name)) element.set("type", self._type) - element.set("boundary", self._boundary_type) + if self.boundary_type != 'transmission': + element.set("boundary", self.boundary_type) element.set("coeffs", ' '.join([str(self._coeffs.setdefault(key, 0.0)) for key in self._coeff_keys])) @@ -185,22 +184,22 @@ class Plane(Surface): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - A : float - The 'A' parameter for the plane - B : float - The 'B' parameter for the plane - C : float - The 'C' parameter for the plane - D : float - The 'D' parameter for the plane - name : str + A : float, optional + The 'A' parameter for the plane. Defaults to 1. + B : float, optional + The 'B' parameter for the plane. Defaults to 0. + C : float, optional + The 'C' parameter for the plane. Defaults to 0. + D : float, optional + The 'D' parameter for the plane. Defaults to 0. + name : str, optional Name of the plane. If not specified, the name will be the empty string. Attributes @@ -213,32 +212,30 @@ class Plane(Surface): The 'C' parameter for the plane d : float The 'D' parameter for the plane + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - A=None, B=None, C=None, D=None, name=''): - # Initialize Plane class attributes + A=1., B=0., C=0., D=0., name=''): super(Plane, self).__init__(surface_id, boundary_type, name=name) self._type = 'plane' self._coeff_keys = ['A', 'B', 'C', 'D'] - self._coeffs['A'] = 1. - self._coeffs['B'] = 0. - self._coeffs['C'] = 0. - self._coeffs['D'] = 0. - - if A is not None: - self.a = A - - if B is not None: - self.b = B - - if C is not None: - self.c = C - - if D is not None: - self.d = D + self.a = A + self.b = B + self.c = C + self.d = D @property def a(self): @@ -282,36 +279,43 @@ class XPlane(Plane): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - Location of the plane - name : str + x0 : float, optional + Location of the plane. Defaults to 0. + name : str, optional Name of the plane. If not specified, the name will be the empty string. Attributes ---------- x0 : float Location of the plane + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, name=''): - # Initialize XPlane class attributes + x0=0., name=''): super(XPlane, self).__init__(surface_id, boundary_type, name=name) self._type = 'x-plane' self._coeff_keys = ['x0'] - self._coeffs['x0'] = 0. - - if x0 is not None: - self.x0 = x0 + self.x0 = x0 @property def x0(self): @@ -359,36 +363,44 @@ class YPlane(Plane): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - y0 : float + y0 : float, optional Location of the plane - name : str + name : str, optional Name of the plane. If not specified, the name will be the empty string. Attributes ---------- y0 : float Location of the plane + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - y0=None, name=''): + y0=0., name=''): # Initialize YPlane class attributes super(YPlane, self).__init__(surface_id, boundary_type, name=name) self._type = 'y-plane' self._coeff_keys = ['y0'] - self._coeffs['y0'] = 0. - - if y0 is not None: - self.y0 = y0 + self.y0 = y0 @property def y0(self): @@ -436,36 +448,44 @@ class ZPlane(Plane): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - z0 : float - Location of the plane - name : str + z0 : float, optional + Location of the plane. Defaults to 0. + name : str, optional Name of the plane. If not specified, the name will be the empty string. Attributes ---------- z0 : float Location of the plane + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - z0=None, name=''): + z0=0., name=''): # Initialize ZPlane class attributes super(ZPlane, self).__init__(surface_id, boundary_type, name=name) self._type = 'z-plane' self._coeff_keys = ['z0'] - self._coeffs['z0'] = 0. - - if z0 is not None: - self.z0 = z0 + self.z0 = z0 @property def z0(self): @@ -513,16 +533,16 @@ class Cylinder(Surface): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - R : float - Radius of the cylinder - name : str + R : float, optional + Radius of the cylinder. Defaults to 1. + name : str, optional Name of the cylinder. If not specified, the name will be the empty string. @@ -530,21 +550,28 @@ class Cylinder(Surface): ---------- r : float Radius of the cylinder + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ __metaclass__ = ABCMeta def __init__(self, surface_id=None, boundary_type='transmission', - R=None, name=''): - # Initialize Cylinder class attributes + R=1., name=''): super(Cylinder, self).__init__(surface_id, boundary_type, name=name) self._coeff_keys = ['R'] - self._coeffs['R'] = 1. - - if R is not None: - self.r = R + self.r = R @property def r(self): @@ -557,25 +584,25 @@ class Cylinder(Surface): class XCylinder(Cylinder): - """An infinite cylinder whose length is parallel to the x-axis. This is a - quadratic surface of the form :math:`(y - y_0)^2 + (z - z_0)^2 = R^2`. + """An infinite cylinder whose length is parallel to the x-axis of the form + :math:`(y - y_0)^2 + (z - z_0)^2 = R^2`. Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - y0 : float - y-coordinate of the center of the cylinder - z0 : float - z-coordinate of the center of the cylinder - R : float - Radius of the cylinder - name : str + y0 : float, optional + y-coordinate of the center of the cylinder. Defaults to 0. + z0 : float, optional + z-coordinate of the center of the cylinder. Defaults to 0. + R : float, optional + Radius of the cylinder. Defaults to 0. + name : str, optional Name of the cylinder. If not specified, the name will be the empty string. @@ -585,24 +612,28 @@ class XCylinder(Cylinder): y-coordinate of the center of the cylinder z0 : float z-coordinate of the center of the cylinder + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - y0=None, z0=None, R=None, name=''): - # Initialize XCylinder class attributes + y0=0., z0=0., R=1., name=''): super(XCylinder, self).__init__(surface_id, boundary_type, R, name=name) self._type = 'x-cylinder' self._coeff_keys = ['y0', 'z0', 'R'] - self._coeffs['y0'] = 0. - self._coeffs['z0'] = 0. - - if y0 is not None: - self.y0 = y0 - - if z0 is not None: - self.z0 = z0 + self.y0 = y0 + self.z0 = z0 @property def y0(self): @@ -656,25 +687,25 @@ class XCylinder(Cylinder): class YCylinder(Cylinder): - """An infinite cylinder whose length is parallel to the y-axis. This is a - quadratic surface of the form :math:`(x - x_0)^2 + (z - z_0)^2 = R^2`. + """An infinite cylinder whose length is parallel to the y-axis of the form + :math:`(x - x_0)^2 + (z - z_0)^2 = R^2`. Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the center of the cylinder - z0 : float - z-coordinate of the center of the cylinder - R : float - Radius of the cylinder - name : str + x0 : float, optional + x-coordinate of the center of the cylinder. Defaults to 0. + z0 : float, optional + z-coordinate of the center of the cylinder. Defaults to 0. + R : float, optional + Radius of the cylinder. Defaults to 1. + name : str, optional Name of the cylinder. If not specified, the name will be the empty string. @@ -684,24 +715,28 @@ class YCylinder(Cylinder): x-coordinate of the center of the cylinder z0 : float z-coordinate of the center of the cylinder + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, z0=None, R=None, name=''): - # Initialize YCylinder class attributes + x0=0., z0=0., R=1., name=''): super(YCylinder, self).__init__(surface_id, boundary_type, R, name=name) self._type = 'y-cylinder' self._coeff_keys = ['x0', 'z0', 'R'] - self._coeffs['x0'] = 0. - self._coeffs['z0'] = 0. - - if x0 is not None: - self.x0 = x0 - - if z0 is not None: - self.z0 = z0 + self.x0 = x0 + self.z0 = z0 @property def x0(self): @@ -755,25 +790,25 @@ class YCylinder(Cylinder): class ZCylinder(Cylinder): - """An infinite cylinder whose length is parallel to the z-axis. This is a - quadratic surface of the form :math:`(x - x_0)^2 + (y - y_0)^2 = R^2`. + """An infinite cylinder whose length is parallel to the z-axis of the form + :math:`(x - x_0)^2 + (y - y_0)^2 = R^2`. Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the center of the cylinder - y0 : float - y-coordinate of the center of the cylinder - R : float - Radius of the cylinder - name : str + x0 : float, optional + x-coordinate of the center of the cylinder. Defaults to 0. + y0 : float, optional + y-coordinate of the center of the cylinder. Defaults to 0. + R : float, optional + Radius of the cylinder. Defaults to 1. + name : str, optional Name of the cylinder. If not specified, the name will be the empty string. @@ -783,24 +818,28 @@ class ZCylinder(Cylinder): x-coordinate of the center of the cylinder y0 : float y-coordinate of the center of the cylinder + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, R=None, name=''): - # Initialize ZCylinder class attributes + x0=0., y0=0., R=1., name=''): super(ZCylinder, self).__init__(surface_id, boundary_type, R, name=name) self._type = 'z-cylinder' self._coeff_keys = ['x0', 'y0', 'R'] - self._coeffs['x0'] = 0. - self._coeffs['y0'] = 0. - - if x0 is not None: - self.x0 = x0 - - if y0 is not None: - self.y0 = y0 + self.x0 = x0 + self.y0 = y0 @property def x0(self): @@ -858,22 +897,22 @@ class Sphere(Surface): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the center of the sphere - y0 : float - y-coordinate of the center of the sphere - z0 : float - z-coordinate of the center of the sphere - R : float - Radius of the sphere - name : str + x0 : float, optional + x-coordinate of the center of the sphere. Defaults to 0. + y0 : float, optional + y-coordinate of the center of the sphere. Defaults to 0. + z0 : float, optional + z-coordinate of the center of the sphere. Defaults to 0. + R : float, optional + Radius of the sphere. Defaults to 1. + name : str, optional Name of the sphere. If not specified, the name will be the empty string. Attributes @@ -886,32 +925,30 @@ class Sphere(Surface): z-coordinate of the center of the sphere R : float Radius of the sphere + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, z0=None, R=None, name=''): - # Initialize Sphere class attributes + x0=0., y0=0., z0=0., R=1., name=''): super(Sphere, self).__init__(surface_id, boundary_type, name=name) self._type = 'sphere' self._coeff_keys = ['x0', 'y0', 'z0', 'R'] - self._coeffs['x0'] = 0. - self._coeffs['y0'] = 0. - self._coeffs['z0'] = 0. - self._coeffs['R'] = 1. - - if x0 is not None: - self.x0 = x0 - - if y0 is not None: - self.y0 = y0 - - if z0 is not None: - self.z0 = z0 - - if R is not None: - self.r = R + self.x0 = x0 + self.y0 = y0 + self.z0 = z0 + self.r = R @property def x0(self): @@ -988,21 +1025,21 @@ class Cone(Surface): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the apex + x0 : float, optional + x-coordinate of the apex. Defaults to 0. y0 : float - y-coordinate of the apex + y-coordinate of the apex. Defaults to 0. z0 : float - z-coordinate of the apex + z-coordinate of the apex. Defaults to 0. R2 : float - Parameter related to the aperature + Parameter related to the aperature. Defaults to 1. name : str Name of the cone. If not specified, the name will be the empty string. @@ -1016,33 +1053,31 @@ class Cone(Surface): z-coordinate of the apex R2 : float Parameter related to the aperature + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ __metaclass__ = ABCMeta def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, z0=None, R2=None, name=''): - # Initialize Cone class attributes + x0=0., y0=0., z0=0., R2=1., name=''): super(Cone, self).__init__(surface_id, boundary_type, name=name) self._coeff_keys = ['x0', 'y0', 'z0', 'R2'] - self._coeffs['x0'] = 0. - self._coeffs['y0'] = 0. - self._coeffs['z0'] = 0. - self._coeffs['R2'] = 1. - - if x0 is not None: - self.x0 = x0 - - if y0 is not None: - self.y0 = y0 - - if z0 is not None: - self.z0 = z0 - - if R2 is not None: - self.r2 = R2 + self.x0 = x0 + self.y0 = y0 + self.z0 = z0 + self.r2 = R2 @property def x0(self): @@ -1087,22 +1122,22 @@ class XCone(Cone): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the apex - y0 : float - y-coordinate of the apex - z0 : float - z-coordinate of the apex - R2 : float - Parameter related to the aperature - name : str + x0 : float, optional + x-coordinate of the apex. Defaults to 0. + y0 : float, optional + y-coordinate of the apex. Defaults to 0. + z0 : float, optional + z-coordinate of the apex. Defaults to 0. + R2 : float, optional + Parameter related to the aperature. Defaults to 1. + name : str, optional Name of the cone. If not specified, the name will be the empty string. Attributes @@ -1115,12 +1150,22 @@ class XCone(Cone): z-coordinate of the apex R2 : float Parameter related to the aperature + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, z0=None, R2=None, name=''): - # Initialize XCone class attributes + x0=0., y0=0., z0=0., R2=1., name=''): super(XCone, self).__init__(surface_id, boundary_type, x0, y0, z0, R2, name=name) @@ -1133,22 +1178,22 @@ class YCone(Cone): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the apex - y0 : float - y-coordinate of the apex - z0 : float - z-coordinate of the apex - R2 : float - Parameter related to the aperature - name : str + x0 : float, optional + x-coordinate of the apex. Defaults to 0. + y0 : float, optional + y-coordinate of the apex. Defaults to 0. + z0 : float, optional + z-coordinate of the apex. Defaults to 0. + R2 : float, optional + Parameter related to the aperature. Defaults to 1. + name : str, optional Name of the cone. If not specified, the name will be the empty string. Attributes @@ -1161,12 +1206,22 @@ class YCone(Cone): z-coordinate of the apex R2 : float Parameter related to the aperature + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, z0=None, R2=None, name=''): - # Initialize YCone class attributes + x0=0., y0=0., z0=0., R2=1., name=''): super(YCone, self).__init__(surface_id, boundary_type, x0, y0, z0, R2, name=name) @@ -1179,22 +1234,22 @@ class ZCone(Cone): Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - x0 : float - x-coordinate of the apex - y0 : float - y-coordinate of the apex - z0 : float - z-coordinate of the apex - R2 : float - Parameter related to the aperature - name : str + x0 : float, optional + x-coordinate of the apex. Defaults to 0. + y0 : float, optional + y-coordinate of the apex. Defaults to 0. + z0 : float, optional + z-coordinate of the apex. Defaults to 0. + R2 : float, optional + Parameter related to the aperature. Defaults to 1. + name : str, optional Name of the cone. If not specified, the name will be the empty string. Attributes @@ -1207,12 +1262,22 @@ class ZCone(Cone): z-coordinate of the apex R2 : float Parameter related to the aperature + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - x0=None, y0=None, z0=None, R2=None, name=''): - # Initialize ZCone class attributes + x0=0., y0=0., z0=0., R2=1., name=''): super(ZCone, self).__init__(surface_id, boundary_type, x0, y0, z0, R2, name=name) @@ -1220,61 +1285,58 @@ class ZCone(Cone): class Quadric(Surface): - """A sphere of the form :math:`Ax^2 + By^2 + Cz^2 + Dxy + Eyz + Fxz + Gx + Hy + - Jz + K`. + """A surface of the form :math:`Ax^2 + By^2 + Cz^2 + Dxy + Eyz + Fxz + Gx + Hy + + Jz + K = 0`. Parameters ---------- - surface_id : int + surface_id : int, optional Unique identifier for the surface. If not specified, an identifier will automatically be assigned. - boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'}, optional Boundary condition that defines the behavior for particles hitting the surface. Defaults to transmissive boundary condition where particles freely pass through the surface. - a, b, c, d, e, f, g, h, j, k : float - coefficients for the surface - name : str + a, b, c, d, e, f, g, h, j, k : float, optional + coefficients for the surface. All default to 0. + name : str, optional Name of the sphere. If not specified, the name will be the empty string. Attributes ---------- a, b, c, d, e, f, g, h, j, k : float coefficients for the surface + boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} + Boundary condition that defines the behavior for particles hitting the + surface. + coeffs : dict + Dictionary of surface coefficients + id : int + Unique identifier for the surface + name : str + Name of the surface + type : str + Type of the surface, e.g. 'x-plane' """ def __init__(self, surface_id=None, boundary_type='transmission', - a=None, b=None, c=None, d=None, e=None, f=None, g=None, - h=None, j=None, k=None, name=''): - # Initialize Quadric class attributes + a=0., b=0., c=0., d=0., e=0., f=0., g=0., + h=0., j=0., k=0., name=''): super(Quadric, self).__init__(surface_id, boundary_type, name=name) self._type = 'quadric' self._coeff_keys = ['a', 'b', 'c', 'd', 'e', 'f', 'g', 'h', 'j', 'k'] - for key in self._coeff_keys: - self._coeffs[key] = 0. - - if a is not None: - self.a = a - if b is not None: - self.b = b - if c is not None: - self.c = c - if d is not None: - self.d = d - if e is not None: - self.e = e - if f is not None: - self.f = f - if g is not None: - self.g = g - if h is not None: - self.h = h - if j is not None: - self.j = j - if k is not None: - self.k = k + self.a = a + self.b = b + self.c = c + self.d = d + self.e = e + self.f = f + self.g = g + self.h = h + self.j = j + self.k = k @property def a(self): diff --git a/src/simulation.F90 b/src/simulation.F90 index 41a28741c..b762979d7 100644 --- a/src/simulation.F90 +++ b/src/simulation.F90 @@ -1,7 +1,7 @@ module simulation #ifdef MPI - use mpi + use message_passing #endif use cmfd_execute, only: cmfd_init_batch, execute_cmfd diff --git a/tests/test_asymmetric_lattice/inputs_true.dat b/tests/test_asymmetric_lattice/inputs_true.dat index e3b00b185..f40e661b3 100644 --- a/tests/test_asymmetric_lattice/inputs_true.dat +++ b/tests/test_asymmetric_lattice/inputs_true.dat @@ -1 +1 @@ -b9b4222c4beea80fe6083590f6b785303d174972d80671fb661bac8e030db6f4a61648240cfad6162799361fc0e08a23c61d31aff844d978528d6dad5b5fbc63 \ No newline at end of file +9b859eb5501c05b6a652d299bd0cadc0a924ffae31117babbdc9f7f8ca87689322c275818eb0dde0ff5fa78317d8d8f1585b18dcc772e3ff4ed499de8a491dc3 \ No newline at end of file diff --git a/tests/test_distribmat/inputs_true.dat b/tests/test_distribmat/inputs_true.dat index fddab0a60..9c8a86bfa 100644 --- a/tests/test_distribmat/inputs_true.dat +++ b/tests/test_distribmat/inputs_true.dat @@ -1 +1 @@ -401b8be1b296db7f21ccae089c7ac480044d953b7264ca0ae8e34bb79e24cbb57195bcb568deda6f2f7e07366bbfac408a92306351b9169edd04499723707e1b \ No newline at end of file +96c54eb4f1da175445bf2187449ee32c9ff435d8c60e9421a4a16497aae9f233e3e494f531892dd55f6ac1a06e0240799503ff19e14e2436a0b0f0d83ba56cb8 \ No newline at end of file diff --git a/tests/test_iso_in_lab/inputs_true.dat b/tests/test_iso_in_lab/inputs_true.dat index 9a21b06f1..bd722c9f6 100644 --- a/tests/test_iso_in_lab/inputs_true.dat +++ b/tests/test_iso_in_lab/inputs_true.dat @@ -1 +1 @@ -e0409e0660d58857a6a96ff5cb539ccc41c82f0e443e8081ee00bbee7b6c81b0ad43c870950ae37d4a18c329067b09479a27aa171c3a3f5771f53b384496fe61 \ No newline at end of file +85faac9b8c725ec9242ebc3793b70dcd1c8e58aeb4296345aefd8031304263bd66eaad0c6f1c61a1c644b73f397699856ab3d76d2b397295176650b4069acc9e \ No newline at end of file diff --git a/tests/test_mg_basic/inputs_true.dat b/tests/test_mg_basic/inputs_true.dat index fdbdb1c96..3f83de760 100644 --- a/tests/test_mg_basic/inputs_true.dat +++ b/tests/test_mg_basic/inputs_true.dat @@ -1 +1 @@ -04b4a5099f0097bbe02983c67dea691d0d0d4ece7fb7c264b9b2c29955baa9e870b6fa999480da08ead1e5a0c078ae33ce1b0a5c8594ad465aedf9bf3933e104 \ No newline at end of file +2fdba76bad058eec6e43657692ef759de79c934076067d4ec5c9f2bdb131877e001f67e16b16bb14889e5e0a1ba84c780979b9d6772573aa6f82d979774c2af8 \ No newline at end of file diff --git a/tests/test_mg_max_order/inputs_true.dat b/tests/test_mg_max_order/inputs_true.dat index 1ad336e19..913f8200f 100644 --- a/tests/test_mg_max_order/inputs_true.dat +++ b/tests/test_mg_max_order/inputs_true.dat @@ -1 +1 @@ -abe20c626d613e73ccb1a3f8468ad1b9aecca528afa9e8131a411d754eb86b8ab64a6fb1fdc9c0b8b8158ff7c82f548de5912041bf035aa5a2d4532cfe0c9510 \ No newline at end of file +7f7465abaf559b3ef56cb6b0f28050c12f392f55db33dc5d2cefc14b92beb2c9068834c05273e51323d3516643e8a385e4c177a7a471678c961808d19055a30f \ No newline at end of file diff --git a/tests/test_mg_nuclide/inputs_true.dat b/tests/test_mg_nuclide/inputs_true.dat index eb643bbaf..32a7773c1 100644 --- a/tests/test_mg_nuclide/inputs_true.dat +++ b/tests/test_mg_nuclide/inputs_true.dat @@ -1 +1 @@ -c9f9e7211bfb2af58130bedfd64592d093b7bfa424953eba433ecf08940595a96b8de7a892f12d1ab465cebd8e5dd784114c1b1299b534ed329df92752c9ed1f \ No newline at end of file +825dee3ca35d48788f1a4d5364789bbd83b36e33af9a990da758dd73c3bfcbee14bce2a41e6c80e0147f45575e59078653c8dfa8590cd361c09f19c26dc8c88e \ No newline at end of file diff --git a/tests/test_mg_tallies/inputs_true.dat b/tests/test_mg_tallies/inputs_true.dat index 304d2e888..41bbd2136 100644 --- a/tests/test_mg_tallies/inputs_true.dat +++ b/tests/test_mg_tallies/inputs_true.dat @@ -1 +1 @@ -ca8490e0e4549fed727ddc75b6d92cfe5162e11b905218a0afaa3ce2ee0763e2ff38074de27aaa678818624f49c5823650475dfa8f66f502a98fc03145399c0d \ No newline at end of file +6c437c3f9281c52a80a9b166971aa0f5db7ff8b6cf65c79b6d7bf294fad30cc7044f6a665cd9059f8580441bcbb581f7152ff5bccbc21fbcc407847ea6fe3306 \ No newline at end of file diff --git a/tests/test_mgxs_library_condense/inputs_true.dat b/tests/test_mgxs_library_condense/inputs_true.dat index b94f64122..51fc95c60 100644 --- a/tests/test_mgxs_library_condense/inputs_true.dat +++ b/tests/test_mgxs_library_condense/inputs_true.dat @@ -1 +1 @@ -53b1740921b71e4ead909ab9e4c25f7d43990fe7d7051fde6f66c39c0a6082177385640244010e1b9dbeaf5f34adf1627e9603088af729fadd6b589c19102edc \ No newline at end of file +3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/inputs_true.dat b/tests/test_mgxs_library_distribcell/inputs_true.dat index 04e56658f..78ffa3faf 100644 --- a/tests/test_mgxs_library_distribcell/inputs_true.dat +++ b/tests/test_mgxs_library_distribcell/inputs_true.dat @@ -1 +1 @@ -224a9e84e87c8a21385326d34ef27c046107d4a2ace6ee85d7a36142a3726e12532e2fc1a318ab707437e0b306a81c6d2b80c531d4c3210d4162242e6265ba70 \ No newline at end of file +2c078f650fed5fc241f42b2d7404fb7fae59d782102fad66b4cd2c8a4b1f266d64e8ce1ec0556117c2a2b1fe49aa583f340dc43df3ddc9320557aa97bb554c05 \ No newline at end of file diff --git a/tests/test_mgxs_library_hdf5/inputs_true.dat b/tests/test_mgxs_library_hdf5/inputs_true.dat index b94f64122..51fc95c60 100644 --- a/tests/test_mgxs_library_hdf5/inputs_true.dat +++ b/tests/test_mgxs_library_hdf5/inputs_true.dat @@ -1 +1 @@ -53b1740921b71e4ead909ab9e4c25f7d43990fe7d7051fde6f66c39c0a6082177385640244010e1b9dbeaf5f34adf1627e9603088af729fadd6b589c19102edc \ No newline at end of file +3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/inputs_true.dat b/tests/test_mgxs_library_no_nuclides/inputs_true.dat index b94f64122..51fc95c60 100644 --- a/tests/test_mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_no_nuclides/inputs_true.dat @@ -1 +1 @@ -53b1740921b71e4ead909ab9e4c25f7d43990fe7d7051fde6f66c39c0a6082177385640244010e1b9dbeaf5f34adf1627e9603088af729fadd6b589c19102edc \ No newline at end of file +3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/inputs_true.dat b/tests/test_mgxs_library_nuclides/inputs_true.dat index f87bc242d..9436f03a0 100644 --- a/tests/test_mgxs_library_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_nuclides/inputs_true.dat @@ -1 +1 @@ -c6a2a1c707bc723fd38bafd18efcfb22beaac0bd5953d7524ced1d47866cc1e1ee4152e39234d32a06fe43aff446fb12f8c5b62a44075607f274778b49110762 \ No newline at end of file +b035f783fa75ada619b0a58675913e318fef94e519c85cae6982f650d7655cb130f625572fde2058e005b490359180cb9d1e1095f5d35d41c9a0f8ff6e0dc3c1 \ No newline at end of file diff --git a/tests/test_tallies/inputs_true.dat b/tests/test_tallies/inputs_true.dat index 657a9e77d..be789fc83 100644 --- a/tests/test_tallies/inputs_true.dat +++ b/tests/test_tallies/inputs_true.dat @@ -1 +1 @@ -5e168146d91b7b5fadecb80a32df9edc906718fb2d70b68b4c18dbed0641739251a1c16177c9f4d47516dfd528ec930879534292ff0eb82af89eca2c3fa4a3e0 \ No newline at end of file +0597eff3fddbc45a09b5b324c9704e540b694b07c136f2040426fdcfe5ec544f036073e4afa34a5fb0fbd721a4c0a609b9b68bf17ce4ec78302023b46b71930c \ No newline at end of file diff --git a/tests/test_tally_aggregation/inputs_true.dat b/tests/test_tally_aggregation/inputs_true.dat index 7b4276f59..055ac76fd 100644 --- a/tests/test_tally_aggregation/inputs_true.dat +++ b/tests/test_tally_aggregation/inputs_true.dat @@ -1 +1 @@ -530a5e969901e153531f74aed46246b1e8783a0e2f347e472f7554c9970152f45d85499f17d7df9c35c74fed6f78d449aa70bf0c1f8947cd34d3a829483a0055 \ No newline at end of file +f819f1b3564ca1df1e235f120f4bd65003cd80935fa8261f0a5982b7e7ec5b2e7497716673c142fab99f3fb26c174ac7a12e145b9a6f2caf707d2a07702f6eb2 \ No newline at end of file diff --git a/tests/test_tally_arithmetic/inputs_true.dat b/tests/test_tally_arithmetic/inputs_true.dat index 1b6046f1a..d7b854a51 100644 --- a/tests/test_tally_arithmetic/inputs_true.dat +++ b/tests/test_tally_arithmetic/inputs_true.dat @@ -1 +1 @@ -57384883e37964076aa82c19fa542434331cdb09735d710485b5aa0ca3445d543729e40cb9c7b6a70e7101ef186923eb1ff6315c73b01ff257052838add68fc7 \ No newline at end of file +bb7e730630f7bb4694a27fd77c3c0171f70c78df2681acc26b0ef88bcff367523b11335f487b46269325adbcee7faeb756484af64055c3c91b0103f7ed962053 \ No newline at end of file diff --git a/tests/test_tally_slice_merge/inputs_true.dat b/tests/test_tally_slice_merge/inputs_true.dat index 29f0f1d82..be2ec63dc 100644 --- a/tests/test_tally_slice_merge/inputs_true.dat +++ b/tests/test_tally_slice_merge/inputs_true.dat @@ -1 +1 @@ -8d1ab9e4add51b99045e990ac9c3dad9447e9720d811bc430d4bfdd7c2c035424bcb7750e4a4d0ec0460ea1ef4be46ac58372ed01d55f5d8cfeebbce75559066 \ No newline at end of file +bb4ae3b75445846bd5db05a06cc20e7589990154ccef8302f276cd8356630d585c513ebb6bfa99f9fc93dd2d30c42bfbb67dd3454134f4c9fcb3bac128d1f1c5 \ No newline at end of file From cccca4062aea16d8894a2257173ce33fad0a25d3 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 09:04:52 -0500 Subject: [PATCH 038/147] Goodbye openmc.Executor. Hello openmc.run and openmc.plot. --- openmc/executor.py | 177 ++++++++---------- tests/test_plot/test_plot.py | 5 +- .../test_statepoint_restart.py | 17 +- tests/testing_harness.py | 25 +-- 4 files changed, 92 insertions(+), 132 deletions(-) diff --git a/openmc/executor.py b/openmc/executor.py index 214517d6e..89bcc2e10 100644 --- a/openmc/executor.py +++ b/openmc/executor.py @@ -1,131 +1,100 @@ from __future__ import print_function import subprocess from numbers import Integral -import os import sys -from openmc.checkvalue import check_type - if sys.version_info[0] >= 3: basestring = str -class Executor(object): - """Control execution of OpenMC +def _run(command, output, cwd): + # Launch a subprocess + p = subprocess.Popen(command, shell=True, cwd=cwd, stdout=subprocess.PIPE, + universal_newlines=True) - Attributes + # Capture and re-print OpenMC output in real-time + while True: + # If OpenMC is finished, break loop + line = p.stdout.readline() + if not line and p.poll() != None: + break + + # If user requested output, print to screen + if output: + print(line, end='') + + # Return the returncode (integer, zero if no problems encountered) + return p.returncode + + +def plot(output=True, openmc_exec='openmc', cwd='.'): + """Run OpenMC in plotting mode + + Parameters ---------- - working_directory : str - Path to working directory to run in + output : bool + Capture OpenMC output from standard out + openmc_exec : str + Path to OpenMC executable + cwd : str, optional + Path to working directory to run in. Defaults to the current working directory. """ - def __init__(self): - self._working_directory = '.' + return _run(openmc_exec + ' -p', output, cwd) - def _run_openmc(self, command, output): - # Launch a subprocess to run OpenMC - p = subprocess.Popen(command, shell=True, - cwd=self._working_directory, - stdout=subprocess.PIPE, - universal_newlines=True) - # Capture and re-print OpenMC output in real-time - while True: - # If OpenMC is finished, break loop - line = p.stdout.readline() - if not line and p.poll() != None: - break +def run(particles=None, threads=None, geometry_debug=False, + restart_file=None, tracks=False, mpi_procs=1, output=True, + openmc_exec='openmc', mpi_exec='mpiexec', cwd='.'): + """Run an OpenMC simulation. - # If user requested output, print to screen - if output: - print(line, end='') + Parameters + ---------- + particles : int, optional + Number of particles to simulate per generation. + threads : int, optional + Number of OpenMP threads. + geometry_debug : bool, optional + Turn on geometry debugging during simulation. Defaults to False. + restart_file : str, optional + Path to restart file to use + tracks : bool, optional + Write tracks for all particles. Defaults to False. + mpi_procs : int, optional + Number of MPI processes. + output : bool, optional + Capture OpenMC output from standard out. Defaults to True. + openmc_exec : str, optional + Path to OpenMC executable. Defaults to 'openmc'. + mpi_exec : str, optional + MPI execute command. Defaults to 'mpiexec'. + cwd : str, optional + Path to working directory to run in. Defaults to the current working directory. - # Return the returncode (integer, zero if no problems encountered) - return p.returncode + """ - @property - def working_directory(self): - return self._working_directory + post_args = ' ' + pre_args = '' - @working_directory.setter - def working_directory(self, working_directory): - check_type("Executor's working directory", working_directory, - basestring) - if not os.path.isdir(working_directory): - msg = 'Unable to set Executor\'s working directory to "{0}" ' \ - 'which does not exist'.format(working_directory) - raise ValueError(msg) + if isinstance(particles, Integral) and particles > 0: + post_args += '-n {0} '.format(particles) - self._working_directory = working_directory + if isinstance(threads, Integral) and threads > 0: + post_args += '-s {0} '.format(threads) - def plot_geometry(self, output=True, openmc_exec='openmc'): - """Run OpenMC in plotting mode""" + if geometry_debug: + post_args += '-g ' - return self._run_openmc(openmc_exec + ' -p', output) + if isinstance(restart_file, basestring): + post_args += '-r {0} '.format(restart_file) - def run_simulation(self, particles=None, threads=None, - geometry_debug=False, restart_file=None, - tracks=False, mpi_procs=1, output=True, - openmc_exec='openmc', mpi_exec=None): - """Run an OpenMC simulation. + if tracks: + post_args += '-t' - Parameters - ---------- - particles : int - Number of particles to simulate per generation - threads : int - Number of OpenMP threads - geometry_debug : bool - Turn on geometry debugging during simulation - restart_file : str - Path to restart file to use - tracks : bool - Write tracks for all particles - mpi_procs : int - Number of MPI processes - output : bool - Capture OpenMC output from standard out - openmc_exec : str - Path to OpenMC executable + if isinstance(mpi_procs, Integral) and mpi_procs > 1: + pre_args += '{} -n {} '.format(mpi_exec, mpi_procs) - """ + command = pre_args + openmc_exec + ' ' + post_args - post_args = ' ' - pre_args = '' - - if isinstance(particles, Integral) and particles > 0: - post_args += '-n {0} '.format(particles) - - if isinstance(threads, Integral) and threads > 0: - post_args += '-s {0} '.format(threads) - - if geometry_debug: - post_args += '-g ' - - if isinstance(restart_file, basestring): - post_args += '-r {0} '.format(restart_file) - - if tracks: - post_args += '-t' - - if isinstance(mpi_procs, Integral) and mpi_procs > 1: - np_present = True - else: - np_present = False - - if mpi_exec is not None and isinstance(mpi_exec, basestring): - mpi_exec_present = True - else: - mpi_exec_present = False - - if np_present or mpi_exec_present: - if mpi_exec_present: - pre_args += mpi_exec + ' ' - else: - pre_args += 'mpirun ' - pre_args += '-n {0} '.format(mpi_procs) - - command = pre_args + openmc_exec + ' ' + post_args - - return self._run_openmc(command, output) + return _run(command, output, cwd) diff --git a/tests/test_plot/test_plot.py b/tests/test_plot/test_plot.py index 015577d21..e40cef49c 100644 --- a/tests/test_plot/test_plot.py +++ b/tests/test_plot/test_plot.py @@ -9,7 +9,7 @@ from testing_harness import TestHarness import h5py -from openmc import Executor +import openmc class PlotTestHarness(TestHarness): @@ -19,8 +19,7 @@ class PlotTestHarness(TestHarness): self._plot_names = plot_names def _run_openmc(self): - executor = Executor() - returncode = executor.plot_geometry(openmc_exec=self._opts.exe) + returncode = openmc.plot(openmc_exec=self._opts.exe) assert returncode == 0, 'OpenMC did not exit successfully.' def _test_output_created(self): diff --git a/tests/test_statepoint_restart/test_statepoint_restart.py b/tests/test_statepoint_restart/test_statepoint_restart.py index c842689d9..d39bf7cd5 100644 --- a/tests/test_statepoint_restart/test_statepoint_restart.py +++ b/tests/test_statepoint_restart/test_statepoint_restart.py @@ -5,8 +5,7 @@ import os import sys sys.path.insert(0, os.pardir) from testing_harness import TestHarness -from openmc.statepoint import StatePoint -from openmc.executor import Executor +import openmc class StatepointRestartTestHarness(TestHarness): @@ -50,17 +49,15 @@ class StatepointRestartTestHarness(TestHarness): statepoint = statepoint[0] # Run OpenMC - executor = Executor() - if self._opts.mpi_exec is not None: - returncode = executor.run_simulation(mpi_procs=self._opts.mpi_np, - restart_file=statepoint, - openmc_exec=self._opts.exe, - mpi_exec=self._opts.mpi_exec) + returncode = openmc.run(mpi_procs=self._opts.mpi_np, + restart_file=statepoint, + openmc_exec=self._opts.exe, + mpi_exec=self._opts.mpi_exec) else: - returncode = executor.run_simulation(openmc_exec=self._opts.exe, - restart_file=statepoint) + returncode = openmc.run(openmc_exec=self._opts.exe, + restart_file=statepoint) assert returncode == 0, 'OpenMC did not exit successfully.' diff --git a/tests/testing_harness.py b/tests/testing_harness.py index 7d6dbc914..78e5553e8 100644 --- a/tests/testing_harness.py +++ b/tests/testing_harness.py @@ -13,9 +13,7 @@ import numpy as np sys.path.insert(0, os.path.join(os.pardir, os.pardir)) from input_set import InputSet, MGInputSet -from openmc.statepoint import StatePoint -from openmc.executor import Executor -import openmc.particle_restart as pr +import openmc class TestHarness(object): @@ -63,15 +61,13 @@ class TestHarness(object): self._cleanup() def _run_openmc(self): - executor = Executor() - if self._opts.mpi_exec is not None: - returncode = executor.run_simulation(mpi_procs=self._opts.mpi_np, - openmc_exec=self._opts.exe, - mpi_exec=self._opts.mpi_exec) + returncode = openmc.run(mpi_procs=self._opts.mpi_np, + openmc_exec=self._opts.exe, + mpi_exec=self._opts.mpi_exec) else: - returncode = executor.run_simulation(openmc_exec=self._opts.exe) + returncode = openmc.run(openmc_exec=self._opts.exe) assert returncode == 0, 'OpenMC did not exit successfully.' @@ -90,7 +86,7 @@ class TestHarness(object): """Digest info in the statepoint and return as a string.""" # Read the statepoint file. statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] - sp = StatePoint(statepoint) + sp = openmc.StatePoint(statepoint) # Write out k-combined. outstr = 'k-combined:\n' @@ -158,7 +154,7 @@ class CMFDTestHarness(TestHarness): """Digest info in the statepoint and return as a string.""" # Read the statepoint file. statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] - sp = StatePoint(statepoint) + sp = openmc.StatePoint(statepoint) # Write out the eigenvalue and tallies. outstr = super(CMFDTestHarness, self)._get_results() @@ -195,13 +191,12 @@ class ParticleRestartTestHarness(TestHarness): 'mpi_exec': self._opts.mpi_exec}) # Initial run - executor = Executor() - returncode = executor.run_simulation(**args) + returncode = openmc.run(**args) assert returncode == 0, 'OpenMC did not exit successfully.' # Run particle restart args.update({'restart_file': self._sp_name}) - returncode = executor.run_simulation(**args) + returncode = openmc.run(**args) assert returncode == 0, 'OpenMC did not exit successfully.' def _test_output_created(self): @@ -216,7 +211,7 @@ class ParticleRestartTestHarness(TestHarness): """Digest info in the statepoint and return as a string.""" # Read the particle restart file. particle = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] - p = pr.Particle(particle) + p = openmc.Particle(particle) # Write out the properties. outstr = '' From a855e8f1b04f3983b699422c9d938d21f2f3315c Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 09:31:40 -0500 Subject: [PATCH 039/147] Increase MAX_EVENTS to 1 million --- src/constants.F90 | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/src/constants.F90 b/src/constants.F90 index 8863ca18c..5b58f409d 100644 --- a/src/constants.F90 +++ b/src/constants.F90 @@ -37,7 +37,7 @@ module constants real(8), parameter :: FP_COINCIDENT = 1e-12_8 ! Maximum number of collisions/crossings - integer, parameter :: MAX_EVENTS = 10000 + integer, parameter :: MAX_EVENTS = 1000000 integer, parameter :: MAX_SAMPLE = 100000 ! Maximum number of secondary particles created From 50a80693b5d4ac0fb1bc0e88a4c105338c35601e Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 10:37:06 -0500 Subject: [PATCH 040/147] Rename main Python API classes to get rid of File. --- docs/source/_templates/myfunction.rst | 6 ++ docs/source/pythonapi/index.rst | 18 ++--- examples/python/basic/build-xml.py | 28 ++++---- examples/python/boxes/build-xml.py | 20 +++--- .../python/lattice/hexagonal/build-xml.py | 28 ++++---- examples/python/lattice/nested/build-xml.py | 34 ++++----- examples/python/lattice/simple/build-xml.py | 34 ++++----- examples/python/pincell/build-xml.py | 28 ++++---- .../python/pincell_multigroup/build-xml.py | 32 ++++----- examples/python/reflective/build-xml.py | 22 +++--- openmc/cmfd.py | 2 +- openmc/executor.py | 2 +- openmc/geometry.py | 71 ++++++------------- openmc/material.py | 9 ++- openmc/mgxs/library.py | 6 +- openmc/mgxs_library.py | 9 ++- openmc/plots.py | 5 +- openmc/settings.py | 2 +- openmc/tallies.py | 7 +- tests/input_set.py | 26 ++----- .../test_asymmetric_lattice.py | 10 ++- tests/test_distribmat/test_distribmat.py | 10 ++- tests/test_mg_max_order/test_mg_max_order.py | 2 +- tests/test_mg_nuclide/test_mg_nuclide.py | 2 +- tests/test_mg_tallies/test_mg_tallies.py | 2 +- .../test_mgxs_library_condense.py | 4 +- .../test_mgxs_library_distribcell.py | 4 +- .../test_mgxs_library_hdf5.py | 8 +-- .../test_mgxs_library_no_nuclides.py | 4 +- .../test_mgxs_library_nuclides.py | 4 +- tests/test_plot/test_plot.py | 2 +- .../test_resonance_scattering.py | 8 +-- tests/test_source/test_source.py | 16 ++--- tests/test_tallies/test_tallies.py | 4 +- .../test_tally_aggregation.py | 2 +- .../test_tally_arithmetic.py | 2 +- .../test_tally_slice_merge.py | 14 ++-- 37 files changed, 203 insertions(+), 284 deletions(-) create mode 100644 docs/source/_templates/myfunction.rst diff --git a/docs/source/_templates/myfunction.rst b/docs/source/_templates/myfunction.rst new file mode 100644 index 000000000..4d7ea38a1 --- /dev/null +++ b/docs/source/_templates/myfunction.rst @@ -0,0 +1,6 @@ +{{ fullname }} +{{ underline }} + +.. currentmodule:: {{ module }} + +.. autofunction:: {{ objname }} diff --git a/docs/source/pythonapi/index.rst b/docs/source/pythonapi/index.rst index 9fd70cb5a..3bedaf2c7 100644 --- a/docs/source/pythonapi/index.rst +++ b/docs/source/pythonapi/index.rst @@ -29,7 +29,7 @@ Classes :template: myclass.rst openmc.XSdata - openmc.MGXSLibraryFile + openmc.MGXSLibrary Functions +++++++++ @@ -50,7 +50,7 @@ Simulation Settings openmc.Source openmc.ResonanceScattering - openmc.SettingsFile + openmc.Settings Material Specification ---------------------- @@ -64,7 +64,7 @@ Material Specification openmc.Element openmc.Macroscopic openmc.Material - openmc.MaterialsFile + openmc.Materials Building geometry ----------------- @@ -96,7 +96,6 @@ Building geometry openmc.RectLattice openmc.HexLattice openmc.Geometry - openmc.GeometryFile Many of the above classes are derived from several abstract classes: @@ -121,7 +120,7 @@ Constructing Tallies openmc.Mesh openmc.Trigger openmc.Tally - openmc.TalliesFile + openmc.Tallies Coarse Mesh Finite Difference Acceleration ------------------------------------------ @@ -132,7 +131,7 @@ Coarse Mesh Finite Difference Acceleration :template: myclass.rst openmc.CMFDMesh - openmc.CMFDFile + openmc.CMFD Plotting -------- @@ -143,7 +142,7 @@ Plotting :template: myclass.rst openmc.Plot - openmc.PlotsFile + openmc.Plots Running OpenMC -------------- @@ -151,9 +150,10 @@ Running OpenMC .. autosummary:: :toctree: generated :nosignatures: - :template: myclass.rst + :template: myfunction.rst - openmc.Executor + openmc.run + openmc.plot_geometry Post-processing --------------- diff --git a/examples/python/basic/build-xml.py b/examples/python/basic/build-xml.py index fbe683661..19737cf91 100644 --- a/examples/python/basic/build-xml.py +++ b/examples/python/basic/build-xml.py @@ -12,7 +12,7 @@ particles = 10000 ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate some Nuclides @@ -31,15 +31,15 @@ fuel = openmc.Material(material_id=40, name='fuel') fuel.set_density('g/cc', 4.5) fuel.add_nuclide(u235, 1.) -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials collection, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate ZCylinder surfaces @@ -74,22 +74,18 @@ cell1.fill = universe1 universe1.add_cells([cell2, cell3]) root.add_cells([cell1, cell4]) -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -103,7 +99,7 @@ settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC tallies.xml File +# Exporting to OpenMC tallies.xml file ############################################################################### # Instantiate some tally Filters @@ -128,8 +124,8 @@ third_tally = openmc.Tally(tally_id=3, name='third tally') third_tally.filters = [cell_filter, energy_filter, energyout_filter] third_tally.scores = ['scatter', 'nu-scatter', 'nu-fission'] -# Instantiate a TalliesFile, register all Tallies, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register all Tallies, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_tally(first_tally) tallies_file.add_tally(second_tally) tallies_file.add_tally(third_tally) diff --git a/examples/python/boxes/build-xml.py b/examples/python/boxes/build-xml.py index ea3e81d17..196a10ca7 100644 --- a/examples/python/boxes/build-xml.py +++ b/examples/python/boxes/build-xml.py @@ -36,15 +36,15 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([fuel1, fuel2, moderator]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate planar surfaces @@ -97,14 +97,10 @@ outer_box.fill = moderator root = openmc.Universe(universe_id=0, name='root universe') root.add_cells([inner_box, middle_box, outer_box]) -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### @@ -112,7 +108,7 @@ geometry_file.export_to_xml() ############################################################################### # Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -133,7 +129,7 @@ plot.width = [20, 20] plot.pixels = [200, 200] plot.color = 'cell' -# Instantiate a PlotsFile, add Plot, and export to XML -plot_file = openmc.PlotsFile() +# Instantiate a Plots object, add Plot, and export to XML +plot_file = openmc.Plots() plot_file.add_plot(plot) plot_file.export_to_xml() diff --git a/examples/python/lattice/hexagonal/build-xml.py b/examples/python/lattice/hexagonal/build-xml.py index 7f92e6602..a9d7f6899 100644 --- a/examples/python/lattice/hexagonal/build-xml.py +++ b/examples/python/lattice/hexagonal/build-xml.py @@ -35,15 +35,15 @@ iron = openmc.Material(material_id=3, name='iron') iron.set_density('g/cc', 7.9) iron.add_nuclide(fe56, 1.) -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel, iron]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate Surfaces @@ -105,22 +105,18 @@ lattice.outer = univ2 # Fill Cell with the Lattice cell1.fill = lattice -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### # Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -137,7 +133,7 @@ settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC plots.xml File +# Exporting to OpenMC plots.xml file ############################################################################### plot_xy = openmc.Plot(plot_id=1) @@ -155,8 +151,8 @@ plot_yz.width = [8, 8] plot_yz.pixels = [400, 400] plot_yz.color = 'mat' -# Instantiate a PlotsFile, add Plot, and export to XML -plot_file = openmc.PlotsFile() +# Instantiate a Plots object, add plots, and export to XML +plot_file = openmc.Plots() plot_file.add_plot(plot_xy) plot_file.add_plot(plot_yz) plot_file.export_to_xml() @@ -171,7 +167,7 @@ tally = openmc.Tally(tally_id=1) tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])] tally.scores = ['total'] -# Instantiate a TalliesFile, register Tally/Mesh, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register Tally/Mesh, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/lattice/nested/build-xml.py b/examples/python/lattice/nested/build-xml.py index f54f06453..eb16c8327 100644 --- a/examples/python/lattice/nested/build-xml.py +++ b/examples/python/lattice/nested/build-xml.py @@ -11,7 +11,7 @@ particles = 10000 ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate some Nuclides @@ -30,15 +30,15 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate Surfaces @@ -116,22 +116,18 @@ lattice2.universes = [[univ4, univ4], cell1.fill = lattice2 cell2.fill = lattice1 -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -145,7 +141,7 @@ settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC plots.xml File +# Exporting to OpenMC plots.xml file ############################################################################### plot = openmc.Plot(plot_id=1) @@ -154,14 +150,14 @@ plot.width = [4, 4] plot.pixels = [400, 400] plot.color = 'mat' -# Instantiate a PlotsFile, add Plot, and export to XML -plot_file = openmc.PlotsFile() +# Instantiate a Plots object, add Plot, and export to XML +plot_file = openmc.Plots() plot_file.add_plot(plot) plot_file.export_to_xml() ############################################################################### -# Exporting to OpenMC tallies.xml File +# Exporting to OpenMC tallies.xml file ############################################################################### # Instantiate a tally mesh @@ -180,8 +176,8 @@ tally = openmc.Tally(tally_id=1) tally.filters = [mesh_filter] tally.scores = ['total'] -# Instantiate a TalliesFile, register Tally/Mesh, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register Tally/Mesh, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/lattice/simple/build-xml.py b/examples/python/lattice/simple/build-xml.py index f633fa96f..6e44e4da0 100644 --- a/examples/python/lattice/simple/build-xml.py +++ b/examples/python/lattice/simple/build-xml.py @@ -11,7 +11,7 @@ particles = 10000 ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate some Nuclides @@ -30,15 +30,15 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate Surfaces @@ -106,22 +106,18 @@ lattice.universes = [[univ1, univ2, univ1, univ2], # Fill Cell with the Lattice cell1.fill = lattice -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -137,7 +133,7 @@ settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC plots.xml File +# Exporting to OpenMC plots.xml file ############################################################################### plot = openmc.Plot(plot_id=1) @@ -146,14 +142,14 @@ plot.width = [4, 4] plot.pixels = [400, 400] plot.color = 'mat' -# Instantiate a PlotsFile, add Plot, and export to XML -plot_file = openmc.PlotsFile() +# Instantiate a Plots object, add Plot, and export to XML +plot_file = openmc.Plots() plot_file.add_plot(plot) plot_file.export_to_xml() ############################################################################### -# Exporting to OpenMC tallies.xml File +# Exporting to OpenMC tallies.xml file ############################################################################### # Instantiate a tally mesh @@ -177,8 +173,8 @@ tally.filters = [mesh_filter] tally.scores = ['total'] tally.triggers = [trigger] -# Instantiate a TalliesFile, register Tally/Mesh, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register Tally/Mesh, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/pincell/build-xml.py b/examples/python/pincell/build-xml.py index 2e72d82ab..10cd4944d 100644 --- a/examples/python/pincell/build-xml.py +++ b/examples/python/pincell/build-xml.py @@ -11,7 +11,7 @@ particles = 1000 ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate some Nuclides @@ -100,15 +100,15 @@ borated_water.add_nuclide(o16, 2.4672e-2) borated_water.add_nuclide(o17, 6.0099e-5) borated_water.add_s_alpha_beta('HH2O', '71t') -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([uo2, helium, zircaloy, borated_water]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate ZCylinder surfaces @@ -149,22 +149,18 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cells with Universe root.add_cells([fuel, gap, clad, water]) -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles @@ -181,7 +177,7 @@ settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC tallies.xml File +# Exporting to OpenMC tallies.xml file ############################################################################### # Instantiate a tally mesh @@ -201,8 +197,8 @@ tally = openmc.Tally(tally_id=1, name='tally 1') tally.filters = [energy_filter, mesh_filter] tally.scores = ['flux', 'fission', 'nu-fission'] -# Instantiate a TalliesFile, register all Tallies, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register all Tallies, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/pincell_multigroup/build-xml.py b/examples/python/pincell_multigroup/build-xml.py index 60026c089..233728142 100644 --- a/examples/python/pincell_multigroup/build-xml.py +++ b/examples/python/pincell_multigroup/build-xml.py @@ -12,7 +12,7 @@ inactive = 10 particles = 1000 ############################################################################### -# Exporting to OpenMC mg_cross_sections.xml File +# Exporting to OpenMC mg_cross_sections.xml file ############################################################################### # Instantiate the energy group data @@ -59,13 +59,13 @@ scatter = [[[0.0444777, 0.1134000, 0.0007235, 0.0000037, 0.0000001, 0.0000000, 0 [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.1324400, 2.4807000]]] h2o_xsdata.scatter = np.array(scatter) -mg_cross_sections_file = openmc.MGXSLibraryFile(groups) +mg_cross_sections_file = openmc.MGXSLibrary(groups) mg_cross_sections_file.add_xsdatas([uo2_xsdata,h2o_xsdata]) mg_cross_sections_file.export_to_xml() ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate some Macroscopic Data @@ -81,15 +81,15 @@ water = openmc.Material(material_id=2, name='Water') water.set_density('macro', 1.0) water.add_macroscopic(h2o_data) -# Instantiate a MaterialsFile, register all Materials, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register all Materials, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '300K' materials_file.add_materials([uo2, water]) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate ZCylinder surfaces @@ -122,22 +122,18 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cells with Universe root.add_cells([fuel, moderator]) -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.energy_mode = "multi-group" settings_file.cross_sections = "./mg_cross_sections.xml" settings_file.batches = batches @@ -152,7 +148,7 @@ settings_file.source = openmc.source.Source(space=uniform_dist) settings_file.export_to_xml() ############################################################################### -# Exporting to OpenMC tallies.xml File +# Exporting to OpenMC tallies.xml file ############################################################################### # Instantiate a tally mesh @@ -177,8 +173,8 @@ tally.add_score('flux') tally.add_score('fission') tally.add_score('nu-fission') -# Instantiate a TalliesFile, register all Tallies, and export to XML -tallies_file = openmc.TalliesFile() +# Instantiate a Tallies object, register all Tallies, and export to XML +tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/reflective/build-xml.py b/examples/python/reflective/build-xml.py index 01a5c7815..7d96e296d 100644 --- a/examples/python/reflective/build-xml.py +++ b/examples/python/reflective/build-xml.py @@ -12,7 +12,7 @@ particles = 10000 ############################################################################### -# Exporting to OpenMC materials.xml File +# Exporting to OpenMC materials.xml file ############################################################################### # Instantiate a Nuclides @@ -23,15 +23,15 @@ fuel = openmc.Material(material_id=1, name='fuel') fuel.set_density('g/cc', 4.5) fuel.add_nuclide(u235, 1.) -# Instantiate a MaterialsFile, register Material, and export to XML -materials_file = openmc.MaterialsFile() +# Instantiate a Materials object, register Material, and export to XML +materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_material(fuel) materials_file.export_to_xml() ############################################################################### -# Exporting to OpenMC geometry.xml File +# Exporting to OpenMC geometry.xml file ############################################################################### # Instantiate Surfaces @@ -64,22 +64,18 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cell with Universe root.add_cell(cell) -# Instantiate a Geometry and register the root Universe +# Instantiate a Geometry and register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root - -# Instantiate a GeometryFile, register Geometry, and export to XML -geometry_file = openmc.GeometryFile() -geometry_file.geometry = geometry -geometry_file.export_to_xml() +geometry.export_to_xml() ############################################################################### -# Exporting to OpenMC settings.xml File +# Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML -settings_file = openmc.SettingsFile() +# Instantiate a Settings object, set all runtime parameters, and export to XML +settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles diff --git a/openmc/cmfd.py b/openmc/cmfd.py index b9977a288..d4cce2af5 100644 --- a/openmc/cmfd.py +++ b/openmc/cmfd.py @@ -187,7 +187,7 @@ class CMFDMesh(object): return element -class CMFDFile(object): +class CMFD(object): """Parameters that control the use of coarse-mesh finite difference acceleration in OpenMC. This corresponds directly to the cmfd.xml input file. diff --git a/openmc/executor.py b/openmc/executor.py index 89bcc2e10..9bb3477c5 100644 --- a/openmc/executor.py +++ b/openmc/executor.py @@ -27,7 +27,7 @@ def _run(command, output, cwd): return p.returncode -def plot(output=True, openmc_exec='openmc', cwd='.'): +def plot_geometry(output=True, openmc_exec='openmc', cwd='.'): """Run OpenMC in plotting mode Parameters diff --git a/openmc/geometry.py b/openmc/geometry.py index f5dfe97e4..ed437f6e1 100644 --- a/openmc/geometry.py +++ b/openmc/geometry.py @@ -23,7 +23,6 @@ class Geometry(object): """ def __init__(self): - # Initialize Geometry class attributes self._root_universe = None self._offsets = {} @@ -42,6 +41,27 @@ class Geometry(object): self._root_universe = root_universe + def export_to_xml(self): + """Create a geometry.xml file that can be used for a simulation. + + """ + + # Clear OpenMC written IDs used to optimize XML generation + openmc.universe.WRITTEN_IDS = {} + + # Create XML representation + geometry_file = ET.Element("geometry") + self.root_universe.create_xml_subelement(geometry_file) + + # Clean the indentation in the file to be user-readable + sort_xml_elements(geometry_file) + clean_xml_indentation(geometry_file) + + # Write the XML Tree to the geometry.xml file + tree = ET.ElementTree(geometry_file) + tree.write("geometry.xml", xml_declaration=True, encoding='utf-8', + method="xml") + def get_cell_instance(self, path): """Return the instance number for the final cell in a geometry path. @@ -436,52 +456,3 @@ class Geometry(object): lattices = list(lattices) lattices.sort(key=lambda x: x.id) return lattices - - -class GeometryFile(object): - """Geometry file used for an OpenMC simulation. Corresponds directly to the - geometry.xml input file. - - Attributes - ---------- - geometry : openmc.Geometry - The geometry to be used - - """ - - def __init__(self): - # Initialize GeometryFile class attributes - self._geometry = None - self._geometry_file = ET.Element("geometry") - - @property - def geometry(self): - return self._geometry - - @geometry.setter - def geometry(self, geometry): - check_type('the geometry', geometry, Geometry) - self._geometry = geometry - - def export_to_xml(self): - """Create a geometry.xml file that can be used for a simulation. - - """ - - # Clear OpenMC written IDs used to optimize XML generation - openmc.universe.WRITTEN_IDS = {} - - # Reset xml element tree - self._geometry_file.clear() - - root_universe = self.geometry.root_universe - root_universe.create_xml_subelement(self._geometry_file) - - # Clean the indentation in the file to be user-readable - sort_xml_elements(self._geometry_file) - clean_xml_indentation(self._geometry_file) - - # Write the XML Tree to the geometry.xml file - tree = ET.ElementTree(self._geometry_file) - tree.write("geometry.xml", xml_declaration=True, - encoding='utf-8', method="xml") diff --git a/openmc/material.py b/openmc/material.py index 16af82439..6b0a0f246 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -642,8 +642,8 @@ class Material(object): return element -class MaterialsFile(object): - """Materials file used for an OpenMC simulation. Corresponds directly to the +class Materials(object): + """Materials used for an OpenMC simulation. Corresponds directly to the materials.xml input file. Attributes @@ -655,7 +655,6 @@ class MaterialsFile(object): """ def __init__(self): - # Initialize MaterialsFile class attributes self._materials = [] self._default_xs = None self._materials_file = ET.Element("materials") @@ -681,7 +680,7 @@ class MaterialsFile(object): if not isinstance(material, Material): msg = 'Unable to add a non-Material "{0}" to the ' \ - 'MaterialsFile'.format(material) + 'Materials instance'.format(material) raise ValueError(msg) self._materials.append(material) @@ -716,7 +715,7 @@ class MaterialsFile(object): if not isinstance(material, Material): msg = 'Unable to remove a non-Material "{0}" from the ' \ - 'MaterialsFile'.format(material) + 'Materials instance'.format(material) raise ValueError(msg) self._materials.remove(material) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 4de4bb48a..ca7bf39cd 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -354,8 +354,8 @@ class Library(object): Parameters ---------- - tallies_file : openmc.TalliesFile - A TalliesFile object to add each MGXS' tallies to generate a + tallies_file : openmc.Tallies + A Tallies object to add each MGXS' tallies to generate a "tallies.xml" input file for OpenMC merge : bool Indicate whether tallies should be merged when possible. Defaults @@ -363,7 +363,7 @@ class Library(object): """ - cv.check_type('tallies_file', tallies_file, openmc.TalliesFile) + cv.check_type('tallies_file', tallies_file, openmc.Tallies) # Add tallies from each MGXS for each domain and mgxs type for domain in self.domains: diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index c0b04fed1..8db3c84ff 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -647,7 +647,7 @@ class XSdata(object): return element -class MGXSLibraryFile(object): +class MGXSLibrary(object): """Multi-Group Cross Sections file used for an OpenMC simulation. Corresponds directly to the MG version of the cross_sections.xml input file. @@ -662,7 +662,6 @@ class MGXSLibraryFile(object): """ def __init__(self, energy_groups): - # Initialize MGXSLibraryFile class attributes self._xsdatas = [] self._energy_groups = energy_groups self._inverse_velocities = None @@ -701,12 +700,12 @@ class MGXSLibraryFile(object): # Check the type if not isinstance(xsdata, XSdata): msg = 'Unable to add a non-XSdata "{0}" to the ' \ - 'MGXSLibraryFile'.format(xsdata) + 'MGXSLibrary instance'.format(xsdata) raise ValueError(msg) # Make sure energy groups match. if xsdata.energy_groups != self._energy_groups: - msg = 'Energy groups of XSdata do not match that of MGXSLibraryFile!' + msg = 'Energy groups of XSdata do not match that of MGXSLibrary!' raise ValueError(msg) self._xsdatas.append(xsdata) @@ -741,7 +740,7 @@ class MGXSLibraryFile(object): if not isinstance(xsdata, XSdata): msg = 'Unable to remove a non-XSdata "{0}" from the ' \ - 'XSdatasFile'.format(xsdata) + 'MGXSLibrary instance'.format(xsdata) raise ValueError(msg) self._xsdatas.remove(xsdata) diff --git a/openmc/plots.py b/openmc/plots.py index 5e7c47743..ae34678bb 100644 --- a/openmc/plots.py +++ b/openmc/plots.py @@ -401,14 +401,13 @@ class Plot(object): return element -class PlotsFile(object): +class Plots(object): """Plots file used for an OpenMC simulation. Corresponds directly to the plots.xml input file. """ def __init__(self): - # Initialize PlotsFile class attributes self._plots = [] self._plots_file = ET.Element("plots") @@ -423,7 +422,7 @@ class PlotsFile(object): """ if not isinstance(plot, Plot): - msg = 'Unable to add a non-Plot "{0}" to the PlotsFile'.format(plot) + msg = 'Unable to add a non-Plot "{0}" to the Plots instance'.format(plot) raise ValueError(msg) self._plots.append(plot) diff --git a/openmc/settings.py b/openmc/settings.py index 0be50bc56..ec38bf54c 100644 --- a/openmc/settings.py +++ b/openmc/settings.py @@ -16,7 +16,7 @@ if sys.version_info[0] >= 3: basestring = str -class SettingsFile(object): +class Settings(object): """Settings file used for an OpenMC simulation. Corresponds directly to the settings.xml input file. diff --git a/openmc/tallies.py b/openmc/tallies.py index 2ee03c675..1af3b12bc 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -3419,14 +3419,13 @@ class Tally(object): return new_tally -class TalliesFile(object): +class Tallies(object): """Tallies file used for an OpenMC simulation. Corresponds directly to the tallies.xml input file. """ def __init__(self): - # Initialize TalliesFile class attributes self._tallies = [] self._meshes = [] self._tallies_file = ET.Element("tallies") @@ -3453,7 +3452,7 @@ class TalliesFile(object): """ if not isinstance(tally, Tally): - msg = 'Unable to add a non-Tally "{0}" to the TalliesFile'.format(tally) + msg = 'Unable to add a non-Tally "{0}" to the Tallies instance'.format(tally) raise ValueError(msg) if merge: @@ -3524,7 +3523,7 @@ class TalliesFile(object): """ if not isinstance(mesh, Mesh): - msg = 'Unable to add a non-Mesh "{0}" to the TalliesFile'.format(mesh) + msg = 'Unable to add a non-Mesh "{0}" to the Tallies instance'.format(mesh) raise ValueError(msg) self._meshes.append(mesh) diff --git a/tests/input_set.py b/tests/input_set.py index daff38ba1..3be6c1db4 100644 --- a/tests/input_set.py +++ b/tests/input_set.py @@ -5,9 +5,9 @@ from openmc.stats import Box class InputSet(object): def __init__(self): - self.settings = openmc.SettingsFile() - self.materials = openmc.MaterialsFile() - self.geometry = openmc.GeometryFile() + self.settings = openmc.Settings() + self.materials = openmc.Materials() + self.geometry = openmc.Geometry() self.tallies = None self.plots = None @@ -550,11 +550,8 @@ class InputSet(object): root.add_cells((c1, c2, c3, c4, c5, c6, c7, c8, c9, c10, c11, c12)) - # Define the geometry file. - geometry = openmc.Geometry() - geometry.root_universe = root - - self.geometry.geometry = geometry + # Assign root universe to geometry + self.geometry.root_universe = root def build_default_settings(self): self.settings.batches = 10 @@ -630,12 +627,8 @@ class MGInputSet(InputSet): root.add_cells((c1,c2,c3)) - # Define the geometry file. - geometry = openmc.Geometry() - geometry.root_universe = root - - self.geometry.geometry = geometry - + # Assign root universe to geometry + self.geometry.root_universe = root def build_default_settings(self): self.settings.batches = 10 @@ -656,8 +649,3 @@ class MGInputSet(InputSet): plot.color = 'mat' self.plots.add_plot(plot) - - - - - diff --git a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py index fdb21db33..94562e6d9 100644 --- a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py +++ b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py @@ -7,8 +7,6 @@ import hashlib sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness import openmc -from openmc.source import Source -from openmc.stats import Box class AsymmetricLatticeTestHarness(PyAPITestHarness): @@ -20,7 +18,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): self._input_set.build_default_materials_and_geometry() # Extract universes encapsulating fuel and water assemblies - geometry = self._input_set.geometry.geometry + geometry = self._input_set.geometry water = geometry.get_universes_by_name('water assembly (hot)')[0] fuel = geometry.get_universes_by_name('fuel assembly (hot)')[0] @@ -49,7 +47,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): root_univ.add_cell(root_cell) # Over-ride geometry in the input set with this 3x3 lattice - self._input_set.geometry.geometry.root_universe = root_univ + self._input_set.geometry.root_universe = root_univ # Initialize a "distribcell" filter for the fuel pin cell distrib_filter = openmc.Filter(type='distribcell', bins=[27]) @@ -60,7 +58,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): tally.add_score('nu-fission') # Initialize the tallies file - tallies_file = openmc.TalliesFile() + tallies_file = openmc.Tallies() tallies_file.add_tally(tally) # Assign the tallies file to the input set @@ -70,7 +68,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): self._input_set.build_default_settings() # Specify summary output and correct source sampling box - source = Source(space=Box([-32, -32, 0], [32, 32, 32])) + source = openmc.Source(space=openmc.stats.Box([-32, -32, 0], [32, 32, 32])) source.space.only_fissionable = True self._input_set.settings.source = source self._input_set.settings.output = {'summary': True} diff --git a/tests/test_distribmat/test_distribmat.py b/tests/test_distribmat/test_distribmat.py index a0608c108..ded2863bd 100644 --- a/tests/test_distribmat/test_distribmat.py +++ b/tests/test_distribmat/test_distribmat.py @@ -28,7 +28,7 @@ class DistribmatTestHarness(PyAPITestHarness): light_fuel.set_density('g/cc', 2.0) light_fuel.add_nuclide('U-235', 1.0) - mats_file = openmc.MaterialsFile() + mats_file = openmc.Materials() mats_file.default_xs = '71c' mats_file.add_materials([moderator, dense_fuel, light_fuel]) mats_file.export_to_xml() @@ -74,16 +74,14 @@ class DistribmatTestHarness(PyAPITestHarness): geometry = openmc.Geometry() geometry.root_universe = root_univ - geo_file = openmc.GeometryFile() - geo_file.geometry = geometry - geo_file.export_to_xml() + geometry.export_to_xml() #################### # Settings #################### - sets_file = openmc.SettingsFile() + sets_file = openmc.Settings() sets_file.batches = 5 sets_file.inactive = 0 sets_file.particles = 1000 @@ -96,7 +94,7 @@ class DistribmatTestHarness(PyAPITestHarness): # Plots #################### - plots_file = openmc.PlotsFile() + plots_file = openmc.Plots() plot = openmc.Plot(plot_id=1) plot.basis = 'xy' diff --git a/tests/test_mg_max_order/test_mg_max_order.py b/tests/test_mg_max_order/test_mg_max_order.py index 2f5ee4e4e..2c4db58df 100644 --- a/tests/test_mg_max_order/test_mg_max_order.py +++ b/tests/test_mg_max_order/test_mg_max_order.py @@ -68,7 +68,7 @@ class MGNuclideInputSet(MGInputSet): geometry = openmc.Geometry() geometry.root_universe = root - self.geometry.geometry = geometry + self.geometry = geometry class MGMaxOrderTestHarness(PyAPITestHarness): def __init__(self, statepoint_name, tallies_present, mg=False): diff --git a/tests/test_mg_nuclide/test_mg_nuclide.py b/tests/test_mg_nuclide/test_mg_nuclide.py index deb784bad..0fa7184a3 100644 --- a/tests/test_mg_nuclide/test_mg_nuclide.py +++ b/tests/test_mg_nuclide/test_mg_nuclide.py @@ -67,7 +67,7 @@ class MGNuclideInputSet(MGInputSet): geometry = openmc.Geometry() geometry.root_universe = root - self.geometry.geometry = geometry + self.geometry = geometry class MGNuclideTestHarness(PyAPITestHarness): def __init__(self, statepoint_name, tallies_present, mg=False): diff --git a/tests/test_mg_tallies/test_mg_tallies.py b/tests/test_mg_tallies/test_mg_tallies.py index c54fb4d32..ffc57f9e9 100644 --- a/tests/test_mg_tallies/test_mg_tallies.py +++ b/tests/test_mg_tallies/test_mg_tallies.py @@ -41,7 +41,7 @@ class MGTalliesTestHarness(PyAPITestHarness): tally2.add_score('scatter') tally2.add_score('nu-scatter') - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self._input_set.tallies.add_mesh(mesh) self._input_set.tallies.add_tally(tally1) self._input_set.tallies.add_tally(tally2) diff --git a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py index 82ce3acab..97bb853b6 100644 --- a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py +++ b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py @@ -23,7 +23,7 @@ class MGXSTestHarness(PyAPITestHarness): energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.]) # Initialize MGXS Library for a few cross section types - self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry.geometry) + self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry) self.mgxs_lib.by_nuclide = False self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] @@ -32,7 +32,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.build_library() # Initialize a tallies file - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() diff --git a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py index 1de21a603..681266186 100644 --- a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py +++ b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py @@ -24,7 +24,7 @@ class MGXSTestHarness(PyAPITestHarness): # Initialize MGXS Library for a few cross section types # for one material-filled cell in the geometry - self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry.geometry) + self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry) self.mgxs_lib.by_nuclide = False self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] @@ -35,7 +35,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.build_library() # Initialize a tallies file - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() diff --git a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py index 642073104..30be46b4c 100644 --- a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py +++ b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py @@ -24,7 +24,7 @@ class MGXSTestHarness(PyAPITestHarness): energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.]) # Initialize MGXS Library for a few cross section types - self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry.geometry) + self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry) self.mgxs_lib.by_nuclide = False self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] @@ -33,7 +33,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.build_library() # Initialize a tallies file - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() @@ -51,7 +51,7 @@ class MGXSTestHarness(PyAPITestHarness): # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) - + # Export the MGXS Library to an HDF5 file self.mgxs_lib.build_hdf5_store(directory='.') @@ -67,7 +67,7 @@ class MGXSTestHarness(PyAPITestHarness): outstr += str(f[key][...]) + '\n' key = 'material/{0}/{1}/std. dev.'.format(domain.id, mgxs_type) outstr += str(f[key][...]) + '\n' - + # Close the MGXS HDF5 file f.close() diff --git a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py index 2afa9039e..381b5b87c 100644 --- a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py +++ b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py @@ -23,7 +23,7 @@ class MGXSTestHarness(PyAPITestHarness): energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.]) # Initialize MGXS Library for a few cross section types - self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry.geometry) + self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry) self.mgxs_lib.by_nuclide = False self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] @@ -32,7 +32,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.build_library() # Initialize a tallies file - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() diff --git a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py index 173043cf0..c3e4f5f77 100644 --- a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py +++ b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py @@ -23,7 +23,7 @@ class MGXSTestHarness(PyAPITestHarness): energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.]) # Initialize MGXS Library for a few cross section types - self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry.geometry) + self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry) self.mgxs_lib.by_nuclide = True self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] @@ -32,7 +32,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.build_library() # Initialize a tallies file - self._input_set.tallies = openmc.TalliesFile() + self._input_set.tallies = openmc.Tallies() self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() diff --git a/tests/test_plot/test_plot.py b/tests/test_plot/test_plot.py index e40cef49c..606a1fd64 100644 --- a/tests/test_plot/test_plot.py +++ b/tests/test_plot/test_plot.py @@ -19,7 +19,7 @@ class PlotTestHarness(TestHarness): self._plot_names = plot_names def _run_openmc(self): - returncode = openmc.plot(openmc_exec=self._opts.exe) + returncode = openmc.plot_geometry(openmc_exec=self._opts.exe) assert returncode == 0, 'OpenMC did not exit successfully.' def _test_output_created(self): diff --git a/tests/test_resonance_scattering/test_resonance_scattering.py b/tests/test_resonance_scattering/test_resonance_scattering.py index d977488bf..5cecfedc4 100644 --- a/tests/test_resonance_scattering/test_resonance_scattering.py +++ b/tests/test_resonance_scattering/test_resonance_scattering.py @@ -17,7 +17,7 @@ class ResonanceScatteringTestHarness(PyAPITestHarness): mat.add_nuclide('Pu-239', 0.02) mat.add_nuclide('H-1', 20.0) - mats_file = openmc.MaterialsFile() + mats_file = openmc.Materials() mats_file.default_xs = '71c' mats_file.add_material(mat) mats_file.export_to_xml() @@ -35,9 +35,7 @@ class ResonanceScatteringTestHarness(PyAPITestHarness): geometry = openmc.Geometry() geometry.root_universe = root_univ - geo_file = openmc.GeometryFile() - geo_file.geometry = geometry - geo_file.export_to_xml() + geometry.export_to_xml() # Settings nuclide = openmc.Nuclide('U-238', '71c') @@ -67,7 +65,7 @@ class ResonanceScatteringTestHarness(PyAPITestHarness): res_scatt_ares.E_min = 1e-6 res_scatt_ares.E_max = 210e-6 - sets_file = openmc.SettingsFile() + sets_file = openmc.Settings() sets_file.batches = 10 sets_file.inactive = 5 sets_file.particles = 1000 diff --git a/tests/test_source/test_source.py b/tests/test_source/test_source.py index 9d303b06b..1e41bd10e 100644 --- a/tests/test_source/test_source.py +++ b/tests/test_source/test_source.py @@ -9,8 +9,6 @@ import numpy as np sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness import openmc -import openmc.stats -from openmc.source import Source class SourceTestHarness(PyAPITestHarness): @@ -18,7 +16,7 @@ class SourceTestHarness(PyAPITestHarness): mat1 = openmc.Material(material_id=1) mat1.set_density('g/cm3', 4.5) mat1.add_nuclide(openmc.Nuclide('U-235', '71c'), 1.0) - materials = openmc.MaterialsFile() + materials = openmc.Materials() materials.add_material(mat1) materials.export_to_xml() @@ -31,9 +29,7 @@ class SourceTestHarness(PyAPITestHarness): root.add_cell(inside_sphere) geometry = openmc.Geometry() geometry.root_universe = root - geometry_xml = openmc.GeometryFile() - geometry_xml.geometry = geometry - geometry_xml.export_to_xml() + geometry.export_to_xml() # Create an array of different sources x_dist = openmc.stats.Uniform(-3., 3.) @@ -56,11 +52,11 @@ class SourceTestHarness(PyAPITestHarness): energy2 = openmc.stats.Watt(0.988, 2.249) energy3 = openmc.stats.Tabular(E, p, interpolation='histogram') - source1 = Source(spatial1, angle1, energy1, strength=0.5) - source2 = Source(spatial2, angle2, energy2, strength=0.3) - source3 = Source(spatial3, angle3, energy3, strength=0.2) + source1 = openmc.Source(spatial1, angle1, energy1, strength=0.5) + source2 = openmc.Source(spatial2, angle2, energy2, strength=0.3) + source3 = openmc.Source(spatial3, angle3, energy3, strength=0.2) - settings = openmc.SettingsFile() + settings = openmc.Settings() settings.batches = 10 settings.inactive = 5 settings.particles = 1000 diff --git a/tests/test_tallies/test_tallies.py b/tests/test_tallies/test_tallies.py index 81e8641de..bb0273589 100644 --- a/tests/test_tallies/test_tallies.py +++ b/tests/test_tallies/test_tallies.py @@ -4,7 +4,7 @@ import os import sys sys.path.insert(0, os.pardir) from testing_harness import PyAPITestHarness -from openmc import Filter, Mesh, Tally, TalliesFile +from openmc import Filter, Mesh, Tally, Tallies from openmc.source import Source from openmc.stats import Box @@ -170,7 +170,7 @@ class TalliesTestHarness(PyAPITestHarness): all_nuclide_tallies[0].estimator = 'tracklength' all_nuclide_tallies[0].estimator = 'collision' - self._input_set.tallies = TalliesFile() + self._input_set.tallies = Tallies() self._input_set.tallies.add_tally(azimuthal_tally1) self._input_set.tallies.add_tally(azimuthal_tally2) self._input_set.tallies.add_tally(azimuthal_tally3) diff --git a/tests/test_tally_aggregation/test_tally_aggregation.py b/tests/test_tally_aggregation/test_tally_aggregation.py index 7d682b698..009a7dc09 100644 --- a/tests/test_tally_aggregation/test_tally_aggregation.py +++ b/tests/test_tally_aggregation/test_tally_aggregation.py @@ -16,7 +16,7 @@ class TallyAggregationTestHarness(PyAPITestHarness): self._input_set.settings.output = {'summary': True} # Initialize the tallies file - tallies_file = openmc.TalliesFile() + tallies_file = openmc.Tallies() # Initialize the nuclides u235 = openmc.Nuclide('U-235') diff --git a/tests/test_tally_arithmetic/test_tally_arithmetic.py b/tests/test_tally_arithmetic/test_tally_arithmetic.py index cf8d012e8..ffea74603 100644 --- a/tests/test_tally_arithmetic/test_tally_arithmetic.py +++ b/tests/test_tally_arithmetic/test_tally_arithmetic.py @@ -16,7 +16,7 @@ class TallyArithmeticTestHarness(PyAPITestHarness): self._input_set.settings.output = {'summary': True} # Initialize the tallies file - tallies_file = openmc.TalliesFile() + tallies_file = openmc.Tallies() # Initialize the nuclides u235 = openmc.Nuclide('U-235') diff --git a/tests/test_tally_slice_merge/test_tally_slice_merge.py b/tests/test_tally_slice_merge/test_tally_slice_merge.py index 79acf182d..933fdf6fa 100644 --- a/tests/test_tally_slice_merge/test_tally_slice_merge.py +++ b/tests/test_tally_slice_merge/test_tally_slice_merge.py @@ -17,7 +17,7 @@ class TallySliceMergeTestHarness(PyAPITestHarness): self._input_set.settings.output = {'summary': True} # Initialize the tallies file - tallies_file = openmc.TalliesFile() + tallies_file = openmc.Tallies() # Define nuclides and scores to add to both tallies self.nuclides = ['U-235', 'U-238'] @@ -69,8 +69,8 @@ class TallySliceMergeTestHarness(PyAPITestHarness): for nuclide in self.nuclides: distribcell_tally.add_nuclide(nuclide) - # Add tallies to a TalliesFile - tallies_file = openmc.TalliesFile() + # Add tallies to a Tallies object + tallies_file = openmc.Tallies() tallies_file.add_tally(tallies[0]) tallies_file.add_tally(distribcell_tally) @@ -95,7 +95,7 @@ class TallySliceMergeTestHarness(PyAPITestHarness): # Slice the tallies by cell filter bins cell_filter_prod = itertools.product(tallies, self.cell_filters) - tallies = map(lambda tf: tf[0].get_slice(filters=[tf[1].type], + tallies = map(lambda tf: tf[0].get_slice(filters=[tf[1].type], filter_bins=[tf[1].get_bin(0)]), cell_filter_prod) # Slice the tallies by energy filter bins @@ -133,11 +133,11 @@ class TallySliceMergeTestHarness(PyAPITestHarness): # Extract the distribcell tally distribcell_tally = sp.get_tally(name='distribcell tally') - # Sum up a few subdomains from the distribcell tally - sum1 = distribcell_tally.summation(filter_type='distribcell', + # Sum up a few subdomains from the distribcell tally + sum1 = distribcell_tally.summation(filter_type='distribcell', filter_bins=[0,100,2000,30000]) # Sum up a few subdomains from the distribcell tally - sum2 = distribcell_tally.summation(filter_type='distribcell', + sum2 = distribcell_tally.summation(filter_type='distribcell', filter_bins=[500,5000,50000]) # Merge the distribcell tally slices From 68f7de13155231cf88213b19d9dd7e0aba8571ae Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 10:44:20 -0500 Subject: [PATCH 041/147] Update Jupyter notebooks --- .../pythonapi/examples/mgxs-part-i.ipynb | 27 ++++++-------- .../pythonapi/examples/mgxs-part-ii.ipynb | 29 ++++++--------- .../pythonapi/examples/mgxs-part-iii.ipynb | 37 ++++++++----------- .../examples/pandas-dataframes.ipynb | 37 ++++++++----------- .../pythonapi/examples/post-processing.ipynb | 27 ++++++-------- .../pythonapi/examples/tally-arithmetic.ipynb | 29 ++++++--------- 6 files changed, 78 insertions(+), 108 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index de66cbb83..c7a5b2ffa 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -201,7 +201,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "With our material, we can now create a `MaterialsFile` object that can be exported to an actual XML file." + "With our material, we can now create a `Materials` object that can be exported to an actual XML file." ] }, { @@ -212,8 +212,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, register all Materials, and export to XML\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, register all Materials, and export to XML\n", + "materials_file = openmc.Materials()\n", "materials_file.default_xs = '71c'\n", "materials_file.add_material(inf_medium)\n", "materials_file.export_to_xml()" @@ -290,7 +290,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We now must create a geometry that is assigned a root universe, put the geometry into a `GeometryFile` object, and export it to XML." + "We now must create a geometry that is assigned a root universe and export it to XML." ] }, { @@ -305,12 +305,8 @@ "openmc_geometry = openmc.Geometry()\n", "openmc_geometry.root_universe = root_universe\n", "\n", - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = openmc_geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "openmc_geometry.export_to_xml()" ] }, { @@ -333,8 +329,8 @@ "inactive = 10\n", "particles = 2500\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -455,7 +451,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "The `Absorption` object includes tracklength tallies for the 'absorption' and 'flux' scores in the 2-group structure in cell 1. Now that each `MGXS` object contains the tallies that it needs, we must add these tallies to a `TalliesFile` object to generate the \"tallies.xml\" input file for OpenMC." + "The `Absorption` object includes tracklength tallies for the 'absorption' and 'flux' scores in the 2-group structure in cell 1. Now that each `MGXS` object contains the tallies that it needs, we must add these tallies to a `Tallies` object to generate the \"tallies.xml\" input file for OpenMC." ] }, { @@ -466,8 +462,8 @@ }, "outputs": [], "source": [ - "# Instantiate an empty TalliesFile\n", - "tallies_file = openmc.TalliesFile()\n", + "# Instantiate an empty Tallies object\n", + "tallies_file = openmc.Tallies()\n", "\n", "# Add total tallies to the tallies file\n", "for tally in total.tallies.values():\n", @@ -644,8 +640,7 @@ ], "source": [ "# Run OpenMC\n", - "executor = openmc.Executor()\n", - "executor.run_simulation()" + "openmc.run()" ] }, { diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index 6ed5cd38d..49e301f5b 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -122,7 +122,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "With our materials, we can now create a `MaterialsFile` object that can be exported to an actual XML file." + "With our materials, we can now create a `Materials` object that can be exported to an actual XML file." ] }, { @@ -133,8 +133,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, add Materials\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, add Materials\n", + "materials_file = openmc.Materials()\n", "materials_file.add_material(fuel)\n", "materials_file.add_material(water)\n", "materials_file.add_material(zircaloy)\n", @@ -238,7 +238,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We now must create a geometry that is assigned a root universe, put the geometry into a `GeometryFile` object, and export it to XML." + "We now must create a geometry that is assigned a root universe and export it to XML." ] }, { @@ -253,12 +253,8 @@ "openmc_geometry = openmc.Geometry()\n", "openmc_geometry.root_universe = root_universe\n", "\n", - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = openmc_geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "openmc_geometry.export_to_xml()" ] }, { @@ -281,8 +277,8 @@ "inactive = 10\n", "particles = 10000\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -396,8 +392,8 @@ }, "outputs": [], "source": [ - "# Instantiate an empty TalliesFile\n", - "tallies_file = openmc.TalliesFile()\n", + "# Instantiate an empty Tallies object\n", + "tallies_file = openmc.Tallies()\n", "\n", "# Iterate over all cells and cross section types\n", "for cell in openmc_cells:\n", @@ -607,8 +603,7 @@ ], "source": [ "# Run OpenMC\n", - "executor = openmc.Executor()\n", - "executor.run_simulation(output=True)" + "openmc.run(output=True)" ] }, { @@ -1360,7 +1355,7 @@ ], "source": [ "# Generate tracks for OpenMOC\n", - "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=128, spacing=0.1)\n", + "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=128, azim_spacing=0.1)\n", "track_generator.generateTracks()\n", "\n", "# Run OpenMOC\n", @@ -1699,7 +1694,7 @@ ], "source": [ "# Generate tracks for OpenMOC\n", - "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=128, spacing=0.1)\n", + "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=128, azim_spacing=0.1)\n", "track_generator.generateTracks()\n", "\n", "# Run OpenMOC\n", diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 5fccc4f03..3a3533ffe 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -122,7 +122,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "With our three materials, we can now create a `MaterialsFile` object that can be exported to an actual XML file." + "With our three materials, we can now create a `Materials` object that can be exported to an actual XML file." ] }, { @@ -133,8 +133,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, add Materials\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, add Materials\n", + "materials_file = openmc.Materials()\n", "materials_file.add_material(fuel)\n", "materials_file.add_material(water)\n", "materials_file.add_material(zircaloy)\n", @@ -331,7 +331,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We now must create a geometry that is assigned a root universe, put the geometry into a `GeometryFile` object, and export it to XML." + "We now must create a geometry that is assigned a root universe and export it to XML." ] }, { @@ -355,12 +355,8 @@ }, "outputs": [], "source": [ - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "geometry.export_to_xml()" ] }, { @@ -383,8 +379,8 @@ "inactive = 10\n", "particles = 2500\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -403,7 +399,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Let us also create a `PlotsFile` that we can use to verify that our fuel assembly geometry was created successfully." + "Let us also create a `Plots` file that we can use to verify that our fuel assembly geometry was created successfully." ] }, { @@ -422,8 +418,8 @@ "plot.width = [-10.71*2, -10.71*2]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a PlotsFile, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.PlotsFile()\n", + "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", + "plot_file = openmc.Plots()\n", "plot_file.add_plot(plot)\n", "plot_file.export_to_xml()" ] @@ -455,8 +451,7 @@ ], "source": [ "# Run openmc in plotting mode\n", - "executor = openmc.Executor()\n", - "executor.plot_geometry(output=False)" + "openmc.plot_geometry(output=False)" ] }, { @@ -643,7 +638,7 @@ "source": [ "The tallies can now be export to a \"tallies.xml\" input file for OpenMC. \n", "\n", - "**NOTE**: At this point the `Library` has constructed nearly 100 distinct `Tally` objects. The overhead to tally in OpenMC scales as $O(N)$ for $N$ tallies, which can become a bottleneck for large tally datasets. To compensate for this, the Python API's `Tally`, `Filter` and `TalliesFile` classes allow for the smart *merging* of tallies when possible. The `Library` class supports this runtime optimization with the use of the optional `merge` paramter (`False` by default) for the `Library.add_to_tallies_file(...)` method, as shown below." + "**NOTE**: At this point the `Library` has constructed nearly 100 distinct `Tally` objects. The overhead to tally in OpenMC scales as $O(N)$ for $N$ tallies, which can become a bottleneck for large tally datasets. To compensate for this, the Python API's `Tally`, `Filter` and `Tallies` classes allow for the smart *merging* of tallies when possible. The `Library` class supports this runtime optimization with the use of the optional `merge` paramter (`False` by default) for the `Library.add_to_tallies_file(...)` method, as shown below." ] }, { @@ -655,7 +650,7 @@ "outputs": [], "source": [ "# Create a \"tallies.xml\" file for the MGXS Library\n", - "tallies_file = openmc.TalliesFile()\n", + "tallies_file = openmc.Tallies()\n", "mgxs_lib.add_to_tallies_file(tallies_file, merge=True)" ] }, @@ -690,7 +685,7 @@ "tally.filters = [mesh_filter]\n", "tally.scores = ['fission', 'nu-fission']\n", "\n", - "# Add mesh and Tally to TalliesFile\n", + "# Add mesh and tally to Tallies\n", "tallies_file.add_mesh(mesh)\n", "tallies_file.add_tally(tally)" ] @@ -860,7 +855,7 @@ ], "source": [ "# Run OpenMC\n", - "executor.run_simulation()" + "openmc.run()" ] }, { @@ -1449,7 +1444,7 @@ ], "source": [ "# Generate tracks for OpenMOC\n", - "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=32, spacing=0.1)\n", + "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=32, azim_spacing=0.1)\n", "track_generator.generateTracks()\n", "\n", "# Run OpenMOC\n", diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index 388e4aaa6..b0f2f6b13 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -108,8 +108,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, add Materials\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, add Materials\n", + "materials_file = openmc.Materials()\n", "materials_file.add_material(fuel)\n", "materials_file.add_material(water)\n", "materials_file.add_material(zircaloy)\n", @@ -239,7 +239,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We now must create a geometry that is assigned a root universe, put the geometry into a `GeometryFile` object, and export it to XML." + "We now must create a geometry that is assigned a root universe and export it to XML." ] }, { @@ -263,12 +263,8 @@ }, "outputs": [], "source": [ - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "geometry.export_to_xml()" ] }, { @@ -292,8 +288,8 @@ "inactive = 5\n", "particles = 2500\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = min_batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -333,8 +329,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a PlotsFile, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.PlotsFile()\n", + "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", + "plot_file = openmc.Plots()\n", "plot_file.add_plot(plot)\n", "plot_file.export_to_xml()" ] @@ -366,8 +362,7 @@ ], "source": [ "# Run openmc in plotting mode\n", - "executor = openmc.Executor()\n", - "executor.plot_geometry(output=False)" + "openmc.plot_geometry(output=False)" ] }, { @@ -412,8 +407,8 @@ }, "outputs": [], "source": [ - "# Instantiate an empty TalliesFile\n", - "tallies_file = openmc.TalliesFile()\n", + "# Instantiate an empty Tallies object\n", + "tallies_file = openmc.Tallies()\n", "tallies_file._tallies = []" ] }, @@ -453,7 +448,7 @@ "tally.filters = [mesh_filter, energy_filter]\n", "tally.scores = ['fission', 'nu-fission']\n", "\n", - "# Add mesh and Tally to TalliesFile\n", + "# Add mesh and Tally to Tallies\n", "tallies_file.add_mesh(mesh)\n", "tallies_file.add_tally(tally)" ] @@ -482,7 +477,7 @@ "tally.scores = ['scatter-y2']\n", "tally.nuclides = [u235, u238]\n", "\n", - "# Add mesh and tally to TalliesFile\n", + "# Add mesh and tally to Tallies\n", "tallies_file.add_tally(tally)" ] }, @@ -514,7 +509,7 @@ "tally.scores = ['absorption', 'scatter']\n", "tally.triggers = [trigger]\n", "\n", - "# Add mesh and tally to TalliesFile\n", + "# Add mesh and tally to Tallies\n", "tallies_file.add_tally(tally)" ] }, @@ -669,8 +664,8 @@ "# Remove old HDF5 (summary, statepoint) files\n", "!rm statepoint.*\n", "\n", - "# Run OpenMC with MPI!\n", - "executor.run_simulation()" + "# Run OpenMC!\n", + "openmc.run()" ] }, { diff --git a/docs/source/pythonapi/examples/post-processing.ipynb b/docs/source/pythonapi/examples/post-processing.ipynb index 0dc18d5a2..ce9209b03 100644 --- a/docs/source/pythonapi/examples/post-processing.ipynb +++ b/docs/source/pythonapi/examples/post-processing.ipynb @@ -104,8 +104,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, add Materials\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, add Materials\n", + "materials_file = openmc.Materials()\n", "materials_file.add_material(fuel)\n", "materials_file.add_material(water)\n", "materials_file.add_material(zircaloy)\n", @@ -236,12 +236,8 @@ }, "outputs": [], "source": [ - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "geometry.export_to_xml()" ] }, { @@ -264,8 +260,8 @@ "inactive = 10\n", "particles = 5000\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -302,8 +298,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a PlotsFile, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.PlotsFile()\n", + "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", + "plot_file = openmc.Plots()\n", "plot_file.add_plot(plot)\n", "plot_file.export_to_xml()" ] @@ -335,8 +331,7 @@ ], "source": [ "# Run openmc in plotting mode\n", - "executor = openmc.Executor()\n", - "executor.plot_geometry(output=False)" + "openmc.plot_geometry(output=False)" ] }, { @@ -381,8 +376,8 @@ }, "outputs": [], "source": [ - "# Instantiate an empty TalliesFile\n", - "tallies_file = openmc.TalliesFile()" + "# Instantiate an empty Tallies object\n", + "tallies_file = openmc.Tallies()" ] }, { @@ -634,7 +629,7 @@ ], "source": [ "# Run OpenMC!\n", - "executor.run_simulation()" + "openmc.run()" ] }, { diff --git a/docs/source/pythonapi/examples/tally-arithmetic.ipynb b/docs/source/pythonapi/examples/tally-arithmetic.ipynb index 094842895..81334efc2 100644 --- a/docs/source/pythonapi/examples/tally-arithmetic.ipynb +++ b/docs/source/pythonapi/examples/tally-arithmetic.ipynb @@ -126,8 +126,8 @@ }, "outputs": [], "source": [ - "# Instantiate a MaterialsFile, add Materials\n", - "materials_file = openmc.MaterialsFile()\n", + "# Instantiate a Materials object, add Materials\n", + "materials_file = openmc.Materials()\n", "materials_file.add_material(fuel)\n", "materials_file.add_material(water)\n", "materials_file.add_material(zircaloy)\n", @@ -258,12 +258,8 @@ }, "outputs": [], "source": [ - "# Instantiate a GeometryFile\n", - "geometry_file = openmc.GeometryFile()\n", - "geometry_file.geometry = geometry\n", - "\n", "# Export to \"geometry.xml\"\n", - "geometry_file.export_to_xml()" + "geometry.export_to_xml()" ] }, { @@ -286,8 +282,8 @@ "inactive = 5\n", "particles = 2500\n", "\n", - "# Instantiate a SettingsFile\n", - "settings_file = openmc.SettingsFile()\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", "settings_file.batches = batches\n", "settings_file.inactive = inactive\n", "settings_file.particles = particles\n", @@ -325,8 +321,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a PlotsFile, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.PlotsFile()\n", + "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", + "plot_file = openmc.Plots()\n", "plot_file.add_plot(plot)\n", "plot_file.export_to_xml()" ] @@ -358,8 +354,7 @@ ], "source": [ "# Run openmc in plotting mode\n", - "executor = openmc.Executor()\n", - "executor.plot_geometry(output=False)" + "openmc.plot_geometry(output=False)" ] }, { @@ -404,8 +399,8 @@ }, "outputs": [], "source": [ - "# Instantiate an empty TalliesFile\n", - "tallies_file = openmc.TalliesFile()" + "# Instantiate an empty Tallies object\n", + "tallies_file = openmc.Tallies()" ] }, { @@ -673,8 +668,8 @@ "# Remove old HDF5 (summary, statepoint) files\n", "!rm statepoint.*\n", "\n", - "# Run OpenMC with MPI!\n", - "executor.run_simulation()" + "# Run OpenMC!\n", + "openmc.run()" ] }, { From 3da96a89be182d72cec65f6ce448fdc7780ee76d Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 12:43:38 -0500 Subject: [PATCH 042/147] Fix assignment of universe IDs for lattices --- openmc/lattice.py | 21 ++++++++++----------- 1 file changed, 10 insertions(+), 11 deletions(-) diff --git a/openmc/lattice.py b/openmc/lattice.py index 7e78abf06..baccbad90 100644 --- a/openmc/lattice.py +++ b/openmc/lattice.py @@ -7,7 +7,7 @@ import sys import numpy as np import openmc.checkvalue as cv -from openmc.universe import Universe, AUTO_UNIVERSE_ID +import openmc if sys.version_info[0] >= 3: basestring = str @@ -93,9 +93,8 @@ class Lattice(object): @id.setter def id(self, lattice_id): if lattice_id is None: - global AUTO_UNIVERSE_ID - self._id = AUTO_UNIVERSE_ID - AUTO_UNIVERSE_ID += 1 + self._id = openmc.universe.AUTO_UNIVERSE_ID + openmc.universe.AUTO_UNIVERSE_ID += 1 else: cv.check_type('lattice ID', lattice_id, Integral) cv.check_greater_than('lattice ID', lattice_id, 0, equality=True) @@ -111,12 +110,12 @@ class Lattice(object): @outer.setter def outer(self, outer): - cv.check_type('outer universe', outer, Universe) + cv.check_type('outer universe', outer, openmc.Universe) self._outer = outer @universes.setter def universes(self, universes): - cv.check_iterable_type('lattice universes', universes, Universe, + cv.check_iterable_type('lattice universes', universes, openmc.Universe, min_depth=2, max_depth=3) self._universes = np.asarray(universes) @@ -127,20 +126,20 @@ class Lattice(object): ------- universes : collections.OrderedDict Dictionary whose keys are universe IDs and values are - :class:`Universe` instances + :class:`openmc.Universe` instances """ univs = OrderedDict() for k in range(len(self._universes)): for j in range(len(self._universes[k])): - if isinstance(self._universes[k][j], Universe): + if isinstance(self._universes[k][j], openmc.Universe): u = self._universes[k][j] univs[u._id] = u else: for i in range(len(self._universes[k][j])): u = self._universes[k][j][i] - assert isinstance(u, Universe) + assert isinstance(u, openmc.Universe) univs[u._id] = u if self.outer is not None: @@ -615,10 +614,10 @@ class HexLattice(Lattice): # clockwise fashion. # Check to see if the given universes look like a 2D or a 3D array. - if isinstance(self._universes[0][0], Universe): + if isinstance(self._universes[0][0], openmc.Universe): n_dims = 2 - elif isinstance(self._universes[0][0][0], Universe): + elif isinstance(self._universes[0][0][0], openmc.Universe): n_dims = 3 else: From 34bd4052452d034e3bcd096054ae9aafc0eae8df Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 25 Apr 2016 12:58:33 -0500 Subject: [PATCH 043/147] Fix Python 3.5-related issue in mgxs module --- openmc/mgxs/mgxs.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 0c3612e9f..33255de30 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -412,7 +412,7 @@ class MGXS(object): # Otherwise, return all nuclides in the spatial domain else: nuclides = self.domain.get_all_nuclides() - return nuclides.keys() + return list(nuclides.keys()) def get_nuclide_density(self, nuclide): """Get the atomic number density in units of atoms/b-cm for a nuclide From dc01204b70527f73f96aff547117146f1b46f628 Mon Sep 17 00:00:00 2001 From: Colin Josey Date: Mon, 25 Apr 2016 17:37:53 -0400 Subject: [PATCH 044/147] Add documentation for WMP library This commit adds documentation for the HDF5 component of the WMP library. --- docs/source/usersguide/data_wmp.rst | 80 +++++++++++++++++++++++++++++ 1 file changed, 80 insertions(+) create mode 100644 docs/source/usersguide/data_wmp.rst diff --git a/docs/source/usersguide/data_wmp.rst b/docs/source/usersguide/data_wmp.rst new file mode 100644 index 000000000..524e97251 --- /dev/null +++ b/docs/source/usersguide/data_wmp.rst @@ -0,0 +1,80 @@ +.. _usersguide_data_wmp: + +========================================== +The Windowed Multipole Library Format v0.2 +========================================== + +**/nuclide/** + - **broaden_poly** (*int[]*) + If 1, Doppler broaden curve fit for window with corresponding index. + If 0, do not. + - **curvefit** (*double[][][]*) + Curve fit coefficients. Indexed by (reaction type, coefficient index, + window index). + - **data** (*complex[][]*) + Complex poles and residues. First index is `[pole, residue_1, + residue_2, ...]`. Residues are in the order: total, competitive if + present, absorption, fission. Second index is the set index. Complex + numbers are stored by forming a type with `"r"` and `"i"` identifiers, + similar to how `h5py` does it. + - **start_E** (*double*) + Lowest energy the windowed multipole part of the library is valid for. + - **end_E** (*double*) + Highest energy the windowed multipole part of the library is valid for. + - **energy_points** (*double[]*) + Energy grid for the pointwise library in the reaction group. + - **fissionable** (*int*) + 1 if this nuclide has fission data. 0 if it does not. + - **fit_order** (*int*) + The order of the curve fit. + - **formalism** (*int*) + The formalism of the underlying data. Uses the `ENDF-6`_ format formalism + numbers. + - **l_value** (*int[]*) + The index for a corresponding pole. Equivalent to the :math:`l` quantum + number of the resonance the pole comes from :math:`+1`. + - **length** (*int*) + Total count of poles in `data`. + - **max_w** (*int*) + Maximum number of poles in a window. + - **MT_count** (*int*) + Number of pointwise tables in the library. + - **MT_list** (*int[]*) + A list of available MT identifiers. See `ENDF-6`_ for meaning. + - **n_grid** (*int*) + Total length of the pointwise data. + - **num_l** (*int*) + Number of possible :math:`l` quantum states for this nuclide. + - **pseudo_K0RS** (*double[]*) + :math:`l` dependent value of + + .. math:: + \sqrt{\frac{2 m_n}{\hbar}}\frac{AWR}{AWR + 1} r_{s,l} + + Where :math:`m_n` is mass of neutron, :math:`AWR` is the atomic weight + ratio of the target to the neutron, and :math:`r_{s,l}` is the + scattering radius for a given :math:`l`. + - **spacing** (*double*) + .. math:: + \frac{\sqrt{E_{max}}- \sqrt{E_{min}}}{n_w} + + Where :math:`E_{max}` is the maximum energy the windows go up to. This + is not equivalent to the maximum energy for which the windowed multipole + data is valid for. It is slightly higher to ensure an integer number of + windows. :math:`E_{min}` is the minimum energy and equivalent to + `start_E`, and :math:`n_w` is the number of windows, given by `windows`. + - **sqrtAWR** (*double*) + Square root of the atomic weight ratio. + - **w_start** (*int[]*) + The pole to start from for each window. + - **w_end** (*int[]*) + The pole to end at for each window. + - **windows** (*int*) + Number of windows. + +**/nuclide/reactions/MT** + - **MT_sigma** (*double[]*) -- Cross section value for this reaction. + - **Q_value** (*double*) -- Energy released in this reaction, in eV. + - **threshold** (*int*) -- The first non-zero entry in `MT_sigma`. + +.. _ENDF-6: https://www.oecd-nea.org/dbdata/data/manual-endf/endf102.pdf From 787f7aee5f568144897a244db49c4b94c3c6b20a Mon Sep 17 00:00:00 2001 From: Colin Josey Date: Mon, 25 Apr 2016 18:17:58 -0400 Subject: [PATCH 045/147] Clarify the 'data' component of the documentation --- docs/source/usersguide/data_wmp.rst | 11 ++++++----- 1 file changed, 6 insertions(+), 5 deletions(-) diff --git a/docs/source/usersguide/data_wmp.rst b/docs/source/usersguide/data_wmp.rst index 524e97251..81ba0ca2c 100644 --- a/docs/source/usersguide/data_wmp.rst +++ b/docs/source/usersguide/data_wmp.rst @@ -12,11 +12,12 @@ The Windowed Multipole Library Format v0.2 Curve fit coefficients. Indexed by (reaction type, coefficient index, window index). - **data** (*complex[][]*) - Complex poles and residues. First index is `[pole, residue_1, - residue_2, ...]`. Residues are in the order: total, competitive if - present, absorption, fission. Second index is the set index. Complex - numbers are stored by forming a type with `"r"` and `"i"` identifiers, - similar to how `h5py` does it. + Complex poles and residues. Each pole has a corresponding set of + residues. For example, the `i`th pole and corresponding residues are + stored as `data[:,i] = [pole, residue_1, residue_2, ...]`. The + residues are in the order: total, competitive if present, absorption, + fission. Complex numbers are stored by forming a type with `"r"` and + `"i"` identifiers, similar to how `h5py` does it. - **start_E** (*double*) Lowest energy the windowed multipole part of the library is valid for. - **end_E** (*double*) From 9c931eb26a907a276c2e6e6dbaa72660bfb991e7 Mon Sep 17 00:00:00 2001 From: Colin Josey Date: Mon, 25 Apr 2016 18:28:51 -0400 Subject: [PATCH 046/147] Add table with formalism identifiers --- docs/source/usersguide/data_wmp.rst | 15 +++++++++++++-- 1 file changed, 13 insertions(+), 2 deletions(-) diff --git a/docs/source/usersguide/data_wmp.rst b/docs/source/usersguide/data_wmp.rst index 81ba0ca2c..8e8043439 100644 --- a/docs/source/usersguide/data_wmp.rst +++ b/docs/source/usersguide/data_wmp.rst @@ -29,8 +29,19 @@ The Windowed Multipole Library Format v0.2 - **fit_order** (*int*) The order of the curve fit. - **formalism** (*int*) - The formalism of the underlying data. Uses the `ENDF-6`_ format formalism - numbers. + The formalism of the underlying data. Uses the `ENDF-6`_ format + formalism numbers. + + .. table:: Table of supported formalisms. + + +-------------+------------------+ + | Formalism | Formalism number | + +=============+==================+ + | MLBW | 2 | + +-------------+------------------+ + | Reich-Moore | 3 | + +-------------+------------------+ + - **l_value** (*int[]*) The index for a corresponding pole. Equivalent to the :math:`l` quantum number of the resonance the pole comes from :math:`+1`. From 806a8a0c9a1d7bf9639e60846a3e8ba316ba1793 Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Mon, 25 Apr 2016 19:03:31 -0400 Subject: [PATCH 047/147] Move all I/O file formats to special docs section --- docs/source/index.rst | 1 + docs/source/io_formats/data_wmp.rst | 92 +++++++++++++++++++ .../output => io_formats}/index.rst | 10 +- .../mgxs_library.rst | 2 +- .../particle_restart.rst | 2 +- .../output => io_formats}/source.rst | 2 +- .../output => io_formats}/statepoint.rst | 2 +- .../output => io_formats}/summary.rst | 2 +- .../output => io_formats}/track.rst | 2 +- .../output => io_formats}/voxel.rst | 2 +- docs/source/methods/cross_sections.rst | 3 + docs/source/usersguide/index.rst | 2 - docs/source/usersguide/input.rst | 2 +- docs/source/usersguide/processing.rst | 4 +- 14 files changed, 112 insertions(+), 16 deletions(-) create mode 100644 docs/source/io_formats/data_wmp.rst rename docs/source/{usersguide/output => io_formats}/index.rst (55%) rename docs/source/{usersguide => io_formats}/mgxs_library.rst (99%) rename docs/source/{usersguide/output => io_formats}/particle_restart.rst (97%) rename docs/source/{usersguide/output => io_formats}/source.rst (96%) rename docs/source/{usersguide/output => io_formats}/statepoint.rst (99%) rename docs/source/{usersguide/output => io_formats}/summary.rst (99%) rename docs/source/{usersguide/output => io_formats}/track.rst (96%) rename docs/source/{usersguide/output => io_formats}/voxel.rst (95%) diff --git a/docs/source/index.rst b/docs/source/index.rst index 54ba825e5..605f3c977 100644 --- a/docs/source/index.rst +++ b/docs/source/index.rst @@ -34,6 +34,7 @@ free to send a message to the User's Group `mailing list`_. usersguide/index devguide/index pythonapi/index + io_formats/index publications license developers diff --git a/docs/source/io_formats/data_wmp.rst b/docs/source/io_formats/data_wmp.rst new file mode 100644 index 000000000..1e791d6c5 --- /dev/null +++ b/docs/source/io_formats/data_wmp.rst @@ -0,0 +1,92 @@ +.. _io_data_wmp: + +========================================== +The Windowed Multipole Library Format v0.2 +========================================== + +**/nuclide/** + - **broaden_poly** (*int[]*) + If 1, Doppler broaden curve fit for window with corresponding index. + If 0, do not. + - **curvefit** (*double[][][]*) + Curve fit coefficients. Indexed by (reaction type, coefficient index, + window index). + - **data** (*complex[][]*) + Complex poles and residues. Each pole has a corresponding set of + residues. For example, the `i`th pole and corresponding residues are + stored as `data[:,i] = [pole, residue_1, residue_2, ...]`. The + residues are in the order: total, competitive if present, absorption, + fission. Complex numbers are stored by forming a type with `"r"` and + `"i"` identifiers, similar to how `h5py` does it. + - **start_E** (*double*) + Lowest energy the windowed multipole part of the library is valid for. + - **end_E** (*double*) + Highest energy the windowed multipole part of the library is valid for. + - **energy_points** (*double[]*) + Energy grid for the pointwise library in the reaction group. + - **fissionable** (*int*) + 1 if this nuclide has fission data. 0 if it does not. + - **fit_order** (*int*) + The order of the curve fit. + - **formalism** (*int*) + The formalism of the underlying data. Uses the `ENDF-6`_ format + formalism numbers. + + .. table:: Table of supported formalisms. + + +-------------+------------------+ + | Formalism | Formalism number | + +=============+==================+ + | MLBW | 2 | + +-------------+------------------+ + | Reich-Moore | 3 | + +-------------+------------------+ + + - **l_value** (*int[]*) + The index for a corresponding pole. Equivalent to the :math:`l` quantum + number of the resonance the pole comes from :math:`+1`. + - **length** (*int*) + Total count of poles in `data`. + - **max_w** (*int*) + Maximum number of poles in a window. + - **MT_count** (*int*) + Number of pointwise tables in the library. + - **MT_list** (*int[]*) + A list of available MT identifiers. See `ENDF-6`_ for meaning. + - **n_grid** (*int*) + Total length of the pointwise data. + - **num_l** (*int*) + Number of possible :math:`l` quantum states for this nuclide. + - **pseudo_K0RS** (*double[]*) + :math:`l` dependent value of + + .. math:: + \sqrt{\frac{2 m_n}{\hbar}}\frac{AWR}{AWR + 1} r_{s,l} + + Where :math:`m_n` is mass of neutron, :math:`AWR` is the atomic weight + ratio of the target to the neutron, and :math:`r_{s,l}` is the + scattering radius for a given :math:`l`. + - **spacing** (*double*) + .. math:: + \frac{\sqrt{E_{max}}- \sqrt{E_{min}}}{n_w} + + Where :math:`E_{max}` is the maximum energy the windows go up to. This + is not equivalent to the maximum energy for which the windowed multipole + data is valid for. It is slightly higher to ensure an integer number of + windows. :math:`E_{min}` is the minimum energy and equivalent to + `start_E`, and :math:`n_w` is the number of windows, given by `windows`. + - **sqrtAWR** (*double*) + Square root of the atomic weight ratio. + - **w_start** (*int[]*) + The pole to start from for each window. + - **w_end** (*int[]*) + The pole to end at for each window. + - **windows** (*int*) + Number of windows. + +**/nuclide/reactions/MT** + - **MT_sigma** (*double[]*) -- Cross section value for this reaction. + - **Q_value** (*double*) -- Energy released in this reaction, in eV. + - **threshold** (*int*) -- The first non-zero entry in `MT_sigma`. + +.. _ENDF-6: https://www.oecd-nea.org/dbdata/data/manual-endf/endf102.pdf diff --git a/docs/source/usersguide/output/index.rst b/docs/source/io_formats/index.rst similarity index 55% rename from docs/source/usersguide/output/index.rst rename to docs/source/io_formats/index.rst index 31bd1da91..33c43df08 100644 --- a/docs/source/usersguide/output/index.rst +++ b/docs/source/io_formats/index.rst @@ -1,13 +1,15 @@ -.. _usersguide_output: +.. _io_file_formats: -=================== -Output File Formats -=================== +=============== +IO File Formats +=============== .. toctree:: :numbered: :maxdepth: 3 + data_wmp + mgxs_library statepoint source summary diff --git a/docs/source/usersguide/mgxs_library.rst b/docs/source/io_formats/mgxs_library.rst similarity index 99% rename from docs/source/usersguide/mgxs_library.rst rename to docs/source/io_formats/mgxs_library.rst index a5d2ec0d0..e6284e328 100644 --- a/docs/source/usersguide/mgxs_library.rst +++ b/docs/source/io_formats/mgxs_library.rst @@ -1,4 +1,4 @@ -.. _usersguide_mgxs_library: +.. _io_mgxs_library: ======================================== Multi-Group Cross Section Library Format diff --git a/docs/source/usersguide/output/particle_restart.rst b/docs/source/io_formats/particle_restart.rst similarity index 97% rename from docs/source/usersguide/output/particle_restart.rst rename to docs/source/io_formats/particle_restart.rst index 70f00a930..c30eda318 100644 --- a/docs/source/usersguide/output/particle_restart.rst +++ b/docs/source/io_formats/particle_restart.rst @@ -1,4 +1,4 @@ -.. _usersguide_particle_restart: +.. _io_particle_restart: ============================ Particle Restart File Format diff --git a/docs/source/usersguide/output/source.rst b/docs/source/io_formats/source.rst similarity index 96% rename from docs/source/usersguide/output/source.rst rename to docs/source/io_formats/source.rst index 53841a5eb..a0a62afca 100644 --- a/docs/source/usersguide/output/source.rst +++ b/docs/source/io_formats/source.rst @@ -1,4 +1,4 @@ -.. _usersguide_source: +.. _io_source: ================== Source File Format diff --git a/docs/source/usersguide/output/statepoint.rst b/docs/source/io_formats/statepoint.rst similarity index 99% rename from docs/source/usersguide/output/statepoint.rst rename to docs/source/io_formats/statepoint.rst index 95a3d842c..e8b8f8b90 100644 --- a/docs/source/usersguide/output/statepoint.rst +++ b/docs/source/io_formats/statepoint.rst @@ -1,4 +1,4 @@ -.. _usersguide_statepoint: +.. _io_statepoint: ======================= State Point File Format diff --git a/docs/source/usersguide/output/summary.rst b/docs/source/io_formats/summary.rst similarity index 99% rename from docs/source/usersguide/output/summary.rst rename to docs/source/io_formats/summary.rst index cb9f725e8..8af4f2398 100644 --- a/docs/source/usersguide/output/summary.rst +++ b/docs/source/io_formats/summary.rst @@ -1,4 +1,4 @@ -.. _usersguide_summary: +.. _io_summary: =================== Summary File Format diff --git a/docs/source/usersguide/output/track.rst b/docs/source/io_formats/track.rst similarity index 96% rename from docs/source/usersguide/output/track.rst rename to docs/source/io_formats/track.rst index d3c7a27d8..e5cb5d46e 100644 --- a/docs/source/usersguide/output/track.rst +++ b/docs/source/io_formats/track.rst @@ -1,4 +1,4 @@ -.. _usersguide_track: +.. _io_track: ================= Track File Format diff --git a/docs/source/usersguide/output/voxel.rst b/docs/source/io_formats/voxel.rst similarity index 95% rename from docs/source/usersguide/output/voxel.rst rename to docs/source/io_formats/voxel.rst index 1da501fb5..6b73f2800 100644 --- a/docs/source/usersguide/output/voxel.rst +++ b/docs/source/io_formats/voxel.rst @@ -1,4 +1,4 @@ -.. _usersguide_voxel: +.. _io_voxel: ====================== Voxel Plot File Format diff --git a/docs/source/methods/cross_sections.rst b/docs/source/methods/cross_sections.rst index 50a97d575..ec8f8fe45 100644 --- a/docs/source/methods/cross_sections.rst +++ b/docs/source/methods/cross_sections.rst @@ -136,6 +136,9 @@ Note that the implementation of WMP in OpenMC currently assumes that inelastic scattering does not occur in the resolved resonance region. This is usually, but not always the case. Future library versions may eliminate this issue. +The data format used by OpenMC to represent windowed multipole data is specified +in :ref:`io_data_wmp` + .. only:: html .. rubric:: References diff --git a/docs/source/usersguide/index.rst b/docs/source/usersguide/index.rst index 0338c5cef..f8b4e64fa 100644 --- a/docs/source/usersguide/index.rst +++ b/docs/source/usersguide/index.rst @@ -14,7 +14,5 @@ essential aspects of using OpenMC to perform simulations. beginners install input - mgxs_library - output/index processing troubleshoot diff --git a/docs/source/usersguide/input.rst b/docs/source/usersguide/input.rst index 324fbfc2d..24a8ac3e7 100644 --- a/docs/source/usersguide/input.rst +++ b/docs/source/usersguide/input.rst @@ -1941,7 +1941,7 @@ sub-elements: datafiles can be processed into 3D SILO files using the ``openmc-voxel-to-silovtk`` utility provided with the OpenMC source, and subsequently viewed with a 3D viewer such as VISIT or Paraview. See the - :ref:`usersguide_voxel` for information about the datafile structure. + :ref:`io_voxel` for information about the datafile structure. .. note:: Since the PPM format is saved without any kind of compression, the resulting file sizes can be quite large. Saving the image in diff --git a/docs/source/usersguide/processing.rst b/docs/source/usersguide/processing.rst index 059659dbc..93a17a7b8 100644 --- a/docs/source/usersguide/processing.rst +++ b/docs/source/usersguide/processing.rst @@ -161,7 +161,7 @@ or * `VTK `_ with python bindings. On debian derivatives, these are easily obtained with ``sudo apt-get install python-vtk`` -For the HDF5 file structure, see :ref:`usersguide_voxel`. +For the HDF5 file structure, see :ref:`io_voxel`. Once processed into a standard 3D file format, colors and masks can be defined using the stored id numbers to better explore the geometry. The process for @@ -195,7 +195,7 @@ Data Extraction --------------- A great deal of information is available in statepoint files (See -:ref:`usersguide_statepoint`), all of which is accessible through the Python +:ref:`io_statepoint`), all of which is accessible through the Python API. The :class:`openmc.StatePoint` class can load statepoints and access data as requested; it is used in many of the provided plotting utilities, OpenMC's regression test suite, and can be used in user-created scripts to carry out From 6234c4e05ebe416c48ba113b39c1911afb9e6ef4 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 26 Apr 2016 07:06:18 -0500 Subject: [PATCH 048/147] Update copyright in two places and link to license in header --- docs/source/license.rst | 2 +- src/output.F90 | 4 ++-- 2 files changed, 3 insertions(+), 3 deletions(-) diff --git a/docs/source/license.rst b/docs/source/license.rst index 73e329617..c51902d6f 100644 --- a/docs/source/license.rst +++ b/docs/source/license.rst @@ -4,7 +4,7 @@ License Agreement ================= -Copyright © 2011-2015 Massachusetts Institute of Technology +Copyright © 2011-2016 Massachusetts Institute of Technology Permission is hereby granted, free of charge, to any person obtaining a copy of this software and associated documentation files (the "Software"), to deal in diff --git a/src/output.F90 b/src/output.F90 index fafa198f7..4b4b966dc 100644 --- a/src/output.F90 +++ b/src/output.F90 @@ -52,9 +52,9 @@ contains ! Write version information write(UNIT=OUTPUT_UNIT, FMT=*) & - ' Copyright: 2011-2015 Massachusetts Institute of Technology' + ' Copyright: 2011-2016 Massachusetts Institute of Technology' write(UNIT=OUTPUT_UNIT, FMT=*) & - ' License: http://mit-crpg.github.io/openmc/license.html' + ' License: http://openmc.readthedocs.org/en/latest/license.html' write(UNIT=OUTPUT_UNIT, FMT='(6X,"Version:",8X,I1,".",I1,".",I1)') & VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE #ifdef GIT_SHA1 From 1e57cb84074c4d35500fcb9f027b203a20a546de Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 26 Apr 2016 07:08:03 -0500 Subject: [PATCH 049/147] Respond to @wbinventor comments on #632 --- examples/python/basic/build-xml.py | 4 +- examples/python/boxes/build-xml.py | 8 +- .../python/lattice/hexagonal/build-xml.py | 10 +- examples/python/lattice/nested/build-xml.py | 6 +- examples/python/lattice/simple/build-xml.py | 8 +- examples/python/pincell/build-xml.py | 6 +- .../python/pincell_multigroup/build-xml.py | 6 +- examples/python/reflective/build-xml.py | 4 +- openmc/executor.py | 5 +- openmc/material.py | 4 +- openmc/mgxs/library.py | 2 +- openmc/mgxs_library.py | 2 +- openmc/plots.py | 4 +- openmc/surface.py | 211 +++++++++--------- openmc/tallies.py | 4 +- 15 files changed, 146 insertions(+), 138 deletions(-) diff --git a/examples/python/basic/build-xml.py b/examples/python/basic/build-xml.py index 19737cf91..05accbc5e 100644 --- a/examples/python/basic/build-xml.py +++ b/examples/python/basic/build-xml.py @@ -74,7 +74,7 @@ cell1.fill = universe1 universe1.add_cells([cell2, cell3]) root.add_cells([cell1, cell4]) -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -124,7 +124,7 @@ third_tally = openmc.Tally(tally_id=3, name='third tally') third_tally.filters = [cell_filter, energy_filter, energyout_filter] third_tally.scores = ['scatter', 'nu-scatter', 'nu-fission'] -# Instantiate a Tallies object, register all Tallies, and export to XML +# Instantiate a Tallies collection, register all Tallies, and export to XML tallies_file = openmc.Tallies() tallies_file.add_tally(first_tally) tallies_file.add_tally(second_tally) diff --git a/examples/python/boxes/build-xml.py b/examples/python/boxes/build-xml.py index 196a10ca7..318af2265 100644 --- a/examples/python/boxes/build-xml.py +++ b/examples/python/boxes/build-xml.py @@ -36,7 +36,7 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([fuel1, fuel2, moderator]) @@ -97,7 +97,7 @@ outer_box.fill = moderator root = openmc.Universe(universe_id=0, name='root universe') root.add_cells([inner_box, middle_box, outer_box]) -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -107,7 +107,7 @@ geometry.export_to_xml() # Exporting to OpenMC settings.xml File ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML +# Instantiate a Settings object, set all runtime parameters, and export to XML settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive @@ -129,7 +129,7 @@ plot.width = [20, 20] plot.pixels = [200, 200] plot.color = 'cell' -# Instantiate a Plots object, add Plot, and export to XML +# Instantiate a Plots collection, add Plot, and export to XML plot_file = openmc.Plots() plot_file.add_plot(plot) plot_file.export_to_xml() diff --git a/examples/python/lattice/hexagonal/build-xml.py b/examples/python/lattice/hexagonal/build-xml.py index a9d7f6899..04002faf2 100644 --- a/examples/python/lattice/hexagonal/build-xml.py +++ b/examples/python/lattice/hexagonal/build-xml.py @@ -35,7 +35,7 @@ iron = openmc.Material(material_id=3, name='iron') iron.set_density('g/cc', 7.9) iron.add_nuclide(fe56, 1.) -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel, iron]) @@ -105,7 +105,7 @@ lattice.outer = univ2 # Fill Cell with the Lattice cell1.fill = lattice -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -115,7 +115,7 @@ geometry.export_to_xml() # Exporting to OpenMC settings.xml file ############################################################################### -# Instantiate a SettingsFile, set all runtime parameters, and export to XML +# Instantiate a Settings object, set all runtime parameters, and export to XML settings_file = openmc.Settings() settings_file.batches = batches settings_file.inactive = inactive @@ -151,7 +151,7 @@ plot_yz.width = [8, 8] plot_yz.pixels = [400, 400] plot_yz.color = 'mat' -# Instantiate a Plots object, add plots, and export to XML +# Instantiate a Plots collection, add plots, and export to XML plot_file = openmc.Plots() plot_file.add_plot(plot_xy) plot_file.add_plot(plot_yz) @@ -167,7 +167,7 @@ tally = openmc.Tally(tally_id=1) tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])] tally.scores = ['total'] -# Instantiate a Tallies object, register Tally/Mesh, and export to XML +# Instantiate a Tallies collection, register Tally/Mesh, and export to XML tallies_file = openmc.Tallies() tallies_file.add_tally(tally) tallies_file.export_to_xml() diff --git a/examples/python/lattice/nested/build-xml.py b/examples/python/lattice/nested/build-xml.py index eb16c8327..0e4e459e2 100644 --- a/examples/python/lattice/nested/build-xml.py +++ b/examples/python/lattice/nested/build-xml.py @@ -30,7 +30,7 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel]) @@ -116,7 +116,7 @@ lattice2.universes = [[univ4, univ4], cell1.fill = lattice2 cell2.fill = lattice1 -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -176,7 +176,7 @@ tally = openmc.Tally(tally_id=1) tally.filters = [mesh_filter] tally.scores = ['total'] -# Instantiate a Tallies object, register Tally/Mesh, and export to XML +# Instantiate a Tallies collection, register Tally/Mesh, and export to XML tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) diff --git a/examples/python/lattice/simple/build-xml.py b/examples/python/lattice/simple/build-xml.py index 6e44e4da0..8d9481aaa 100644 --- a/examples/python/lattice/simple/build-xml.py +++ b/examples/python/lattice/simple/build-xml.py @@ -30,7 +30,7 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([moderator, fuel]) @@ -106,7 +106,7 @@ lattice.universes = [[univ1, univ2, univ1, univ2], # Fill Cell with the Lattice cell1.fill = lattice -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -142,7 +142,7 @@ plot.width = [4, 4] plot.pixels = [400, 400] plot.color = 'mat' -# Instantiate a Plots object, add Plot, and export to XML +# Instantiate a Plots collection, add Plot, and export to XML plot_file = openmc.Plots() plot_file.add_plot(plot) plot_file.export_to_xml() @@ -173,7 +173,7 @@ tally.filters = [mesh_filter] tally.scores = ['total'] tally.triggers = [trigger] -# Instantiate a Tallies object, register Tally/Mesh, and export to XML +# Instantiate a Tallies collection, register Tally/Mesh, and export to XML tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) diff --git a/examples/python/pincell/build-xml.py b/examples/python/pincell/build-xml.py index 10cd4944d..561df2b5a 100644 --- a/examples/python/pincell/build-xml.py +++ b/examples/python/pincell/build-xml.py @@ -100,7 +100,7 @@ borated_water.add_nuclide(o16, 2.4672e-2) borated_water.add_nuclide(o17, 6.0099e-5) borated_water.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_materials([uo2, helium, zircaloy, borated_water]) @@ -149,7 +149,7 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cells with Universe root.add_cells([fuel, gap, clad, water]) -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -197,7 +197,7 @@ tally = openmc.Tally(tally_id=1, name='tally 1') tally.filters = [energy_filter, mesh_filter] tally.scores = ['flux', 'fission', 'nu-fission'] -# Instantiate a Tallies object, register all Tallies, and export to XML +# Instantiate a Tallies collection, register all Tallies, and export to XML tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) diff --git a/examples/python/pincell_multigroup/build-xml.py b/examples/python/pincell_multigroup/build-xml.py index 233728142..697a596d9 100644 --- a/examples/python/pincell_multigroup/build-xml.py +++ b/examples/python/pincell_multigroup/build-xml.py @@ -81,7 +81,7 @@ water = openmc.Material(material_id=2, name='Water') water.set_density('macro', 1.0) water.add_macroscopic(h2o_data) -# Instantiate a Materials object, register all Materials, and export to XML +# Instantiate a Materials collection, register all Materials, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '300K' materials_file.add_materials([uo2, water]) @@ -122,7 +122,7 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cells with Universe root.add_cells([fuel, moderator]) -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() @@ -173,7 +173,7 @@ tally.add_score('flux') tally.add_score('fission') tally.add_score('nu-fission') -# Instantiate a Tallies object, register all Tallies, and export to XML +# Instantiate a Tallies collection, register all Tallies, and export to XML tallies_file = openmc.Tallies() tallies_file.add_mesh(mesh) tallies_file.add_tally(tally) diff --git a/examples/python/reflective/build-xml.py b/examples/python/reflective/build-xml.py index 7d96e296d..e4776e744 100644 --- a/examples/python/reflective/build-xml.py +++ b/examples/python/reflective/build-xml.py @@ -23,7 +23,7 @@ fuel = openmc.Material(material_id=1, name='fuel') fuel.set_density('g/cc', 4.5) fuel.add_nuclide(u235, 1.) -# Instantiate a Materials object, register Material, and export to XML +# Instantiate a Materials collection, register Material, and export to XML materials_file = openmc.Materials() materials_file.default_xs = '71c' materials_file.add_material(fuel) @@ -64,7 +64,7 @@ root = openmc.Universe(universe_id=0, name='root universe') # Register Cell with Universe root.add_cell(cell) -# Instantiate a Geometry and register the root Universe, and export to XML +# Instantiate a Geometry, register the root Universe, and export to XML geometry = openmc.Geometry() geometry.root_universe = root geometry.export_to_xml() diff --git a/openmc/executor.py b/openmc/executor.py index 9bb3477c5..edbbaddc4 100644 --- a/openmc/executor.py +++ b/openmc/executor.py @@ -54,7 +54,10 @@ def run(particles=None, threads=None, geometry_debug=False, particles : int, optional Number of particles to simulate per generation. threads : int, optional - Number of OpenMP threads. + Number of OpenMP threads. If OpenMC is compiled with OpenMP threading + enabled, the default is implementation-dependent but is usually equal to + the number of hardware threads available (or a value set by the + OMP_NUM_THREADS environment variable). geometry_debug : bool, optional Turn on geometry debugging during simulation. Defaults to False. restart_file : str, optional diff --git a/openmc/material.py b/openmc/material.py index 6b0a0f246..c6030a8e6 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -643,8 +643,8 @@ class Material(object): class Materials(object): - """Materials used for an OpenMC simulation. Corresponds directly to the - materials.xml input file. + """Collection of Materials used for an OpenMC simulation. Corresponds directly + to the materials.xml input file. Attributes ---------- diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index ca7bf39cd..8d5e9854e 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -355,7 +355,7 @@ class Library(object): Parameters ---------- tallies_file : openmc.Tallies - A Tallies object to add each MGXS' tallies to generate a + A Tallies collection to add each MGXS' tallies to generate a "tallies.xml" input file for OpenMC merge : bool Indicate whether tallies should be merged when possible. Defaults diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 8db3c84ff..d3e49b238 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -705,7 +705,7 @@ class MGXSLibrary(object): # Make sure energy groups match. if xsdata.energy_groups != self._energy_groups: - msg = 'Energy groups of XSdata do not match that of MGXSLibrary!' + msg = 'Energy groups of XSdata do not match that of MGXSLibrary.' raise ValueError(msg) self._xsdatas.append(xsdata) diff --git a/openmc/plots.py b/openmc/plots.py index ae34678bb..a967cb060 100644 --- a/openmc/plots.py +++ b/openmc/plots.py @@ -402,8 +402,8 @@ class Plot(object): class Plots(object): - """Plots file used for an OpenMC simulation. Corresponds directly to the - plots.xml input file. + """Collection of Plots used for an OpenMC simulation. Corresponds directly to + the plots.xml input file. """ diff --git a/openmc/surface.py b/openmc/surface.py index c6f3f2cd0..37e7c2ffd 100644 --- a/openmc/surface.py +++ b/openmc/surface.py @@ -23,7 +23,11 @@ def reset_auto_surface_id(): class Surface(object): - """A two-dimensional surface with an associated boundary condition. + """An implicit surface with an associated boundary condition. + + An implicit surface is defined as the set of zeros of a function of the + three Cartesian coordinates. Surfaces in OpenMC are limited to a set of + algebraic surfaces, i.e., surfaces that are polynomial in x, y, and z. Parameters ---------- @@ -43,14 +47,14 @@ class Surface(object): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -63,7 +67,7 @@ class Surface(object): # A dictionary of the quadratic surface coefficients # Key - coefficeint name # Value - coefficient value - self._coeffs = {} + self._coefficients = {} # An ordered list of the coefficient names to export to XML in the # proper order @@ -82,12 +86,13 @@ class Surface(object): string += '{0: <16}{1}{2}\n'.format('\tType', '=\t', self._type) string += '{0: <16}{1}{2}\n'.format('\tBoundary', '=\t', self._boundary_type) - coeffs = '{0: <16}'.format('\tCoefficients') + '\n' + coefficients = '{0: <16}'.format('\tCoefficients') + '\n' - for coeff in self._coeffs: - coeffs += '{0: <16}{1}{2}\n'.format(coeff, '=\t', self._coeffs[coeff]) + for coeff in self._coefficients: + coefficients += '{0: <16}{1}{2}\n'.format( + coeff, '=\t', self._coefficients[coeff]) - string += coeffs + string += coefficients return string @@ -108,8 +113,8 @@ class Surface(object): return self._boundary_type @property - def coeffs(self): - return self._coeffs + def coefficients(self): + return self._coefficients @id.setter def id(self, surface_id): @@ -173,7 +178,7 @@ class Surface(object): element.set("type", self._type) if self.boundary_type != 'transmission': element.set("boundary", self.boundary_type) - element.set("coeffs", ' '.join([str(self._coeffs.setdefault(key, 0.0)) + element.set("coeffs", ' '.join([str(self._coefficients.setdefault(key, 0.0)) for key in self._coeff_keys])) return element @@ -215,14 +220,14 @@ class Plane(Surface): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -239,39 +244,39 @@ class Plane(Surface): @property def a(self): - return self.coeffs['A'] + return self.coefficients['A'] @property def b(self): - return self.coeffs['B'] + return self.coefficients['B'] @property def c(self): - return self.coeffs['C'] + return self.coefficients['C'] @property def d(self): - return self.coeffs['D'] + return self.coefficients['D'] @a.setter def a(self, A): check_type('A coefficient', A, Real) - self._coeffs['A'] = A + self._coefficients['A'] = A @b.setter def b(self, B): check_type('B coefficient', B, Real) - self._coeffs['B'] = B + self._coefficients['B'] = B @c.setter def c(self, C): check_type('C coefficient', C, Real) - self._coeffs['C'] = C + self._coefficients['C'] = C @d.setter def d(self, D): check_type('D coefficient', D, Real) - self._coeffs['D'] = D + self._coefficients['D'] = D class XPlane(Plane): @@ -298,14 +303,14 @@ class XPlane(Plane): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -319,12 +324,12 @@ class XPlane(Plane): @property def x0(self): - return self.coeffs['x0'] + return self.coefficients['x0'] @x0.setter def x0(self, x0): check_type('x0 coefficient', x0, Real) - self._coeffs['x0'] = x0 + self._coefficients['x0'] = x0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -382,14 +387,14 @@ class YPlane(Plane): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -404,12 +409,12 @@ class YPlane(Plane): @property def y0(self): - return self.coeffs['y0'] + return self.coefficients['y0'] @y0.setter def y0(self, y0): check_type('y0 coefficient', y0, Real) - self._coeffs['y0'] = y0 + self._coefficients['y0'] = y0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -467,14 +472,14 @@ class ZPlane(Plane): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -489,12 +494,12 @@ class ZPlane(Plane): @property def z0(self): - return self.coeffs['z0'] + return self.coefficients['z0'] @z0.setter def z0(self, z0): check_type('z0 coefficient', z0, Real) - self._coeffs['z0'] = z0 + self._coefficients['z0'] = z0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -553,14 +558,14 @@ class Cylinder(Surface): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -575,12 +580,12 @@ class Cylinder(Surface): @property def r(self): - return self.coeffs['R'] + return self.coefficients['R'] @r.setter def r(self, R): check_type('R coefficient', R, Real) - self._coeffs['R'] = R + self._coefficients['R'] = R class XCylinder(Cylinder): @@ -615,14 +620,14 @@ class XCylinder(Cylinder): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -637,21 +642,21 @@ class XCylinder(Cylinder): @property def y0(self): - return self.coeffs['y0'] + return self.coefficients['y0'] @property def z0(self): - return self.coeffs['z0'] + return self.coefficients['z0'] @y0.setter def y0(self, y0): check_type('y0 coefficient', y0, Real) - self._coeffs['y0'] = y0 + self._coefficients['y0'] = y0 @z0.setter def z0(self, z0): check_type('z0 coefficient', z0, Real) - self._coeffs['z0'] = z0 + self._coefficients['z0'] = z0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -718,14 +723,14 @@ class YCylinder(Cylinder): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -740,21 +745,21 @@ class YCylinder(Cylinder): @property def x0(self): - return self.coeffs['x0'] + return self.coefficients['x0'] @property def z0(self): - return self.coeffs['z0'] + return self.coefficients['z0'] @x0.setter def x0(self, x0): check_type('x0 coefficient', x0, Real) - self._coeffs['x0'] = x0 + self._coefficients['x0'] = x0 @z0.setter def z0(self, z0): check_type('z0 coefficient', z0, Real) - self._coeffs['z0'] = z0 + self._coefficients['z0'] = z0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -821,14 +826,14 @@ class ZCylinder(Cylinder): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -843,21 +848,21 @@ class ZCylinder(Cylinder): @property def x0(self): - return self.coeffs['x0'] + return self.coefficients['x0'] @property def y0(self): - return self.coeffs['y0'] + return self.coefficients['y0'] @x0.setter def x0(self, x0): check_type('x0 coefficient', x0, Real) - self._coeffs['x0'] = x0 + self._coefficients['x0'] = x0 @y0.setter def y0(self, y0): check_type('y0 coefficient', y0, Real) - self._coeffs['y0'] = y0 + self._coefficients['y0'] = y0 def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -928,14 +933,14 @@ class Sphere(Surface): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -952,39 +957,39 @@ class Sphere(Surface): @property def x0(self): - return self.coeffs['x0'] + return self.coefficients['x0'] @property def y0(self): - return self.coeffs['y0'] + return self.coefficients['y0'] @property def z0(self): - return self.coeffs['z0'] + return self.coefficients['z0'] @property def r(self): - return self.coeffs['R'] + return self.coefficients['R'] @x0.setter def x0(self, x0): check_type('x0 coefficient', x0, Real) - self._coeffs['x0'] = x0 + self._coefficients['x0'] = x0 @y0.setter def y0(self, y0): check_type('y0 coefficient', y0, Real) - self._coeffs['y0'] = y0 + self._coefficients['y0'] = y0 @z0.setter def z0(self, z0): check_type('z0 coefficient', z0, Real) - self._coeffs['z0'] = z0 + self._coefficients['z0'] = z0 @r.setter def r(self, R): check_type('R coefficient', R, Real) - self._coeffs['R'] = R + self._coefficients['R'] = R def bounding_box(self, side): """Determine an axis-aligned bounding box. @@ -1056,14 +1061,14 @@ class Cone(Surface): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -1081,39 +1086,39 @@ class Cone(Surface): @property def x0(self): - return self.coeffs['x0'] + return self.coefficients['x0'] @property def y0(self): - return self.coeffs['y0'] + return self.coefficients['y0'] @property def z0(self): - return self.coeffs['z0'] + return self.coefficients['z0'] @property def r2(self): - return self.coeffs['r2'] + return self.coefficients['r2'] @x0.setter def x0(self, x0): check_type('x0 coefficient', x0, Real) - self._coeffs['x0'] = x0 + self._coefficients['x0'] = x0 @y0.setter def y0(self, y0): check_type('y0 coefficient', y0, Real) - self._coeffs['y0'] = y0 + self._coefficients['y0'] = y0 @z0.setter def z0(self, z0): check_type('z0 coefficient', z0, Real) - self._coeffs['z0'] = z0 + self._coefficients['z0'] = z0 @r2.setter def r2(self, R2): check_type('R^2 coefficient', R2, Real) - self._coeffs['R2'] = R2 + self._coefficients['R2'] = R2 class XCone(Cone): @@ -1153,14 +1158,14 @@ class XCone(Cone): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -1209,14 +1214,14 @@ class YCone(Cone): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -1265,14 +1270,14 @@ class ZCone(Cone): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -1309,14 +1314,14 @@ class Quadric(Surface): boundary_type : {'transmission, 'vacuum', 'reflective', 'periodic'} Boundary condition that defines the behavior for particles hitting the surface. - coeffs : dict + coefficients : dict Dictionary of surface coefficients id : int Unique identifier for the surface name : str Name of the surface type : str - Type of the surface, e.g. 'x-plane' + Type of the surface """ @@ -1340,93 +1345,93 @@ class Quadric(Surface): @property def a(self): - return self.coeffs['a'] + return self.coefficients['a'] @property def b(self): - return self.coeffs['b'] + return self.coefficients['b'] @property def c(self): - return self.coeffs['c'] + return self.coefficients['c'] @property def d(self): - return self.coeffs['d'] + return self.coefficients['d'] @property def e(self): - return self.coeffs['e'] + return self.coefficients['e'] @property def f(self): - return self.coeffs['f'] + return self.coefficients['f'] @property def g(self): - return self.coeffs['g'] + return self.coefficients['g'] @property def h(self): - return self.coeffs['h'] + return self.coefficients['h'] @property def j(self): - return self.coeffs['j'] + return self.coefficients['j'] @property def k(self): - return self.coeffs['k'] + return self.coefficients['k'] @a.setter def a(self, a): check_type('a coefficient', a, Real) - self._coeffs['a'] = a + self._coefficients['a'] = a @b.setter def b(self, b): check_type('b coefficient', b, Real) - self._coeffs['b'] = b + self._coefficients['b'] = b @c.setter def c(self, c): check_type('c coefficient', c, Real) - self._coeffs['c'] = c + self._coefficients['c'] = c @d.setter def d(self, d): check_type('d coefficient', d, Real) - self._coeffs['d'] = d + self._coefficients['d'] = d @e.setter def e(self, e): check_type('e coefficient', e, Real) - self._coeffs['e'] = e + self._coefficients['e'] = e @f.setter def f(self, f): check_type('f coefficient', f, Real) - self._coeffs['f'] = f + self._coefficients['f'] = f @g.setter def g(self, g): check_type('g coefficient', g, Real) - self._coeffs['g'] = g + self._coefficients['g'] = g @h.setter def h(self, h): check_type('h coefficient', h, Real) - self._coeffs['h'] = h + self._coefficients['h'] = h @j.setter def j(self, j): check_type('j coefficient', j, Real) - self._coeffs['j'] = j + self._coefficients['j'] = j @k.setter def k(self, k): check_type('k coefficient', k, Real) - self._coeffs['k'] = k + self._coefficients['k'] = k class Halfspace(Region): diff --git a/openmc/tallies.py b/openmc/tallies.py index 1af3b12bc..90b09f582 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -3420,8 +3420,8 @@ class Tally(object): class Tallies(object): - """Tallies file used for an OpenMC simulation. Corresponds directly to the - tallies.xml input file. + """Collection of Tallies used for an OpenMC simulation. Corresponds directly to + the tallies.xml input file. """ From d6268831c75604f29d718d01253786a368e923d0 Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Tue, 26 Apr 2016 23:07:07 -0400 Subject: [PATCH 050/147] Allow plotting without settings.xml --- src/input_xml.F90 | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 295422533..474c59d18 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -38,8 +38,8 @@ contains subroutine read_input_xml() - call read_settings_xml() if (run_mode /= MODE_PLOTTING) then + call read_settings_xml() if (run_CE) then call read_ce_cross_sections_xml() else From e204952c369cc7181fbc74842956e991f84c5953 Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Tue, 26 Apr 2016 23:26:16 -0400 Subject: [PATCH 051/147] Alow string shortcut to Material.add_element --- openmc/material.py | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/openmc/material.py b/openmc/material.py index c6030a8e6..17283d4dd 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -387,7 +387,7 @@ class Material(object): Parameters ---------- - element : openmc.Element + element : openmc.Element or str Element to add percent : float Atom or weight percent @@ -401,7 +401,7 @@ class Material(object): 'macroscopic data-set has already been added'.format(self._id) raise ValueError(msg) - if not isinstance(element, openmc.Element): + if not isinstance(element, (openmc.Element, str)): msg = 'Unable to add an Element to Material ID="{0}" with a ' \ 'non-Element value "{1}"'.format(self._id, element) raise ValueError(msg) From 37e8f455d8116d675fe1f514d9ee95eeb26373ab Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Wed, 27 Apr 2016 10:47:06 -0400 Subject: [PATCH 052/147] Allow plotting with or without settings.xml --- src/input_xml.F90 | 22 +++++++++++++--------- 1 file changed, 13 insertions(+), 9 deletions(-) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 474c59d18..90c703d27 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -38,8 +38,8 @@ contains subroutine read_input_xml() + call read_settings_xml() if (run_mode /= MODE_PLOTTING) then - call read_settings_xml() if (run_CE) then call read_ce_cross_sections_xml() else @@ -92,18 +92,22 @@ contains type(NodeList), pointer :: node_scat_list => null() type(NodeList), pointer :: node_source_list => null() - ! Display output message - call write_message("Reading settings XML file...", 5) - ! Check if settings.xml exists filename = trim(path_input) // "settings.xml" inquire(FILE=filename, EXIST=file_exists) if (.not. file_exists) then - call fatal_error("Settings XML file '" // trim(filename) // "' does not & - &exist! In order to run OpenMC, you first need a set of input files;& - & at a minimum, this includes settings.xml, geometry.xml, and & - &materials.xml. Please consult the user's guide at & - &http://mit-crpg.github.io/openmc for further information.") + if (run_mode /= MODE_PLOTTING) then + call fatal_error("Settings XML file '" // trim(filename) // "' does & + ¬ exist! In order to run OpenMC, you first need a set of input & + &files; at a minimum, this includes settings.xml, geometry.xml, & + &and materials.xml. Please consult the user's guide at & + &http://mit-crpg.github.io/openmc for further information.") + else + ! The settings.xml file is optional if we just want to make a plot. + return + end if + else + call write_message("Reading settings XML file...", 5) end if ! Parse settings.xml file From ad7bff393d38aaa15c84e51bd3c0222974efed38 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 27 Apr 2016 15:36:36 -0500 Subject: [PATCH 053/147] Make sure to capture stderr when using openmc.run() --- openmc/executor.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/executor.py b/openmc/executor.py index edbbaddc4..fbd9e5d82 100644 --- a/openmc/executor.py +++ b/openmc/executor.py @@ -10,7 +10,7 @@ if sys.version_info[0] >= 3: def _run(command, output, cwd): # Launch a subprocess p = subprocess.Popen(command, shell=True, cwd=cwd, stdout=subprocess.PIPE, - universal_newlines=True) + stderr=subprocess.STDOUT, universal_newlines=True) # Capture and re-print OpenMC output in real-time while True: From 76b2b65ab8e7233bfbc49663b9792c41edfc69bc Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Wed, 27 Apr 2016 18:13:32 -0400 Subject: [PATCH 054/147] Use basestring instead of str --- openmc/material.py | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/openmc/material.py b/openmc/material.py index 17283d4dd..97c7cedca 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -281,7 +281,7 @@ class Material(object): 'macroscopic data-set has already been added'.format(self._id) raise ValueError(msg) - if not isinstance(nuclide, (openmc.Nuclide, str)): + if not isinstance(nuclide, (openmc.Nuclide, basestring)): msg = 'Unable to add a Nuclide to Material ID="{0}" with a ' \ 'non-Nuclide value "{1}"'.format(self._id, nuclide) raise ValueError(msg) @@ -401,7 +401,7 @@ class Material(object): 'macroscopic data-set has already been added'.format(self._id) raise ValueError(msg) - if not isinstance(element, (openmc.Element, str)): + if not isinstance(element, (openmc.Element, basestring)): msg = 'Unable to add an Element to Material ID="{0}" with a ' \ 'non-Element value "{1}"'.format(self._id, element) raise ValueError(msg) From d9b097dbaf967405005e6a5706492ff0d4d227e8 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 29 Apr 2016 16:14:02 -0500 Subject: [PATCH 055/147] Make Materials, Plots, and Tallies list-like --- .../pythonapi/examples/mgxs-part-i.ipynb | 16 +- .../pythonapi/examples/mgxs-part-ii.ipynb | 9 +- .../pythonapi/examples/mgxs-part-iii.ipynb | 15 +- .../examples/pandas-dataframes.ipynb | 19 +-- .../pythonapi/examples/post-processing.ipynb | 17 +-- .../pythonapi/examples/tally-arithmetic.ipynb | 29 ++-- examples/python/basic/build-xml.py | 12 +- examples/python/boxes/build-xml.py | 10 +- .../python/lattice/hexagonal/build-xml.py | 14 +- examples/python/lattice/nested/build-xml.py | 14 +- examples/python/lattice/simple/build-xml.py | 16 +- examples/python/pincell/build-xml.py | 11 +- .../python/pincell_multigroup/build-xml.py | 16 +- examples/python/reflective/build-xml.py | 5 +- openmc/checkvalue.py | 26 +++- openmc/material.py | 122 +++++++++++----- openmc/mgxs/library.py | 2 +- openmc/plots.py | 76 ++++++++-- openmc/tallies.py | 137 +++++++++++++----- tests/input_set.py | 8 +- .../test_asymmetric_lattice.py | 7 +- tests/test_distribmat/test_distribmat.py | 3 +- tests/test_mg_max_order/test_mg_max_order.py | 2 +- tests/test_mg_nuclide/test_mg_nuclide.py | 2 +- tests/test_mg_tallies/test_mg_tallies.py | 21 +-- .../test_resonance_scattering.py | 3 +- tests/test_source/test_source.py | 3 +- tests/test_tallies/test_tallies.py | 41 ++---- .../test_tally_aggregation.py | 5 +- .../test_tally_arithmetic.py | 5 +- .../test_tally_slice_merge.py | 4 +- 31 files changed, 373 insertions(+), 297 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index c7a5b2ffa..a450af97e 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -212,10 +212,9 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, register all Materials, and export to XML\n", - "materials_file = openmc.Materials()\n", + "# Instantiate a Materials collection and export to XML\n", + "materials_file = openmc.Materials([inf_medium])\n", "materials_file.default_xs = '71c'\n", - "materials_file.add_material(inf_medium)\n", "materials_file.export_to_xml()" ] }, @@ -466,17 +465,14 @@ "tallies_file = openmc.Tallies()\n", "\n", "# Add total tallies to the tallies file\n", - "for tally in total.tallies.values():\n", - " tallies_file.add_tally(tally)\n", + "tallies_file += total.tallies.values()\n", "\n", "# Add absorption tallies to the tallies file\n", - "for tally in absorption.tallies.values():\n", - " tallies_file.add_tally(tally)\n", + "tallies_file += absorption.tallies.values()\n", "\n", "# Add scattering tallies to the tallies file\n", - "for tally in scattering.tallies.values():\n", - " tallies_file.add_tally(tally)\n", - " \n", + "tallies_file += scattering.tallies.values()\n", + "\n", "# Export to \"tallies.xml\"\n", "tallies_file.export_to_xml()" ] diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index 49e301f5b..793d88436 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -133,11 +133,8 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, add Materials\n", - "materials_file = openmc.Materials()\n", - "materials_file.add_material(fuel)\n", - "materials_file.add_material(water)\n", - "materials_file.add_material(zircaloy)\n", + "# Instantiate a Materials collection\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -408,7 +405,7 @@ " \n", " # Add OpenMC tallies to the tallies file for XML generation\n", " for tally in xs_library[cell.id][rxn_type].tallies.values():\n", - " tallies_file.add_tally(tally, merge=True)\n", + " tallies_file.append(tally, merge=True)\n", "\n", "# Export to \"tallies.xml\"\n", "tallies_file.export_to_xml()" diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 3a3533ffe..34190371b 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -133,11 +133,8 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, add Materials\n", - "materials_file = openmc.Materials()\n", - "materials_file.add_material(fuel)\n", - "materials_file.add_material(water)\n", - "materials_file.add_material(zircaloy)\n", + "# Instantiate a Materials object\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -419,8 +416,7 @@ "plot.color = 'mat'\n", "\n", "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.Plots()\n", - "plot_file.add_plot(plot)\n", + "plot_file = openmc.Plots([plot])\n", "plot_file.export_to_xml()" ] }, @@ -685,9 +681,8 @@ "tally.filters = [mesh_filter]\n", "tally.scores = ['fission', 'nu-fission']\n", "\n", - "# Add mesh and tally to Tallies\n", - "tallies_file.add_mesh(mesh)\n", - "tallies_file.add_tally(tally)" + "# Add tally to collection\n", + "tallies_file.append(tally)" ] }, { diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index b0f2f6b13..d5e8b9861 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -108,11 +108,8 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, add Materials\n", - "materials_file = openmc.Materials()\n", - "materials_file.add_material(fuel)\n", - "materials_file.add_material(water)\n", - "materials_file.add_material(zircaloy)\n", + "# Instantiate a Materials collection\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -329,9 +326,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.Plots()\n", - "plot_file.add_plot(plot)\n", + "# Instantiate a Plots collection and export to \"plots.xml\"\n", + "plot_file = openmc.Plots([plot])\n", "plot_file.export_to_xml()" ] }, @@ -449,8 +445,7 @@ "tally.scores = ['fission', 'nu-fission']\n", "\n", "# Add mesh and Tally to Tallies\n", - "tallies_file.add_mesh(mesh)\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { @@ -478,7 +473,7 @@ "tally.nuclides = [u235, u238]\n", "\n", "# Add mesh and tally to Tallies\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { @@ -510,7 +505,7 @@ "tally.triggers = [trigger]\n", "\n", "# Add mesh and tally to Tallies\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { diff --git a/docs/source/pythonapi/examples/post-processing.ipynb b/docs/source/pythonapi/examples/post-processing.ipynb index ce9209b03..36cf63c6a 100644 --- a/docs/source/pythonapi/examples/post-processing.ipynb +++ b/docs/source/pythonapi/examples/post-processing.ipynb @@ -104,11 +104,8 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, add Materials\n", - "materials_file = openmc.Materials()\n", - "materials_file.add_material(fuel)\n", - "materials_file.add_material(water)\n", - "materials_file.add_material(zircaloy)\n", + "# Instantiate a Materials collection\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -298,9 +295,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.Plots()\n", - "plot_file.add_plot(plot)\n", + "# Instantiate a Plots collection and export to \"plots.xml\"\n", + "plot_file = openmc.Plots([plot])\n", "plot_file.export_to_xml()" ] }, @@ -393,17 +389,16 @@ "mesh.dimension = [100, 100]\n", "mesh.lower_left = [-0.63, -0.63]\n", "mesh.upper_right = [0.63, 0.63]\n", - "tallies_file.add_mesh(mesh)\n", "\n", "# Create mesh filter for tally\n", - "mesh_filter = openmc.Filter(type='mesh', bins=[1])\n", + "mesh_filter = openmc.Filter(type='mesh')\n", "mesh_filter.mesh = mesh\n", "\n", "# Create mesh tally to score flux and fission rate\n", "tally = openmc.Tally(name='flux')\n", "tally.filters = [mesh_filter]\n", "tally.scores = ['flux', 'fission']\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { diff --git a/docs/source/pythonapi/examples/tally-arithmetic.ipynb b/docs/source/pythonapi/examples/tally-arithmetic.ipynb index 81334efc2..14ca97d3f 100644 --- a/docs/source/pythonapi/examples/tally-arithmetic.ipynb +++ b/docs/source/pythonapi/examples/tally-arithmetic.ipynb @@ -126,11 +126,8 @@ }, "outputs": [], "source": [ - "# Instantiate a Materials object, add Materials\n", - "materials_file = openmc.Materials()\n", - "materials_file.add_material(fuel)\n", - "materials_file.add_material(water)\n", - "materials_file.add_material(zircaloy)\n", + "# Instantiate a Materials collection\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -321,9 +318,8 @@ "plot.pixels = [250, 250]\n", "plot.color = 'mat'\n", "\n", - "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", - "plot_file = openmc.Plots()\n", - "plot_file.add_plot(plot)\n", + "# Instantiate a Plots collection and export to \"plots.xml\"\n", + "plot_file = openmc.Plots([plot])\n", "plot_file.export_to_xml()" ] }, @@ -421,7 +417,7 @@ "tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n", "tally.filters.append(energy_filter)\n", "tally.scores = ['flux']\n", - "tallies_file.add_tally(tally)\n", + "tallies_file.append(tally)\n", "\n", "# Instantiate reaction rate Tally in fuel\n", "tally = openmc.Tally(name='fuel rxn rates')\n", @@ -429,7 +425,7 @@ "tally.filters.append(energy_filter)\n", "tally.scores = ['nu-fission', 'scatter']\n", "tally.nuclides = [u238, u235]\n", - "tallies_file.add_tally(tally)\n", + "tallies_file.append(tally)\n", "\n", "# Instantiate reaction rate Tally in moderator\n", "tally = openmc.Tally(name='moderator rxn rates')\n", @@ -437,7 +433,7 @@ "tally.filters.append(energy_filter)\n", "tally.scores = ['absorption', 'total']\n", "tally.nuclides = [o16, h1]\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { @@ -453,8 +449,7 @@ "abs_rate = openmc.Tally(name='abs. rate')\n", "fiss_rate.scores = ['nu-fission']\n", "abs_rate.scores = ['absorption']\n", - "tallies_file.add_tally(fiss_rate)\n", - "tallies_file.add_tally(abs_rate)" + "tallies_file += (fiss_rate, abs_rate)", ] }, { @@ -469,7 +464,7 @@ "therm_abs_rate = openmc.Tally(name='therm. abs. rate')\n", "therm_abs_rate.scores = ['absorption']\n", "therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n", - "tallies_file.add_tally(therm_abs_rate)" + "tallies_file.append(therm_abs_rate)" ] }, { @@ -485,7 +480,7 @@ "fuel_therm_abs_rate.scores = ['absorption']\n", "fuel_therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6]),\n", " openmc.Filter(type='cell', bins=[fuel_cell.id])]\n", - "tallies_file.add_tally(fuel_therm_abs_rate)" + "tallies_file.append(fuel_therm_abs_rate)" ] }, { @@ -500,7 +495,7 @@ "therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')\n", "therm_fiss_rate.scores = ['nu-fission']\n", "therm_fiss_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n", - "tallies_file.add_tally(therm_fiss_rate)" + "tallies_file.append(therm_fiss_rate)" ] }, { @@ -520,7 +515,7 @@ "tally.filters.append(energy_filter)\n", "tally.scores = ['nu-fission', 'scatter']\n", "tally.nuclides = [h1, u238]\n", - "tallies_file.add_tally(tally)" + "tallies_file.append(tally)" ] }, { diff --git a/examples/python/basic/build-xml.py b/examples/python/basic/build-xml.py index 05accbc5e..ffff03720 100644 --- a/examples/python/basic/build-xml.py +++ b/examples/python/basic/build-xml.py @@ -31,10 +31,9 @@ fuel = openmc.Material(material_id=40, name='fuel') fuel.set_density('g/cc', 4.5) fuel.add_nuclide(u235, 1.) -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([moderator, fuel]) materials_file.default_xs = '71c' -materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() @@ -124,9 +123,6 @@ third_tally = openmc.Tally(tally_id=3, name='third tally') third_tally.filters = [cell_filter, energy_filter, energyout_filter] third_tally.scores = ['scatter', 'nu-scatter', 'nu-fission'] -# Instantiate a Tallies collection, register all Tallies, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_tally(first_tally) -tallies_file.add_tally(second_tally) -tallies_file.add_tally(third_tally) +# Instantiate a Tallies collection and export to XML +tallies_file = openmc.Tallies((first_tally, second_tally, third_tally)) tallies_file.export_to_xml() diff --git a/examples/python/boxes/build-xml.py b/examples/python/boxes/build-xml.py index 318af2265..814f60beb 100644 --- a/examples/python/boxes/build-xml.py +++ b/examples/python/boxes/build-xml.py @@ -36,10 +36,9 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([fuel1, fuel2, moderator]) materials_file.default_xs = '71c' -materials_file.add_materials([fuel1, fuel2, moderator]) materials_file.export_to_xml() @@ -129,7 +128,6 @@ plot.width = [20, 20] plot.pixels = [200, 200] plot.color = 'cell' -# Instantiate a Plots collection, add Plot, and export to XML -plot_file = openmc.Plots() -plot_file.add_plot(plot) +# Instantiate a Plots collection and export to XML +plot_file = openmc.Plots([plot]) plot_file.export_to_xml() diff --git a/examples/python/lattice/hexagonal/build-xml.py b/examples/python/lattice/hexagonal/build-xml.py index 04002faf2..ef3a12847 100644 --- a/examples/python/lattice/hexagonal/build-xml.py +++ b/examples/python/lattice/hexagonal/build-xml.py @@ -35,10 +35,9 @@ iron = openmc.Material(material_id=3, name='iron') iron.set_density('g/cc', 7.9) iron.add_nuclide(fe56, 1.) -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([moderator, fuel, iron]) materials_file.default_xs = '71c' -materials_file.add_materials([moderator, fuel, iron]) materials_file.export_to_xml() @@ -152,9 +151,7 @@ plot_yz.pixels = [400, 400] plot_yz.color = 'mat' # Instantiate a Plots collection, add plots, and export to XML -plot_file = openmc.Plots() -plot_file.add_plot(plot_xy) -plot_file.add_plot(plot_yz) +plot_file = openmc.Plots((plot_xy, plot_yz)) plot_file.export_to_xml() @@ -167,7 +164,6 @@ tally = openmc.Tally(tally_id=1) tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])] tally.scores = ['total'] -# Instantiate a Tallies collection, register Tally/Mesh, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_tally(tally) +# Instantiate a Tallies collection and export to XML +tallies_file = openmc.Tallies([tally]) tallies_file.export_to_xml() diff --git a/examples/python/lattice/nested/build-xml.py b/examples/python/lattice/nested/build-xml.py index 0e4e459e2..b2d611d34 100644 --- a/examples/python/lattice/nested/build-xml.py +++ b/examples/python/lattice/nested/build-xml.py @@ -30,10 +30,9 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials((moderator, fuel)) materials_file.default_xs = '71c' -materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() @@ -150,9 +149,8 @@ plot.width = [4, 4] plot.pixels = [400, 400] plot.color = 'mat' -# Instantiate a Plots object, add Plot, and export to XML -plot_file = openmc.Plots() -plot_file.add_plot(plot) +# Instantiate a Plots object and export to XML +plot_file = openmc.Plots([plot]) plot_file.export_to_xml() @@ -177,7 +175,5 @@ tally.filters = [mesh_filter] tally.scores = ['total'] # Instantiate a Tallies collection, register Tally/Mesh, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_mesh(mesh) -tallies_file.add_tally(tally) +tallies_file = openmc.Tallies([tally]) tallies_file.export_to_xml() diff --git a/examples/python/lattice/simple/build-xml.py b/examples/python/lattice/simple/build-xml.py index 8d9481aaa..65c355479 100644 --- a/examples/python/lattice/simple/build-xml.py +++ b/examples/python/lattice/simple/build-xml.py @@ -30,10 +30,9 @@ moderator.add_nuclide(h1, 2.) moderator.add_nuclide(o16, 1.) moderator.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([moderator, fuel]) materials_file.default_xs = '71c' -materials_file.add_materials([moderator, fuel]) materials_file.export_to_xml() @@ -142,9 +141,8 @@ plot.width = [4, 4] plot.pixels = [400, 400] plot.color = 'mat' -# Instantiate a Plots collection, add Plot, and export to XML -plot_file = openmc.Plots() -plot_file.add_plot(plot) +# Instantiate a Plots collection and export to XML +plot_file = openmc.Plots([plot]) plot_file.export_to_xml() @@ -173,8 +171,6 @@ tally.filters = [mesh_filter] tally.scores = ['total'] tally.triggers = [trigger] -# Instantiate a Tallies collection, register Tally/Mesh, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_mesh(mesh) -tallies_file.add_tally(tally) +# Instantiate a Tallies collection and export to XML +tallies_file = openmc.Tallies([tally]) tallies_file.export_to_xml() diff --git a/examples/python/pincell/build-xml.py b/examples/python/pincell/build-xml.py index 561df2b5a..a3be3e97e 100644 --- a/examples/python/pincell/build-xml.py +++ b/examples/python/pincell/build-xml.py @@ -100,10 +100,9 @@ borated_water.add_nuclide(o16, 2.4672e-2) borated_water.add_nuclide(o17, 6.0099e-5) borated_water.add_s_alpha_beta('HH2O', '71t') -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([uo2, helium, zircaloy, borated_water]) materials_file.default_xs = '71c' -materials_file.add_materials([uo2, helium, zircaloy, borated_water]) materials_file.export_to_xml() @@ -197,8 +196,6 @@ tally = openmc.Tally(tally_id=1, name='tally 1') tally.filters = [energy_filter, mesh_filter] tally.scores = ['flux', 'fission', 'nu-fission'] -# Instantiate a Tallies collection, register all Tallies, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_mesh(mesh) -tallies_file.add_tally(tally) +# Instantiate a Tallies collection and export to XML +tallies_file = openmc.Tallies([tally]) tallies_file.export_to_xml() diff --git a/examples/python/pincell_multigroup/build-xml.py b/examples/python/pincell_multigroup/build-xml.py index 697a596d9..c7d6dfc8b 100644 --- a/examples/python/pincell_multigroup/build-xml.py +++ b/examples/python/pincell_multigroup/build-xml.py @@ -81,10 +81,9 @@ water = openmc.Material(material_id=2, name='Water') water.set_density('macro', 1.0) water.add_macroscopic(h2o_data) -# Instantiate a Materials collection, register all Materials, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([uo2, water]) materials_file.default_xs = '300K' -materials_file.add_materials([uo2, water]) materials_file.export_to_xml() @@ -167,14 +166,9 @@ mesh_filter.mesh = mesh # Instantiate the Tally tally = openmc.Tally(tally_id=1, name='tally 1') -tally.add_filter(energy_filter) -tally.add_filter(mesh_filter) -tally.add_score('flux') -tally.add_score('fission') -tally.add_score('nu-fission') +tally.filters = [energy_filter, mesh_filter] +tally.scores = ['flux', 'fission', 'nu-fission'] # Instantiate a Tallies collection, register all Tallies, and export to XML -tallies_file = openmc.Tallies() -tallies_file.add_mesh(mesh) -tallies_file.add_tally(tally) +tallies_file = openmc.Tallies([tally]) tallies_file.export_to_xml() diff --git a/examples/python/reflective/build-xml.py b/examples/python/reflective/build-xml.py index e4776e744..4ecd0351f 100644 --- a/examples/python/reflective/build-xml.py +++ b/examples/python/reflective/build-xml.py @@ -23,10 +23,9 @@ fuel = openmc.Material(material_id=1, name='fuel') fuel.set_density('g/cc', 4.5) fuel.add_nuclide(u235, 1.) -# Instantiate a Materials collection, register Material, and export to XML -materials_file = openmc.Materials() +# Instantiate a Materials collection and export to XML +materials_file = openmc.Materials([fuel]) materials_file.default_xs = '71c' -materials_file.add_material(fuel) materials_file.export_to_xml() diff --git a/openmc/checkvalue.py b/openmc/checkvalue.py index 53f4b8368..62b843a3a 100644 --- a/openmc/checkvalue.py +++ b/openmc/checkvalue.py @@ -1,3 +1,4 @@ +import copy from collections import Iterable from numbers import Integral, Real @@ -57,7 +58,7 @@ def check_type(name, value, expected_type, expected_iter_type=None): else: msg = 'Unable to set "{0}" to "{1}" which is not of type "{2}"'.format( name, value, expected_type.__name__) - raise ValueError(msg) + raise TypeError(msg) if expected_iter_type: for item in value: @@ -71,7 +72,7 @@ def check_type(name, value, expected_type, expected_iter_type=None): msg = 'Unable to set "{0}" to "{1}" since each item must be ' \ 'of type "{2}"'.format(name, value, expected_iter_type.__name__) - raise ValueError(msg) + raise TypeError(msg) def check_iterable_type(name, value, expected_type, min_depth=1, max_depth=1): @@ -122,7 +123,7 @@ def check_iterable_type(name, value, expected_type, min_depth=1, max_depth=1): if len(tree) < min_depth: msg = 'Error setting "{0}": The item at {1} does not meet the '\ 'minimum depth of {2}'.format(name, ind_str, min_depth) - raise ValueError(msg) + raise TypeError(msg) # This item is okay. Move on to the next item. index[-1] += 1 @@ -140,7 +141,7 @@ def check_iterable_type(name, value, expected_type, min_depth=1, max_depth=1): msg = 'Error setting {0}: Found an iterable at {1}, items '\ 'in that iterable exceed the maximum depth of {2}' \ .format(name, ind_str, max_depth) - raise ValueError(msg) + raise TypeError(msg) else: # This item is completely unexpected. @@ -148,7 +149,7 @@ def check_iterable_type(name, value, expected_type, min_depth=1, max_depth=1): "item at {2} is of type '{3}'"\ .format(name, expected_type.__name__, ind_str, type(current_item).__name__) - raise ValueError(msg) + raise TypeError(msg) def check_length(name, value, length_min, length_max=None): @@ -278,6 +279,21 @@ class CheckedList(list): for item in items: self.append(item) + def __add__(self, other): + new_instance = copy.copy(self) + new_instance += other + return new_instance + + def __radd__(self, other): + return self + other + + def __iadd__(self, other): + check_type('CheckedList add operand', other, Iterable, + self.expected_type) + for item in other: + self.append(item) + return self + def append(self, item): """Append item to list diff --git a/openmc/material.py b/openmc/material.py index 97c7cedca..b3c281341 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -8,7 +8,7 @@ if sys.version_info[0] >= 3: basestring = str import openmc -from openmc.checkvalue import check_type, check_value, check_greater_than +import openmc.checkvalue as cv from openmc.clean_xml import * @@ -202,15 +202,15 @@ class Material(object): self._id = AUTO_MATERIAL_ID AUTO_MATERIAL_ID += 1 else: - check_type('material ID', material_id, Integral) - check_greater_than('material ID', material_id, 0, equality=True) + cv.check_type('material ID', material_id, Integral) + cv.check_greater_than('material ID', material_id, 0, equality=True) self._id = material_id @name.setter def name(self, name): if name is not None: - check_type('name for Material ID="{0}"'.format(self._id), - name, basestring) + cv.check_type('name for Material ID="{0}"'.format(self._id), + name, basestring) self._name = name else: self._name = '' @@ -228,9 +228,9 @@ class Material(object): """ - check_type('the density for Material ID="{0}"'.format(self._id), - density, Real) - check_value('density units', units, DENSITY_UNITS) + cv.check_type('the density for Material ID="{0}"'.format(self._id), + density, Real) + cv.check_value('density units', units, DENSITY_UNITS) if density is None and units is not 'sum': msg = 'Unable to set the density for Material ID="{0}" ' \ @@ -642,9 +642,25 @@ class Material(object): return element -class Materials(object): - """Collection of Materials used for an OpenMC simulation. Corresponds directly - to the materials.xml input file. +class Materials(cv.CheckedList): + """Collection of Materials used for an OpenMC simulation. + + This class corresponds directly to the materials.xml input file. It can be + thought of as a normal Python list where each member is a + :class:`Material`. It behaves like a list as the following example + demonstrates: + + >>> fuel = openmc.Material() + >>> clad = openmc.Material() + >>> water = openmc.Material() + >>> m = openmc.Materials([fuel]) + >>> m.append(water) + >>> m += [clad] + + Parameters + ---------- + materials : Iterable of openmc.Material + Materials to add to the collection Attributes ---------- @@ -654,10 +670,12 @@ class Materials(object): """ - def __init__(self): - self._materials = [] + def __init__(self, materials=None): + super(Materials, self).__init__(Material, 'materials collection') self._default_xs = None self._materials_file = ET.Element("materials") + if materials is not None: + self += materials @property def default_xs(self): @@ -665,11 +683,14 @@ class Materials(object): @default_xs.setter def default_xs(self, xs): - check_type('default xs', xs, basestring) + cv.check_type('default xs', xs, basestring) self._default_xs = xs def add_material(self, material): - """Add a material to the file. + """Append material to collection + + .. deprecated:: 0.8 + Use :meth:`Materials.append` instead. Parameters ---------- @@ -677,51 +698,72 @@ class Materials(object): Material to add """ - - if not isinstance(material, Material): - msg = 'Unable to add a non-Material "{0}" to the ' \ - 'Materials instance'.format(material) - raise ValueError(msg) - - self._materials.append(material) + warnings.warn("Materials.add_material(...) has been deprecated and may be " + "removed in a future version. Use Material.append(...) " + "instead.", DeprecationWarning) + self.append(material) def add_materials(self, materials): - """Add multiple materials to the file. + """Add multiple materials to the collection + + .. deprecated:: 0.8 + Use compound assignment instead. Parameters ---------- - materials : tuple or list of openmc.Material + materials : Iterable of openmc.Material Materials to add """ - - if not isinstance(materials, Iterable): - msg = 'Unable to create OpenMC materials.xml file from "{0}" which ' \ - 'is not iterable'.format(materials) - raise ValueError(msg) - + warnings.warn("Materials.add_materials(...) has been deprecated and may be " + "removed in a future version. Use compound assignment " + "instead.", DeprecationWarning) for material in materials: - self.add_material(material) + self.append(material) + + def append(self, material): + """Append material to collection + + Parameters + ---------- + material : openmc.Material + Material to append + + """ + super(Materials, self).append(material) + + def insert(self, index, material): + """Insert material before index + + Parameters + ---------- + index : int + Index in list + material : openmc.Material + Material to insert + + """ + super(Materials, self).insert(index, material) def remove_material(self, material): """Remove a material from the file + .. deprecated:: 0.8 + Use :meth:`Materials.remove` instead. + Parameters ---------- material : openmc.Material Material to remove """ - - if not isinstance(material, Material): - msg = 'Unable to remove a non-Material "{0}" from the ' \ - 'Materials instance'.format(material) - raise ValueError(msg) - - self._materials.remove(material) + warnings.warn("Materials.remove_material(...) has been deprecated and " + "may be removed in a future version. Use " + "Materials.remove(...) instead.", DeprecationWarning) + self.remove(material) def make_isotropic_in_lab(self): - for material in self._materials: + for material in self: material.make_isotropic_in_lab() def _create_material_subelements(self): @@ -729,7 +771,7 @@ class Materials(object): subelement = ET.SubElement(self._materials_file, "default_xs") subelement.text = self._default_xs - for material in self._materials: + for material in self: xml_element = material.get_material_xml() self._materials_file.append(xml_element) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 8d5e9854e..f3bf2018d 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -370,7 +370,7 @@ class Library(object): for mgxs_type in self.mgxs_types: mgxs = self.get_mgxs(domain, mgxs_type) for tally_id, tally in mgxs.tallies.items(): - tallies_file.add_tally(tally, merge=merge) + tallies_file.append(tally, merge=merge) def load_from_statepoint(self, statepoint): """Extracts tallies in an OpenMC StatePoint with the data needed to diff --git a/openmc/plots.py b/openmc/plots.py index a967cb060..9167e55d5 100644 --- a/openmc/plots.py +++ b/openmc/plots.py @@ -2,6 +2,7 @@ from collections import Iterable from numbers import Real, Integral from xml.etree import ElementTree as ET import sys +import warnings import numpy as np @@ -401,43 +402,90 @@ class Plot(object): return element -class Plots(object): - """Collection of Plots used for an OpenMC simulation. Corresponds directly to - the plots.xml input file. +class Plots(cv.CheckedList): + """Collection of Plots used for an OpenMC simulation. + + This class corresponds directly to the plots.xml input file. It can be + thought of as a normal Python list where each member is a :class:`Plot`. It + behaves like a list as the following example demonstrates: + + >>> xz_plot = openmc.Plot() + >>> big_plot = openmc.Plot() + >>> small_plot = openmc.Plot() + >>> p = openmc.Plots((xz_plot, big_plot)) + >>> p.append(small_plot) + >>> small_plot = p.pop() + + Parameters + ---------- + plots : Iterable of openmc.Plot + Plots to add to the collection """ - def __init__(self): - self._plots = [] + def __init__(self, plots=None): + super(Plots, self).__init__(Plot, 'plots collection') self._plots_file = ET.Element("plots") + if plots is not None: + self += plots def add_plot(self, plot): """Add a plot to the file. + .. deprecated:: 0.8 + Use :meth:`Plots.append` instead. + Parameters ---------- plot : openmc.Plot Plot to add """ + warnings.warn("Plots.add_plot(...) has been deprecated and may be " + "removed in a future version. Use Plots.append(...) " + "instead.", DeprecationWarning) + self.append(plot) - if not isinstance(plot, Plot): - msg = 'Unable to add a non-Plot "{0}" to the Plots instance'.format(plot) - raise ValueError(msg) + def append(self, plot): + """Append plot to collection - self._plots.append(plot) + Parameters + ---------- + plot : openmc.Plot + Plot to append + + """ + super(Plots, self).append(plot) + + def insert(self, index, plot): + """Insert plot before index + + Parameters + ---------- + index : int + Index in list + plot : openmc.Plot + Plot to insert + + """ + super(Plots, self).insert(index, plot) def remove_plot(self, plot): """Remove a plot from the file. + .. deprecated:: 0.8 + Use :meth:`Plots.remove` instead. + Parameters ---------- plot : openmc.Plot Plot to remove """ - - self._plots.remove(plot) + warnings.warn("Plots.remove_plot(...) has been deprecated and may be " + "removed in a future version. Use Plots.remove(...) " + "instead.", DeprecationWarning) + self.remove(plot) def colorize(self, geometry, seed=1): """Generate a consistent color scheme for each domain in each plot. @@ -455,7 +503,7 @@ class Plots(object): """ - for plot in self._plots: + for plot in self: plot.colorize(geometry, seed) @@ -481,11 +529,11 @@ class Plots(object): """ - for plot in self._plots: + for plot in self: plot.highlight_domains(geometry, domains, seed, alpha, background) def _create_plot_subelements(self): - for plot in self._plots: + for plot in self: xml_element = plot.get_plot_xml() if len(plot._name) > 0: diff --git a/openmc/tallies.py b/openmc/tallies.py index 90b09f582..3a5a1f1e8 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -3419,65 +3419,108 @@ class Tally(object): return new_tally -class Tallies(object): - """Collection of Tallies used for an OpenMC simulation. Corresponds directly to - the tallies.xml input file. +class Tallies(cv.CheckedList): + """Collection of Tallies used for an OpenMC simulation. + + This class corresponds directly to the tallies.xml input file. It can be + thought of as a normal Python list where each member is a :class:`Tally`. It + behaves like a list as the following example demonstrates: + + >>> t1 = openmc.Tally() + >>> t2 = openmc.Tally() + >>> t3 = openmc.Tally() + >>> tallies = openmc.Tallies([t1]) + >>> tallies.append(t2) + >>> tallies += [t3] + + Parameters + ---------- + tallies : Iterable of openmc.Tally + Tallies to add to the collection """ - def __init__(self): - self._tallies = [] - self._meshes = [] + def __init__(self, tallies=None): + super(Tallies, self).__init__(Tally, 'tallies collection') self._tallies_file = ET.Element("tallies") - - @property - def tallies(self): - return self._tallies - - @property - def meshes(self): - return self._meshes + if tallies is not None: + self += tallies def add_tally(self, tally, merge=False): - """Add a tally to the file + """Append tally to collection + + .. deprecated:: 0.8 + Use :meth:`Tallies.append` instead. Parameters ---------- tally : openmc.Tally - Tally to add to file + Tally to add merge : bool Indicate whether the tally should be merged with an existing tally, if possible. Defaults to False. """ + warnings.warn("Tallies.add_tally(...) has been deprecated and may be " + "removed in a future version. Use Tallies.append(...) " + "instead.", DeprecationWarning) + self.append(tally, merge) + def append(self, tally, merge=False): + """Append tally to collection + + Parameters + ---------- + tally : openmc.Tally + Tally to append + merge : bool + Indicate whether the tally should be merged with an existing tally, + if possible. Defaults to False. + + """ if not isinstance(tally, Tally): msg = 'Unable to add a non-Tally "{0}" to the Tallies instance'.format(tally) - raise ValueError(msg) + raise TypeError(msg) if merge: merged = False # Look for a tally to merge with this one - for i, tally2 in enumerate(self._tallies): + for i, tally2 in enumerate(self): # If a mergeable tally is found if tally2.can_merge(tally): # Replace tally 2 with the merged tally merged_tally = tally2.merge(tally) - self._tallies[i] = merged_tally + self[i] = merged_tally merged = True break # If not mergeable tally was found, simply add this tally if not merged: - self._tallies.append(tally) + super(Tallies, self).append(tally) else: - self._tallies.append(tally) + super(Tallies, self).append(tally) + + def insert(self, index, item): + """Insert tally before index + + Parameters + ---------- + index : int + Index in list + item : openmc.Tally + Tally to insert + + """ + super(Tallies, self).insert(index, item) def remove_tally(self, tally): - """Remove a tally from the file + """Remove a tally from the collection + + .. deprecated:: 0.8 + Use :meth:`Tallies.remove` instead. Parameters ---------- @@ -3485,8 +3528,11 @@ class Tallies(object): Tally to remove """ + warnings.warn("Tallies.remove_tally(...) has been deprecated and may " + "be removed in a future version. Use Tallies.remove(...) " + "instead.", DeprecationWarning) - self._tallies.remove(tally) + self.remove(tally) def merge_tallies(self): """Merge any mergeable tallies together. Note that n-way merges are @@ -3494,8 +3540,8 @@ class Tallies(object): """ - for i, tally1 in enumerate(self._tallies): - for j, tally2 in enumerate(self._tallies): + for i, tally1 in enumerate(self): + for j, tally2 in enumerate(self): # Do not merge the same tally with itself if i == j: continue @@ -3504,10 +3550,10 @@ class Tallies(object): if tally1.can_merge(tally2): # Replace tally 1 with the merged tally merged_tally = tally1.merge(tally2) - self._tallies[i] = merged_tally + self[i] = merged_tally # Remove tally 2 since it is no longer needed - self._tallies.pop(j) + self.pop(j) # Continue iterating from the first loop break @@ -3515,6 +3561,10 @@ class Tallies(object): def add_mesh(self, mesh): """Add a mesh to the file + .. deprecated:: 0.8 + Meshes that appear in a tally are automatically added to the + collection. + Parameters ---------- mesh : openmc.Mesh @@ -3522,36 +3572,43 @@ class Tallies(object): """ - if not isinstance(mesh, Mesh): - msg = 'Unable to add a non-Mesh "{0}" to the Tallies instance'.format(mesh) - raise ValueError(msg) - - self._meshes.append(mesh) + warnings.warn("Tallies.add_mesh(...) has been deprecated and may be " + "removed in a future version. Meshes that appear in a " + "tally are automatically added to the collection.", + DeprecationWarning) def remove_mesh(self, mesh): """Remove a mesh from the file + .. deprecated:: 0.8 + Meshes do not need to be managed explicitly. + Parameters ---------- mesh : openmc.Mesh Mesh to remove from the file """ - - self._meshes.remove(mesh) + warnings.warn("Tallies.remove_mesh(...) has been deprecated and may be " + "removed in a future version. Meshes do not need to be " + "managed explicitly.", DeprecationWarning) def _create_tally_subelements(self): - for tally in self._tallies: + for tally in self: xml_element = tally.get_tally_xml() self._tallies_file.append(xml_element) def _create_mesh_subelements(self): - for mesh in self._meshes: - if len(mesh._name) > 0: - self._tallies_file.append(ET.Comment(mesh._name)) + already_written = set() + for tally in self: + for f in tally.filters: + if f.type == 'mesh' and f.mesh not in already_written: + if len(f.mesh.name) > 0: + self._tallies_file.append(ET.Comment(f.mesh.name)) - xml_element = mesh.get_mesh_xml() - self._tallies_file.append(xml_element) + xml_element = f.mesh.get_mesh_xml() + self._tallies_file.append(xml_element) + already_written.add(f.mesh) def export_to_xml(self): """Create a tallies.xml file that can be used for a simulation. diff --git a/tests/input_set.py b/tests/input_set.py index 3be6c1db4..2c6841e25 100644 --- a/tests/input_set.py +++ b/tests/input_set.py @@ -267,9 +267,9 @@ class InputSet(object): # Define the materials file. self.materials.default_xs = '71c' - self.materials.add_materials((fuel, clad, cold_water, hot_water, - rpv_steel, lower_rad_ref, upper_rad_ref, bot_plate, bot_nozzle, - top_nozzle, top_fa, bot_fa)) + self.materials += (fuel, clad, cold_water, hot_water, rpv_steel, + lower_rad_ref, upper_rad_ref, bot_plate, + bot_nozzle, top_nozzle, top_fa, bot_fa) # Define surfaces. s1 = openmc.ZCylinder(R=0.41, surface_id=1) @@ -590,7 +590,7 @@ class MGInputSet(InputSet): # Define the materials file. self.materials.default_xs = '71c' - self.materials.add_materials((uo2, clad, water)) + self.materials += (uo2, clad, water) # Define surfaces. diff --git a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py index 94562e6d9..03e55d32f 100644 --- a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py +++ b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py @@ -54,12 +54,11 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): # Initialize the tallies tally = openmc.Tally(name='distribcell tally', tally_id=27) - tally.add_filter(distrib_filter) - tally.add_score('nu-fission') + tally.filters.append(distrib_filter) + tally.scores.append('nu-fission') # Initialize the tallies file - tallies_file = openmc.Tallies() - tallies_file.add_tally(tally) + tallies_file = openmc.Tallies([tally]) # Assign the tallies file to the input set self._input_set.tallies = tallies_file diff --git a/tests/test_distribmat/test_distribmat.py b/tests/test_distribmat/test_distribmat.py index ded2863bd..d8f78c5cf 100644 --- a/tests/test_distribmat/test_distribmat.py +++ b/tests/test_distribmat/test_distribmat.py @@ -28,9 +28,8 @@ class DistribmatTestHarness(PyAPITestHarness): light_fuel.set_density('g/cc', 2.0) light_fuel.add_nuclide('U-235', 1.0) - mats_file = openmc.Materials() + mats_file = openmc.Materials([moderator, dense_fuel, light_fuel]) mats_file.default_xs = '71c' - mats_file.add_materials([moderator, dense_fuel, light_fuel]) mats_file.export_to_xml() diff --git a/tests/test_mg_max_order/test_mg_max_order.py b/tests/test_mg_max_order/test_mg_max_order.py index 2c4db58df..7f59572cf 100644 --- a/tests/test_mg_max_order/test_mg_max_order.py +++ b/tests/test_mg_max_order/test_mg_max_order.py @@ -27,7 +27,7 @@ class MGNuclideInputSet(MGInputSet): # Define the materials file. self.materials.default_xs = '71c' - self.materials.add_materials((uo2, clad, water)) + self.materials += (uo2, clad, water) # Define surfaces. diff --git a/tests/test_mg_nuclide/test_mg_nuclide.py b/tests/test_mg_nuclide/test_mg_nuclide.py index 0fa7184a3..866840ddf 100644 --- a/tests/test_mg_nuclide/test_mg_nuclide.py +++ b/tests/test_mg_nuclide/test_mg_nuclide.py @@ -26,7 +26,7 @@ class MGNuclideInputSet(MGInputSet): # Define the materials file. self.materials.default_xs = '71c' - self.materials.add_materials((uo2, clad, water)) + self.materials += (uo2, clad, water) # Define surfaces. diff --git a/tests/test_mg_tallies/test_mg_tallies.py b/tests/test_mg_tallies/test_mg_tallies.py index ffc57f9e9..3048f4a39 100644 --- a/tests/test_mg_tallies/test_mg_tallies.py +++ b/tests/test_mg_tallies/test_mg_tallies.py @@ -27,24 +27,15 @@ class MGTalliesTestHarness(PyAPITestHarness): mat_filter = openmc.Filter(type='material', bins=[1,2,3]) tally1 = openmc.Tally(tally_id=1) - tally1.add_filter(mesh_filter) - tally1.add_score('total') - tally1.add_score('absorption') - tally1.add_score('flux') - tally1.add_score('fission') - tally1.add_score('nu-fission') + tally1.filters = [mesh_filter] + tally1.scores = ['total', 'absorption', 'flux', + 'fission', 'nu-fission'] tally2 = openmc.Tally(tally_id=2) - tally2.add_filter(mat_filter) - tally2.add_filter(energy_filter) - tally2.add_filter(energyout_filter) - tally2.add_score('scatter') - tally2.add_score('nu-scatter') + tally2.filters = [mat_filter, energy_filter, energyout_filter] + tally2.scores = ['scatter', 'nu-scatter'] - self._input_set.tallies = openmc.Tallies() - self._input_set.tallies.add_mesh(mesh) - self._input_set.tallies.add_tally(tally1) - self._input_set.tallies.add_tally(tally2) + self._input_set.tallies = openmc.Tallies([tally1, tally2]) super(MGTalliesTestHarness, self)._build_inputs() diff --git a/tests/test_resonance_scattering/test_resonance_scattering.py b/tests/test_resonance_scattering/test_resonance_scattering.py index 5cecfedc4..b752cf7f3 100644 --- a/tests/test_resonance_scattering/test_resonance_scattering.py +++ b/tests/test_resonance_scattering/test_resonance_scattering.py @@ -17,9 +17,8 @@ class ResonanceScatteringTestHarness(PyAPITestHarness): mat.add_nuclide('Pu-239', 0.02) mat.add_nuclide('H-1', 20.0) - mats_file = openmc.Materials() + mats_file = openmc.Materials([mat]) mats_file.default_xs = '71c' - mats_file.add_material(mat) mats_file.export_to_xml() # Geometry diff --git a/tests/test_source/test_source.py b/tests/test_source/test_source.py index 1e41bd10e..0abae4344 100644 --- a/tests/test_source/test_source.py +++ b/tests/test_source/test_source.py @@ -16,8 +16,7 @@ class SourceTestHarness(PyAPITestHarness): mat1 = openmc.Material(material_id=1) mat1.set_density('g/cm3', 4.5) mat1.add_nuclide(openmc.Nuclide('U-235', '71c'), 1.0) - materials = openmc.Materials() - materials.add_material(mat1) + materials = openmc.Materials([mat1]) materials.export_to_xml() sphere = openmc.Sphere(surface_id=1, R=10.0, boundary_type='vacuum') diff --git a/tests/test_tallies/test_tallies.py b/tests/test_tallies/test_tallies.py index bb0273589..52d4084fd 100644 --- a/tests/test_tallies/test_tallies.py +++ b/tests/test_tallies/test_tallies.py @@ -42,7 +42,8 @@ class TalliesTestHarness(PyAPITestHarness): mesh_2x2.lower_left = [-182.07, -182.07] mesh_2x2.upper_right = [182.07, 182.07] mesh_2x2.dimension = [2, 2] - mesh_filter = Filter(type='mesh', bins=(1,)) + mesh_filter = Filter(type='mesh') + mesh_filter.mesh = mesh_2x2 azimuthal_tally4 = Tally() azimuthal_tally4.filters = [azimuthal_filter2, mesh_filter] azimuthal_tally4.scores = ['flux'] @@ -171,32 +172,18 @@ class TalliesTestHarness(PyAPITestHarness): all_nuclide_tallies[0].estimator = 'collision' self._input_set.tallies = Tallies() - self._input_set.tallies.add_tally(azimuthal_tally1) - self._input_set.tallies.add_tally(azimuthal_tally2) - self._input_set.tallies.add_tally(azimuthal_tally3) - self._input_set.tallies.add_tally(azimuthal_tally4) - self._input_set.tallies.add_tally(cellborn_tally) - self._input_set.tallies.add_tally(dg_tally) - self._input_set.tallies.add_tally(energy_tally) - self._input_set.tallies.add_tally(energyout_tally) - self._input_set.tallies.add_tally(transfer_tally) - self._input_set.tallies.add_tally(material_tally) - self._input_set.tallies.add_tally(mu_tally1) - self._input_set.tallies.add_tally(mu_tally2) - self._input_set.tallies.add_tally(mu_tally3) - self._input_set.tallies.add_tally(polar_tally1) - self._input_set.tallies.add_tally(polar_tally2) - self._input_set.tallies.add_tally(polar_tally3) - self._input_set.tallies.add_tally(polar_tally4) - self._input_set.tallies.add_tally(universe_tally) - [self._input_set.tallies.add_tally(t) for t in score_tallies] - [self._input_set.tallies.add_tally(t) for t in flux_tallies] - self._input_set.tallies.add_tally(scatter_tally1) - self._input_set.tallies.add_tally(scatter_tally2) - [self._input_set.tallies.add_tally(t) for t in total_tallies] - self._input_set.tallies.add_tally(questionable_tally) - [self._input_set.tallies.add_tally(t) for t in all_nuclide_tallies] - self._input_set.tallies.add_mesh(mesh_2x2) + self._input_set.tallies += ( + [azimuthal_tally1, azimuthal_tally2, azimuthal_tally3, + azimuthal_tally4, cellborn_tally, dg_tally, energy_tally, + energyout_tally, transfer_tally, material_tally, mu_tally1, + mu_tally2, mu_tally3, polar_tally1, polar_tally2, polar_tally3, + polar_tally4, universe_tally]) + self._input_set.tallies += score_tallies + self._input_set.tallies += flux_tallies + self._input_set.tallies += (scatter_tally1, scatter_tally2) + self._input_set.tallies += total_tallies + self._input_set.tallies.append(questionable_tally) + self._input_set.tallies += all_nuclide_tallies self._input_set.export() diff --git a/tests/test_tally_aggregation/test_tally_aggregation.py b/tests/test_tally_aggregation/test_tally_aggregation.py index 009a7dc09..359afbe34 100644 --- a/tests/test_tally_aggregation/test_tally_aggregation.py +++ b/tests/test_tally_aggregation/test_tally_aggregation.py @@ -15,9 +15,6 @@ class TallyAggregationTestHarness(PyAPITestHarness): # The summary.h5 file needs to be created to read in the tallies self._input_set.settings.output = {'summary': True} - # Initialize the tallies file - tallies_file = openmc.Tallies() - # Initialize the nuclides u235 = openmc.Nuclide('U-235') u238 = openmc.Nuclide('U-238') @@ -33,7 +30,7 @@ class TallyAggregationTestHarness(PyAPITestHarness): tally.filters = [energy_filter, distrib_filter] tally.scores = ['nu-fission', 'total'] tally.nuclides = [u235, u238, pu239] - tallies_file.add_tally(tally) + tallies_file = openmc.Tallies([tally]) # Export tallies to file self._input_set.tallies = tallies_file diff --git a/tests/test_tally_arithmetic/test_tally_arithmetic.py b/tests/test_tally_arithmetic/test_tally_arithmetic.py index ffea74603..8e2d2b349 100644 --- a/tests/test_tally_arithmetic/test_tally_arithmetic.py +++ b/tests/test_tally_arithmetic/test_tally_arithmetic.py @@ -43,14 +43,13 @@ class TallyArithmeticTestHarness(PyAPITestHarness): tally.filters = [material_filter, energy_filter, distrib_filter] tally.scores = ['nu-fission', 'total'] tally.nuclides = [u235, pu239] - tallies_file.add_tally(tally) + tallies_file.append(tally) tally = openmc.Tally(name='tally 2') tally.filters = [energy_filter, mesh_filter] tally.scores = ['total', 'fission'] tally.nuclides = [u238, u235] - tallies_file.add_tally(tally) - tallies_file.add_mesh(mesh) + tallies_file.append(tally) # Export tallies to file self._input_set.tallies = tallies_file diff --git a/tests/test_tally_slice_merge/test_tally_slice_merge.py b/tests/test_tally_slice_merge/test_tally_slice_merge.py index 933fdf6fa..85dd532c6 100644 --- a/tests/test_tally_slice_merge/test_tally_slice_merge.py +++ b/tests/test_tally_slice_merge/test_tally_slice_merge.py @@ -70,9 +70,7 @@ class TallySliceMergeTestHarness(PyAPITestHarness): distribcell_tally.add_nuclide(nuclide) # Add tallies to a Tallies object - tallies_file = openmc.Tallies() - tallies_file.add_tally(tallies[0]) - tallies_file.add_tally(distribcell_tally) + tallies_file = openmc.Tallies((tallies[0], distribcell_tally)) # Export tallies to file self._input_set.tallies = tallies_file From ed5505cd979b72ee6a32f5e4624ec614ef34e802 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 29 Apr 2016 22:13:41 -0400 Subject: [PATCH 056/147] Added option to transpose array returned by ScatterMatrixXS.get_xs(...) method --- openmc/mgxs/mgxs.py | 25 +++++++++++++++++++------ 1 file changed, 19 insertions(+), 6 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 33255de30..90b956b21 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -654,7 +654,8 @@ class MGXS(object): self.tallies[tally_type] = sp_tally def get_xs(self, groups='all', subdomains='all', nuclides='all', - xs_type='macro', order_groups='increasing', value='mean'): + xs_type='macro', order_groups='increasing', + value='mean', **kwargs): """Returns an array of multi-group cross sections. This method constructs a 2D NumPy array for the requested multi-group @@ -1143,7 +1144,7 @@ class MGXS(object): def build_hdf5_store(self, filename='mgxs.h5', directory='mgxs', subdomains='all', nuclides='all', - xs_type='macro', append=True): + xs_type='macro', row_column='inout', append=True): """Export the multi-group cross section data to an HDF5 binary file. This method constructs an HDF5 file which stores the multi-group @@ -1172,6 +1173,9 @@ class MGXS(object): xs_type: {'macro', 'micro'} Store the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + row_column: {'inout', 'outin'} + Store scattering matrices indexed first by incoming group and second + by outgoing group ('inout'), or vice versa ('outin'). append : bool If true, appends to an existing HDF5 file with the same filename directory (if one exists). Defaults to True. @@ -1258,9 +1262,9 @@ class MGXS(object): # Extract the cross section for this subdomain and nuclide average = self.get_xs(subdomains=[subdomain], nuclides=[nuclide], - xs_type=xs_type, value='mean') + xs_type=xs_type, value='mean', row_column=row_column) std_dev = self.get_xs(subdomains=[subdomain], nuclides=[nuclide], - xs_type=xs_type, value='std_dev') + xs_type=xs_type, value='std_dev', row_column=row_column) average = average.squeeze() std_dev = std_dev.squeeze() @@ -1973,7 +1977,8 @@ class ScatterMatrixXS(MGXS): def get_xs(self, in_groups='all', out_groups='all', subdomains='all', nuclides='all', xs_type='macro', - order_groups='increasing', value='mean'): + order_groups='increasing', row_column='inout', + value='mean', **kwargs): """Returns an array of multi-group cross sections. This method constructs a 2D NumPy array for the requested scattering @@ -1999,6 +2004,9 @@ class ScatterMatrixXS(MGXS): Return the cross section indexed according to increasing or decreasing energy groups (decreasing or increasing energies). Defaults to 'increasing'. + row_column: {'inout', 'outin'} + Return the cross section indexed first by incoming group and second + by outgoing group ('inout'), or vice versa ('outin'). value : str A string for the type of value to return - 'mean', 'std_dev', or 'rel_err' are accepted. Defaults to the empty string. @@ -2092,6 +2100,10 @@ class ScatterMatrixXS(MGXS): new_shape += xs.shape[1:] xs = np.reshape(xs, new_shape) + # Transpose the scattering matrix if requested by user + if row_column == 'outin': + xs = np.swapaxes(xs, 1, 2) + # Reverse energies to align with increasing energy groups xs = xs[:, ::-1, ::-1, :] @@ -2422,7 +2434,8 @@ class Chi(MGXS): return merged_mgxs def get_xs(self, groups='all', subdomains='all', nuclides='all', - xs_type='macro', order_groups='increasing', value='mean'): + xs_type='macro', order_groups='increasing', + value='mean', **kwargs): """Returns an array of the fission spectrum. This method constructs a 2D NumPy array for the requested multi-group From d460e51fb772fe53121974c1daaa6996877298d0 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 29 Apr 2016 23:27:59 -0400 Subject: [PATCH 057/147] Moved Jupyter Notebook examples to top of Python API page --- docs/source/pythonapi/index.rst | 28 ++++++++++++++-------------- 1 file changed, 14 insertions(+), 14 deletions(-) diff --git a/docs/source/pythonapi/index.rst b/docs/source/pythonapi/index.rst index 3bedaf2c7..1631976e6 100644 --- a/docs/source/pythonapi/index.rst +++ b/docs/source/pythonapi/index.rst @@ -13,6 +13,20 @@ online. We recommend going through the modules from Codecademy_ and/or the `Scipy lectures`_. The full API documentation serves to provide more information on a given module or class. +------------------------- +Example Jupyter Notebooks +------------------------- + +.. toctree:: + :maxdepth: 1 + + examples/post-processing + examples/pandas-dataframes + examples/tally-arithmetic + examples/mgxs-part-i + examples/mgxs-part-ii + examples/mgxs-part-iii + ------------------------------------ :mod:`openmc` -- Basic Functionality ------------------------------------ @@ -271,20 +285,6 @@ Multi-group Cross Section Libraries openmc.mgxs.Library -------------------------- -Example Jupyter Notebooks -------------------------- - -.. toctree:: - :maxdepth: 1 - - examples/post-processing - examples/pandas-dataframes - examples/tally-arithmetic - examples/mgxs-part-i - examples/mgxs-part-ii - examples/mgxs-part-iii - .. _Jupyter: https://jupyter.org/ .. _NumPy: http://www.numpy.org/ .. _Codecademy: https://www.codecademy.com/tracks/python From 6fc37fb99cf277dfe364559edf642a78f90762b4 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 29 Apr 2016 23:31:12 -0400 Subject: [PATCH 058/147] Added a link to Read the Docs to homepage --- docs/source/index.rst | 3 ++- 1 file changed, 2 insertions(+), 1 deletion(-) diff --git a/docs/source/index.rst b/docs/source/index.rst index 54ba825e5..7edc560e2 100644 --- a/docs/source/index.rst +++ b/docs/source/index.rst @@ -13,11 +13,12 @@ OpenMC was originally developed by members of the `Computational Reactor Physics Group`_ at the `Massachusetts Institute of Technology`_ starting in 2011. Various universities, laboratories, and other organizations now contribute to the development of OpenMC. For more information on OpenMC, feel -free to send a message to the User's Group `mailing list`_. +free to send a message to the User's Group `mailing list`_. Documentation for the latest version of the develop branch can be found on `Read the Docs`_. .. _Computational Reactor Physics Group: http://crpg.mit.edu .. _Massachusetts Institute of Technology: http://web.mit.edu .. _mailing list: https://groups.google.com/forum/?fromgroups=#!forum/openmc-users +.. _Read the Docs: http://openmc.readthedocs.io/en/latest/ .. only:: html From 6a2743f1e12fbc0745ff770f22df8847af859e90 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Sat, 30 Apr 2016 06:37:02 -0500 Subject: [PATCH 059/147] Fix comma in tally arithmetic notebook --- .../pythonapi/examples/tally-arithmetic.ipynb | 66 ++++++++----------- 1 file changed, 28 insertions(+), 38 deletions(-) diff --git a/docs/source/pythonapi/examples/tally-arithmetic.ipynb b/docs/source/pythonapi/examples/tally-arithmetic.ipynb index 14ca97d3f..25c57f3c5 100644 --- a/docs/source/pythonapi/examples/tally-arithmetic.ipynb +++ b/docs/source/pythonapi/examples/tally-arithmetic.ipynb @@ -15,16 +15,7 @@ "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "The autoreload extension is already loaded. To reload it, use:\n", - " %reload_ext autoreload\n" - ] - } - ], + "outputs": [], "source": [ "%load_ext autoreload\n", "%autoreload 2" @@ -362,7 +353,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -449,7 +440,7 @@ "abs_rate = openmc.Tally(name='abs. rate')\n", "fiss_rate.scores = ['nu-fission']\n", "abs_rate.scores = ['absorption']\n", - "tallies_file += (fiss_rate, abs_rate)", + "tallies_file += (fiss_rate, abs_rate)" ] }, { @@ -562,12 +553,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:39:14\n", - " MPI Processes: 1\n", + " Git SHA1: ae083cf5d491e6a778d5b762dad19c8d5fe45238\n", + " Date/Time: 2016-04-30 06:37:41\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -623,20 +613,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.0300E-01 seconds\n", - " Reading cross sections = 8.6000E-02 seconds\n", - " Total time in simulation = 1.4439E+01 seconds\n", - " Time in transport only = 1.4430E+01 seconds\n", - " Time in inactive batches = 2.2790E+00 seconds\n", - " Time in active batches = 1.2160E+01 seconds\n", - " Time synchronizing fission bank = 2.0000E-03 seconds\n", + " Total time for initialization = 7.0900E-01 seconds\n", + " Reading cross sections = 4.0400E-01 seconds\n", + " Total time in simulation = 1.7108E+01 seconds\n", + " Time in transport only = 1.7093E+01 seconds\n", + " Time in inactive batches = 3.3970E+00 seconds\n", + " Time in active batches = 1.3711E+01 seconds\n", + " Time synchronizing fission bank = 1.0000E-03 seconds\n", " Sampling source sites = 1.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 1.0000E-03 seconds\n", - " Total time elapsed = 1.4856E+01 seconds\n", - " Calculation Rate (inactive) = 5484.86 neutrons/second\n", - " Calculation Rate (active) = 3083.88 neutrons/second\n", + " Total time elapsed = 1.7835E+01 seconds\n", + " Calculation Rate (inactive) = 3679.72 neutrons/second\n", + " Calculation Rate (active) = 2735.03 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -810,7 +800,7 @@ " \n", " \n", " 0\n", - " 0\n", + " 0.0\n", " 6.250000e-07\n", " total\n", " absorption\n", @@ -872,7 +862,7 @@ " \n", " \n", " 0\n", - " 0\n", + " 0.0\n", " 6.250000e-07\n", " total\n", " nu-fission\n", @@ -936,7 +926,7 @@ " \n", " \n", " 0\n", - " 0\n", + " 0.0\n", " 6.250000e-07\n", " 10000\n", " total\n", @@ -1002,7 +992,7 @@ " \n", " \n", " 0\n", - " 0\n", + " 0.0\n", " 6.250000e-07\n", " 10000\n", " total\n", @@ -1067,7 +1057,7 @@ " \n", " \n", " 0\n", - " 0\n", + " 0.0\n", " 6.250000e-07\n", " 10000\n", " total\n", @@ -1610,21 +1600,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, From 7741b525bb5457ba03dd4dde101e06c0c2daf766 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 30 Apr 2016 09:35:17 -0400 Subject: [PATCH 060/147] Removed OpenCG dependency for distribcell paths in Pandas DataFrames --- .../examples/pandas-dataframes.ipynb | 484 ++++-------------- openmc/filter.py | 189 ++++--- openmc/tallies.py | 19 +- 3 files changed, 208 insertions(+), 484 deletions(-) diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index b0f2f6b13..c9e73caac 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -374,7 +374,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -538,134 +538,13 @@ "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "\n", - " .d88888b. 888b d888 .d8888b.\n", - " d88P\" \"Y88b 8888b d8888 d88P Y88b\n", - " 888 888 88888b.d88888 888 888\n", - " 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n", - " 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n", - " 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n", - " Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n", - " \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n", - "__________________888______________________________________________________\n", - " 888\n", - " 888\n", - "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", - " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:40:02\n", - " MPI Processes: 1\n", - "\n", - " ===========================================================================\n", - " ========================> INITIALIZATION <=========================\n", - " ===========================================================================\n", - "\n", - " Reading settings XML file...\n", - " Reading cross sections XML file...\n", - " Reading geometry XML file...\n", - " Reading materials XML file...\n", - " Reading tallies XML file...\n", - " Building neighboring cells lists for each surface...\n", - " Loading ACE cross section table: 92235.71c\n", - " Loading ACE cross section table: 92238.71c\n", - " Loading ACE cross section table: 8016.71c\n", - " Loading ACE cross section table: 1001.71c\n", - " Loading ACE cross section table: 5010.71c\n", - " Loading ACE cross section table: 40090.71c\n", - " Maximum neutron transport energy: 20.0000 MeV for 92235.71c\n", - " Initializing source particles...\n", - "\n", - " ===========================================================================\n", - " ====================> K EIGENVALUE SIMULATION <====================\n", - " ===========================================================================\n", - "\n", - " Bat./Gen. k Average k \n", - " ========= ======== ==================== \n", - " 1/1 0.55921 \n", - " 2/1 0.63816 \n", - " 3/1 0.68834 \n", - " 4/1 0.71192 \n", - " 5/1 0.67935 \n", - " 6/1 0.68274 \n", - " 7/1 0.66339 0.67307 +/- 0.00967\n", - " 8/1 0.65835 0.66816 +/- 0.00743\n", - " 9/1 0.66697 0.66786 +/- 0.00527\n", - " 10/1 0.70498 0.67528 +/- 0.00847\n", - " 11/1 0.68596 0.67706 +/- 0.00714\n", - " 12/1 0.68481 0.67817 +/- 0.00614\n", - " 13/1 0.68369 0.67886 +/- 0.00536\n", - " 14/1 0.68785 0.67986 +/- 0.00483\n", - " 15/1 0.66145 0.67802 +/- 0.00470\n", - " 16/1 0.71831 0.68168 +/- 0.00561\n", - " 17/1 0.68428 0.68190 +/- 0.00512\n", - " 18/1 0.67527 0.68139 +/- 0.00474\n", - " 19/1 0.68166 0.68141 +/- 0.00439\n", - " 20/1 0.65475 0.67963 +/- 0.00446\n", - " Triggers unsatisfied, max unc./thresh. is 1.07581 for absorption in tally 10002\n", - " The estimated number of batches is 23\n", - " Creating state point statepoint.020.h5...\n", - " 21/1 0.64538 0.67749 +/- 0.00469\n", - " 22/1 0.73275 0.68074 +/- 0.00547\n", - " 23/1 0.71674 0.68274 +/- 0.00553\n", - " Triggers satisfied for batch 23\n", - " Creating state point statepoint.023.h5...\n", - "\n", - " ===========================================================================\n", - " ======================> SIMULATION FINISHED <======================\n", - " ===========================================================================\n", - "\n", - "\n", - " =======================> TIMING STATISTICS <=======================\n", - "\n", - " Total time for initialization = 3.7900E-01 seconds\n", - " Reading cross sections = 8.6000E-02 seconds\n", - " Total time in simulation = 8.7310E+00 seconds\n", - " Time in transport only = 8.7200E+00 seconds\n", - " Time in inactive batches = 1.3230E+00 seconds\n", - " Time in active batches = 7.4080E+00 seconds\n", - " Time synchronizing fission bank = 2.0000E-03 seconds\n", - " Sampling source sites = 1.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 9.1240E+00 seconds\n", - " Calculation Rate (inactive) = 9448.22 neutrons/second\n", - " Calculation Rate (active) = 5062.10 neutrons/second\n", - "\n", - " ============================> RESULTS <============================\n", - "\n", - " k-effective (Collision) = 0.67952 +/- 0.00434\n", - " k-effective (Track-length) = 0.68274 +/- 0.00553\n", - " k-effective (Absorption) = 0.68095 +/- 0.00369\n", - " Combined k-effective = 0.67994 +/- 0.00349\n", - " Leakage Fraction = 0.34133 +/- 0.00332\n", - "\n" - ] - }, - { - "data": { - "text/plain": [ - "0" - ] - }, - "execution_count": 20, - "metadata": {}, - "output_type": "execute_result" - } - ], + "outputs": [], "source": [ "# Remove old HDF5 (summary, statepoint) files\n", - "!rm statepoint.*\n", + "#!rm statepoint.*\n", "\n", "# Run OpenMC!\n", - "openmc.run()" + "#openmc.run()()" ] }, { @@ -1114,9 +993,9 @@ "outputs": [ { "data": { - "image/png": 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J50fEc2PFt6sP9v2SHsm7EE5tUx3MrGrDtWIbICnqtrWjHG03sLDu+Vn5viJl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\n", "text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1734,7 +1613,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -1757,11 +1636,11 @@ " \n", " \n", " \n", - " cell\n", " univ\n", + " cell\n", " lat\n", - " cell\n", " univ\n", + " cell\n", " \n", " \n", " \n", @@ -1786,14 +1665,14 @@ " \n", " \n", " 558\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 9\n", + " 7\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 279\n", " absorption\n", " 8.19e-05\n", @@ -1801,14 +1680,14 @@ " \n", " \n", " 559\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 9\n", + " 7\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 279\n", " scatter\n", " 1.33e-02\n", @@ -1816,14 +1695,14 @@ " \n", " \n", " 560\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", " 8\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 280\n", " absorption\n", " 1.00e-04\n", @@ -1831,14 +1710,14 @@ " \n", " \n", " 561\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", " 8\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 280\n", " scatter\n", " 1.40e-02\n", @@ -1846,14 +1725,14 @@ " \n", " \n", " 562\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 7\n", + " 9\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 281\n", " absorption\n", " 9.52e-05\n", @@ -1861,14 +1740,14 @@ " \n", " \n", " 563\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 7\n", + " 9\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 281\n", " scatter\n", " 1.51e-02\n", @@ -1876,14 +1755,14 @@ " \n", " \n", " 564\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 6\n", + " 10\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 282\n", " absorption\n", " 9.85e-05\n", @@ -1891,14 +1770,14 @@ " \n", " \n", " 565\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 6\n", + " 10\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 282\n", " scatter\n", " 1.53e-02\n", @@ -1906,14 +1785,14 @@ " \n", " \n", " 566\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 5\n", + " 11\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 283\n", " absorption\n", " 1.08e-04\n", @@ -1921,14 +1800,14 @@ " \n", " \n", " 567\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 5\n", + " 11\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 283\n", " scatter\n", " 1.65e-02\n", @@ -1936,14 +1815,14 @@ " \n", " \n", " 568\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 4\n", + " 12\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 284\n", " absorption\n", " 1.13e-04\n", @@ -1951,14 +1830,14 @@ " \n", " \n", " 569\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 4\n", + " 12\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 284\n", " scatter\n", " 1.67e-02\n", @@ -1966,14 +1845,14 @@ " \n", " \n", " 570\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 3\n", + " 13\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 285\n", " absorption\n", " 1.23e-04\n", @@ -1981,14 +1860,14 @@ " \n", " \n", " 571\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 3\n", + " 13\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 285\n", " scatter\n", " 1.88e-02\n", @@ -1996,14 +1875,14 @@ " \n", " \n", " 572\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 2\n", + " 14\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 286\n", " absorption\n", " 1.44e-04\n", @@ -2011,14 +1890,14 @@ " \n", " \n", " 573\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 2\n", + " 14\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 286\n", " scatter\n", " 1.90e-02\n", @@ -2026,14 +1905,14 @@ " \n", " \n", " 574\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 1\n", + " 15\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 287\n", " absorption\n", " 1.26e-04\n", @@ -2041,14 +1920,14 @@ " \n", " \n", " 575\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", - " 1\n", + " 15\n", " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 287\n", " scatter\n", " 1.97e-02\n", @@ -2056,14 +1935,14 @@ " \n", " \n", " 576\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", + " 16\n", " 0\n", - " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 288\n", " absorption\n", " 1.25e-04\n", @@ -2071,14 +1950,14 @@ " \n", " \n", " 577\n", - " 10003\n", " 0\n", + " 10003\n", " 10001\n", " 16\n", + " 16\n", " 0\n", - " 0\n", - " 10002\n", " 10000\n", + " 10002\n", " 288\n", " scatter\n", " 2.01e-02\n", @@ -2089,29 +1968,29 @@ "" ], "text/plain": [ - " level 1 level 2 level 3 distribcell score \\\n", - " cell univ lat cell univ \n", - " id id id x y z id id \n", - "558 10003 0 10001 16 9 0 10002 10000 279 absorption \n", - "559 10003 0 10001 16 9 0 10002 10000 279 scatter \n", - "560 10003 0 10001 16 8 0 10002 10000 280 absorption \n", - "561 10003 0 10001 16 8 0 10002 10000 280 scatter \n", - "562 10003 0 10001 16 7 0 10002 10000 281 absorption \n", - "563 10003 0 10001 16 7 0 10002 10000 281 scatter \n", - "564 10003 0 10001 16 6 0 10002 10000 282 absorption \n", - "565 10003 0 10001 16 6 0 10002 10000 282 scatter \n", - "566 10003 0 10001 16 5 0 10002 10000 283 absorption \n", - "567 10003 0 10001 16 5 0 10002 10000 283 scatter \n", - "568 10003 0 10001 16 4 0 10002 10000 284 absorption \n", - "569 10003 0 10001 16 4 0 10002 10000 284 scatter \n", - "570 10003 0 10001 16 3 0 10002 10000 285 absorption \n", - "571 10003 0 10001 16 3 0 10002 10000 285 scatter \n", - "572 10003 0 10001 16 2 0 10002 10000 286 absorption \n", - "573 10003 0 10001 16 2 0 10002 10000 286 scatter \n", - "574 10003 0 10001 16 1 0 10002 10000 287 absorption \n", - "575 10003 0 10001 16 1 0 10002 10000 287 scatter \n", - "576 10003 0 10001 16 0 0 10002 10000 288 absorption \n", - "577 10003 0 10001 16 0 0 10002 10000 288 scatter \n", + " level 1 level 2 level 3 distribcell score \\\n", + " univ cell lat univ cell \n", + " id id id x y z id id \n", + "558 0 10003 10001 16 7 0 10000 10002 279 absorption \n", + "559 0 10003 10001 16 7 0 10000 10002 279 scatter \n", + "560 0 10003 10001 16 8 0 10000 10002 280 absorption \n", + "561 0 10003 10001 16 8 0 10000 10002 280 scatter \n", + "562 0 10003 10001 16 9 0 10000 10002 281 absorption \n", + "563 0 10003 10001 16 9 0 10000 10002 281 scatter \n", + "564 0 10003 10001 16 10 0 10000 10002 282 absorption \n", + "565 0 10003 10001 16 10 0 10000 10002 282 scatter \n", + "566 0 10003 10001 16 11 0 10000 10002 283 absorption \n", + "567 0 10003 10001 16 11 0 10000 10002 283 scatter \n", + "568 0 10003 10001 16 12 0 10000 10002 284 absorption \n", + "569 0 10003 10001 16 12 0 10000 10002 284 scatter \n", + "570 0 10003 10001 16 13 0 10000 10002 285 absorption \n", + "571 0 10003 10001 16 13 0 10000 10002 285 scatter \n", + "572 0 10003 10001 16 14 0 10000 10002 286 absorption \n", + "573 0 10003 10001 16 14 0 10000 10002 286 scatter \n", + "574 0 10003 10001 16 15 0 10000 10002 287 absorption \n", + "575 0 10003 10001 16 15 0 10000 10002 287 scatter \n", + "576 0 10003 10001 16 16 0 10000 10002 288 absorption \n", + "577 0 10003 10001 16 16 0 10000 10002 288 scatter \n", "\n", " mean std. dev. \n", " \n", @@ -2138,14 +2017,14 @@ "577 2.01e-02 6.75e-04 " ] }, - "execution_count": 34, + "execution_count": 35, "metadata": {}, "output_type": "execute_result" } ], "source": [ "# Get a pandas dataframe for the distribcell tally data\n", - "df = tally.get_pandas_dataframe(summary=su, nuclides=False)\n", + "df = tally.get_pandas_dataframe(nuclides=False, distribcell_paths=True)\n", "\n", "# Print the last twenty rows in the dataframe\n", "df.tail(20)" @@ -2153,97 +2032,11 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "data": { - "text/html": [ - "
\n", - "\n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - " \n", - "
meanstd. dev.
count2.89e+022.89e+02
mean4.19e-042.24e-05
std2.42e-049.14e-06
min1.90e-053.44e-06
25%2.02e-041.56e-05
50%4.05e-042.20e-05
75%6.07e-042.89e-05
max9.19e-044.95e-05
\n", - "
" - ], - "text/plain": [ - " mean std. dev.\n", - " \n", - " \n", - "count 2.89e+02 2.89e+02\n", - "mean 4.19e-04 2.24e-05\n", - "std 2.42e-04 9.14e-06\n", - "min 1.90e-05 3.44e-06\n", - "25% 2.02e-04 1.56e-05\n", - "50% 4.05e-04 2.20e-05\n", - "75% 6.07e-04 2.89e-05\n", - "max 9.19e-04 4.95e-05" - ] - }, - "execution_count": 35, - "metadata": {}, - "output_type": "execute_result" - } - ], + "outputs": [], "source": [ "# Show summary statistics for absorption distribcell tally data\n", "absorption = df[df['score'] == 'absorption']\n", @@ -2262,19 +2055,11 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "Mann-Whitney Test p-value: 0.303583331507\n" - ] - } - ], + "outputs": [], "source": [ "# Extract tally data from pins in the pins divided along y=-x diagonal\n", "multi_index = ('level 2', 'lat',)\n", @@ -2300,19 +2085,11 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "Mann-Whitney Test p-value: 6.038663783e-42\n" - ] - } - ], + "outputs": [], "source": [ "# Extract tally data from pins in the pins divided along y=x diagonal \n", "multi_index = ('level 2', 'lat',)\n", @@ -2336,43 +2113,11 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stderr", - "output_type": "stream", - "text": [ - "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:4: SettingWithCopyWarning: \n", - "A value is trying to be set on a copy of a slice from a DataFrame.\n", - "Try using .loc[row_indexer,col_indexer] = value instead\n", - "\n", - "See the caveats in the documentation: http://pandas.pydata.org/pandas-docs/stable/indexing.html#indexing-view-versus-copy\n" - ] - }, - { - "data": { - "text/plain": [ - "" - ] - }, - "execution_count": 38, - "metadata": {}, - "output_type": "execute_result" - }, - { - "data": { - "image/png": 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- "text/plain": [ - "" - ] - }, - "metadata": {}, - "output_type": "display_data" - } - ], + "outputs": [], "source": [ "# Extract the scatter tally data from pandas\n", "scatter = df[df['score'] == 'scatter']\n", @@ -2385,32 +2130,11 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "data": { - "text/plain": [ - "" - ] - }, - "execution_count": 39, - "metadata": {}, - "output_type": "execute_result" - }, - { - "data": { - "image/png": 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- "text/plain": [ - "" - ] - }, - "metadata": {}, - "output_type": "display_data" - } - ], + "outputs": [], "source": [ "# Plot a histogram and kernel density estimate for the scattering rates\n", "scatter['mean'].plot(kind='hist', bins=25)\n", diff --git a/openmc/filter.py b/openmc/filter.py index b0e59874b..840482e85 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -1,4 +1,4 @@ -from collections import Iterable +from collections import Iterable, OrderedDict import copy from numbers import Real, Integral import sys @@ -516,7 +516,7 @@ class Filter(object): return filter_bin - def get_pandas_dataframe(self, data_size, summary=None): + def get_pandas_dataframe(self, data_size, distribcell_paths=False): """Builds a Pandas DataFrame for the Filter's bins. This method constructs a Pandas DataFrame object for the filter with @@ -531,12 +531,10 @@ class Filter(object): ---------- data_size : Integral The total number of bins in the tally corresponding to this filter - summary : None or openmc.Summary - An optional Summary object to be used to construct columns for - distribcell tally filters (default is None). The geometric + distribcell_paths : bool + Construct columns for distribcell tally filters. The geometric information in the Summary object is embedded into a Multi-index column with a geometric "path" to each distribcell instance. - NOTE: This option requires the OpenCG Python package. Returns ------- @@ -554,7 +552,7 @@ class Filter(object): 1. a single column with the cell instance IDs (without summary info) 2. separate columns for the cell IDs, universe IDs, and lattice IDs - and x,y,z cell indices corresponding to each (with summary info). + and x,y,z cell indices corresponding to each (distribcell paths). For 'energy' and 'energyout' filters, the DataFrame includes one column for the lower energy bound and one column for the upper @@ -566,8 +564,7 @@ class Filter(object): Raises ------ ImportError - When Pandas is not installed, or summary info is requested but - OpenCG is not installed. + When Pandas is not installed See also -------- @@ -626,106 +623,108 @@ class Filter(object): elif self.type == 'distribcell': level_df = None - if isinstance(summary, Summary): - # Attempt to import the OpenCG package - try: - import opencg - except ImportError: - msg = 'The OpenCG package must be installed ' \ - 'to use a Summary for distribcell dataframes' - raise ImportError(msg) + # Create Pandas Multi-index columns for each level in CSG tree + if distribcell_paths: - # Extract the OpenCG geometry from the Summary - opencg_geometry = summary.opencg_geometry - openmc_geometry = summary.openmc_geometry + # FIXME: Make assumption that each path is the same length??? + # NOTE: Just state this caveat in the docstring - # Use OpenCG to compute the number of regions - opencg_geometry.initialize_cell_offsets() - num_regions = opencg_geometry.num_regions - - # Initialize a dictionary mapping OpenMC distribcell - # offsets to OpenCG LocalCoords linked lists - offsets_to_coords = {} - - for offset, path in enumerate(self.distribcell_paths): - region = opencg_geometry.get_region_from_path(path) - coords = opencg_geometry.find_region(region) - offsets_to_coords[offset] = coords - - # Each distribcell offset is a DataFrame bin - # Unravel the paths into DataFrame columns - num_offsets = len(offsets_to_coords) - - # Initialize termination condition for while loop + distribcell_paths = copy.deepcopy(self.distribcell_paths) + num_offsets = len(distribcell_paths) levels_remain = True - counter = 0 + level_counter = 0 - # Iterate over each level in the CSG tree hierarchy + # FIXME: Allocate NumPy arrays for each CSG level while levels_remain: - levels_remain = False + level_counter += 1 + level_key = 'level {}'.format(level_counter) + first_path = distribcell_paths[0] + level_dict = OrderedDict() - # Initialize dictionary to build Pandas Multi-index - # column for this level in the CSG tree hierarchy - level_dict = {} + next_index = first_path.index('-') + level = first_path[:next_index] + first_path = first_path[next_index+2:] - # Initialize prefix Multi-index keys - counter += 1 - level_key = 'level {0}'.format(counter) - univ_key = (level_key, 'univ', 'id') - cell_key = (level_key, 'cell', 'id') - lat_id_key = (level_key, 'lat', 'id') - lat_x_key = (level_key, 'lat', 'x') - lat_y_key = (level_key, 'lat', 'y') - lat_z_key = (level_key, 'lat', 'z') + # This level is a lattice (e.g., ID(x,y,z)) + if '(' in level: + level_type = 'lattice' - # Allocate NumPy arrays for each CSG level and - # each Multi-index column in the DataFrame - level_dict[univ_key] = np.empty(num_offsets) - level_dict[cell_key] = np.empty(num_offsets) - level_dict[lat_id_key] = np.empty(num_offsets) - level_dict[lat_x_key] = np.empty(num_offsets) - level_dict[lat_y_key] = np.empty(num_offsets) - level_dict[lat_z_key] = np.empty(num_offsets) + # Initialize prefix Multi-index keys + lat_id_key = (level_key, 'lat', 'id') + lat_x_key = (level_key, 'lat', 'x') + lat_y_key = (level_key, 'lat', 'y') + lat_z_key = (level_key, 'lat', 'z') - # Initialize Multi-index columns to NaN - this is - # necessary since some distribcell instances may - # have very different LocalCoords linked lists - level_dict[univ_key][:] = np.NAN - level_dict[cell_key][:] = np.NAN - level_dict[lat_id_key][:] = np.NAN - level_dict[lat_x_key][:] = np.NAN - level_dict[lat_y_key][:] = np.NAN - level_dict[lat_z_key][:] = np.NAN + # Allocate NumPy arrays for each CSG level and + # each Multi-index column in the DataFrame + level_dict[lat_id_key] = np.empty(num_offsets) + level_dict[lat_x_key] = np.empty(num_offsets) + level_dict[lat_y_key] = np.empty(num_offsets) + level_dict[lat_z_key] = np.empty(num_offsets) - # Iterate over all regions (distribcell instances) - for offset in range(num_offsets): - coords = offsets_to_coords[offset] + # This level is a universe / cell (e.g., ID->ID) + else: + level_type = 'universe' - # If entire LocalCoords has been unraveled into - # Multi-index columns already, continue - if coords is None: - continue - - # Assign entry to Universe Multi-index column - if coords._type == 'universe': - level_dict[univ_key][offset] = coords._universe._id - level_dict[cell_key][offset] = coords._cell._id - - # Assign entry to Lattice Multi-index column + # Pop off the cell ID from the path + if '-' in first_path: + next_index = first_path.index('-') + level = first_path[:next_index] + first_path = first_path[next_index+2:] else: - # Reverse y index per lattice ordering in OpenCG - level_dict[lat_id_key][offset] = coords._lattice._id - level_dict[lat_x_key][offset] = coords._lat_x - level_dict[lat_y_key][offset] = \ - coords._lattice.dimension[1] - coords._lat_y - 1 - level_dict[lat_z_key][offset] = coords._lat_z + levels_remain = False + + # Initialize prefix Multi-index keys + univ_key = (level_key, 'univ', 'id') + cell_key = (level_key, 'cell', 'id') + + # Allocate NumPy arrays for each CSG level and + # each Multi-index column in the DataFrame + level_dict[univ_key] = np.empty(num_offsets) + level_dict[cell_key] = np.empty(num_offsets) + + # Populate Multi-index arrays with all distribcell paths + for i, path in enumerate(distribcell_paths): + + if level_type == 'lattice': + # Extract lattice ID, indices from path + next_index = path.index('-') + lat_id_indices = path[:next_index] + + # Trim lattice info from distribcell path + distribcell_paths[i] = path[next_index+2:] + + # Extract the lattice cell indices from the path + i1 = lat_id_indices.index('(') + i2 = lat_id_indices.index(')') + i3 = lat_id_indices[i1+1:i2] + + # Assign entry to Lattice Multi-index column + level_dict[lat_id_key][i] = path[:i1] + level_dict[lat_x_key][i] = int(i3.split(',')[0]) - 1 + level_dict[lat_y_key][i] = int(i3.split(',')[1]) - 1 + level_dict[lat_z_key][i] = int(i3.split(',')[2]) - 1 - # Move to next node in LocalCoords linked list - if coords._next is None: - offsets_to_coords[offset] = None else: - offsets_to_coords[offset] = coords._next - levels_remain = True + # Extract universe ID from path + next_index = path.index('-') + universe_id = int(path[:next_index]) + + # Trim universe info from distribcell path + path = path[next_index+2:] + + # Extract cell ID from path + if '-' in path: + next_index = path.index('-') + cell_id = int(path[:next_index]) + distribcell_paths[i] = path[next_index+2:] + else: + cell_id = int(path) + distribcell_paths[i] = '' + + # Assign entry to Universe, Cell Multi-index columns + level_dict[univ_key][i] = universe_id + level_dict[cell_key][i] = cell_id # Tile the Multi-index columns for level_key, level_bins in level_dict.items(): diff --git a/openmc/tallies.py b/openmc/tallies.py index 90b09f582..6bd55b20f 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -1538,8 +1538,8 @@ class Tally(object): return data - def get_pandas_dataframe(self, filters=True, nuclides=True, - scores=True, summary=None, float_format='{:.2e}'): + def get_pandas_dataframe(self, filters=True, nuclides=True, scores=True, + distribcell_paths=False, float_format='{:.2e}'): """Build a Pandas DataFrame for the Tally data. This method constructs a Pandas DataFrame object for the Tally data @@ -1557,12 +1557,10 @@ class Tally(object): Include columns with nuclide bin information (default is True). scores : bool Include columns with score bin information (default is True). - summary : None or openmc.Summary - An optional Summary object to be used to construct columns for - distribcell tally filters (default is None). The geometric + distribcell_paths : bool + Construct columns for distribcell tally filters. The geometric information in the Summary object is embedded into a Multi-index - column with a geometric "path" to each distribcell intance. - NOTE: This option requires the OpenCG Python package. + column with a geometric "path" to each distribcell instance. float_format : str All floats in the DataFrame will be formatted using the given format string before printing. @@ -1588,13 +1586,15 @@ class Tally(object): msg = 'The Tally ID="{0}" has no data to return'.format(self.id) raise KeyError(msg) + ''' # If using Summary, ensure StatePoint.link_with_summary(...) was called - if summary and not self.with_summary: + if distribcell_pathssummary and not self.with_summary: msg = 'The Tally ID="{0}" has not been linked with the Summary. ' \ 'Call the StatePoint.link_with_summary(...) method ' \ 'before using Tally.get_pandas_dataframe(...) with ' \ 'Summary info'.format(self.id) raise KeyError(msg) + ''' # Initialize a pandas dataframe for the tally data import pandas as pd @@ -1608,7 +1608,8 @@ class Tally(object): # Append each Filter's DataFrame to the overall DataFrame for self_filter in self.filters: - filter_df = self_filter.get_pandas_dataframe(data_size, summary) + filter_df = self_filter.get_pandas_dataframe( + data_size, distribcell_paths) df = pd.concat([df, filter_df], axis=1) # Include DataFrame column for nuclides if user requested it From 615cec9e96f11e4dc45f7d271cfc809970aba425 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 30 Apr 2016 09:45:40 -0400 Subject: [PATCH 061/147] Improved comments for Pandas DataFrames distribcell path construction --- .../examples/pandas-dataframes.ipynb | 319 ++++++++++++++++-- openmc/filter.py | 40 ++- 2 files changed, 321 insertions(+), 38 deletions(-) diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index c9e73caac..57b4b06fb 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -374,7 +374,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -538,13 +538,135 @@ "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "\n", + " .d88888b. 888b d888 .d8888b.\n", + " d88P\" \"Y88b 8888b d8888 d88P Y88b\n", + " 888 888 88888b.d88888 888 888\n", + " 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n", + " 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n", + " 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n", + " Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n", + " \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n", + "__________________888______________________________________________________\n", + " 888\n", + " 888\n", + "\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " Version: 0.7.1\n", + " Git SHA1: 5863cc5c9906ae7b2ec15efbf793b22b9c7f7dcb\n", + " Date/Time: 2016-04-30 09:44:46\n", + " MPI Processes: 1\n", + " OpenMP Threads: 4\n", + "\n", + " ===========================================================================\n", + " ========================> INITIALIZATION <=========================\n", + " ===========================================================================\n", + "\n", + " Reading settings XML file...\n", + " Reading cross sections XML file...\n", + " Reading geometry XML file...\n", + " Reading materials XML file...\n", + " Reading tallies XML file...\n", + " Building neighboring cells lists for each surface...\n", + " Loading ACE cross section table: 92235.71c\n", + " Loading ACE cross section table: 92238.71c\n", + " Loading ACE cross section table: 8016.71c\n", + " Loading ACE cross section table: 1001.71c\n", + " Loading ACE cross section table: 5010.71c\n", + " Loading ACE cross section table: 40090.71c\n", + " Maximum neutron transport energy: 20.0000 MeV for 92235.71c\n", + " Initializing source particles...\n", + "\n", + " ===========================================================================\n", + " ====================> K EIGENVALUE SIMULATION <====================\n", + " ===========================================================================\n", + "\n", + " Bat./Gen. k Average k \n", + " ========= ======== ==================== \n", + " 1/1 0.55921 \n", + " 2/1 0.63816 \n", + " 3/1 0.68834 \n", + " 4/1 0.71192 \n", + " 5/1 0.67935 \n", + " 6/1 0.68274 \n", + " 7/1 0.66339 0.67307 +/- 0.00967\n", + " 8/1 0.65835 0.66816 +/- 0.00743\n", + " 9/1 0.66697 0.66786 +/- 0.00527\n", + " 10/1 0.70498 0.67528 +/- 0.00847\n", + " 11/1 0.68596 0.67706 +/- 0.00714\n", + " 12/1 0.68481 0.67817 +/- 0.00614\n", + " 13/1 0.68369 0.67886 +/- 0.00536\n", + " 14/1 0.68785 0.67986 +/- 0.00483\n", + " 15/1 0.66145 0.67802 +/- 0.00470\n", + " 16/1 0.71831 0.68168 +/- 0.00561\n", + " 17/1 0.68428 0.68190 +/- 0.00512\n", + " 18/1 0.67527 0.68139 +/- 0.00474\n", + " 19/1 0.68166 0.68141 +/- 0.00439\n", + " 20/1 0.65475 0.67963 +/- 0.00446\n", + " Triggers unsatisfied, max unc./thresh. is 1.07581 for absorption in tally 10002\n", + " The estimated number of batches is 23\n", + " Creating state point statepoint.020.h5...\n", + " 21/1 0.64538 0.67749 +/- 0.00469\n", + " 22/1 0.73275 0.68074 +/- 0.00547\n", + " 23/1 0.71674 0.68274 +/- 0.00553\n", + " Triggers satisfied for batch 23\n", + " Creating state point statepoint.023.h5...\n", + "\n", + " ===========================================================================\n", + " ======================> SIMULATION FINISHED <======================\n", + " ===========================================================================\n", + "\n", + "\n", + " =======================> TIMING STATISTICS <=======================\n", + "\n", + " Total time for initialization = 4.1400E-01 seconds\n", + " Reading cross sections = 9.3000E-02 seconds\n", + " Total time in simulation = 4.6240E+00 seconds\n", + " Time in transport only = 4.5580E+00 seconds\n", + " Time in inactive batches = 6.9200E-01 seconds\n", + " Time in active batches = 3.9320E+00 seconds\n", + " Time synchronizing fission bank = 2.0000E-03 seconds\n", + " Sampling source sites = 1.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for finalization = 0.0000E+00 seconds\n", + " Total time elapsed = 5.0530E+00 seconds\n", + " Calculation Rate (inactive) = 18063.6 neutrons/second\n", + " Calculation Rate (active) = 9537.13 neutrons/second\n", + "\n", + " ============================> RESULTS <============================\n", + "\n", + " k-effective (Collision) = 0.67952 +/- 0.00434\n", + " k-effective (Track-length) = 0.68274 +/- 0.00553\n", + " k-effective (Absorption) = 0.68095 +/- 0.00369\n", + " Combined k-effective = 0.67994 +/- 0.00349\n", + " Leakage Fraction = 0.34133 +/- 0.00332\n", + "\n" + ] + }, + { + "data": { + "text/plain": [ + "0" + ] + }, + "execution_count": 20, + "metadata": {}, + "output_type": "execute_result" + } + ], "source": [ "# Remove old HDF5 (summary, statepoint) files\n", - "#!rm statepoint.*\n", + "!rm statepoint.*\n", "\n", "# Run OpenMC!\n", - "#openmc.run()()" + "openmc.run()" ] }, { @@ -995,7 +1117,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1398,7 +1520,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Print the distribcell tally dataframe **without** OpenCG info" + "Print the distribcell tally dataframe **without** distribcell paths" ] }, { @@ -1608,12 +1730,12 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Print the distribcell tally dataframe **with** OpenCG info" + "Print the distribcell tally dataframe **with** distribcell paths" ] }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { "collapsed": false }, @@ -2017,7 +2139,7 @@ "577 2.01e-02 6.75e-04 " ] }, - "execution_count": 35, + "execution_count": 34, "metadata": {}, "output_type": "execute_result" } @@ -2032,11 +2154,97 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 35, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "data": { + "text/html": [ + "
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meanstd. dev.
count2.89e+022.89e+02
mean4.19e-042.24e-05
std2.42e-049.14e-06
min1.90e-053.44e-06
25%2.02e-041.56e-05
50%4.05e-042.20e-05
75%6.07e-042.89e-05
max9.19e-044.95e-05
\n", + "
" + ], + "text/plain": [ + " mean std. dev.\n", + " \n", + " \n", + "count 2.89e+02 2.89e+02\n", + "mean 4.19e-04 2.24e-05\n", + "std 2.42e-04 9.14e-06\n", + "min 1.90e-05 3.44e-06\n", + "25% 2.02e-04 1.56e-05\n", + "50% 4.05e-04 2.20e-05\n", + "75% 6.07e-04 2.89e-05\n", + "max 9.19e-04 4.95e-05" + ] + }, + "execution_count": 35, + "metadata": {}, + "output_type": "execute_result" + } + ], "source": [ "# Show summary statistics for absorption distribcell tally data\n", "absorption = df[df['score'] == 'absorption']\n", @@ -2055,11 +2263,19 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 36, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "Mann-Whitney Test p-value: 6.038663783e-42\n" + ] + } + ], "source": [ "# Extract tally data from pins in the pins divided along y=-x diagonal\n", "multi_index = ('level 2', 'lat',)\n", @@ -2085,11 +2301,19 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 37, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "Mann-Whitney Test p-value: 0.303583331507\n" + ] + } + ], "source": [ "# Extract tally data from pins in the pins divided along y=x diagonal \n", "multi_index = ('level 2', 'lat',)\n", @@ -2113,11 +2337,43 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 38, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stderr", + "output_type": "stream", + "text": [ + "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:4: SettingWithCopyWarning: \n", + "A value is trying to be set on a copy of a slice from a DataFrame.\n", + "Try using .loc[row_indexer,col_indexer] = value instead\n", + "\n", + "See the caveats in the documentation: http://pandas.pydata.org/pandas-docs/stable/indexing.html#indexing-view-versus-copy\n" + ] + }, + { + "data": { + "text/plain": [ + "" + ] + }, + "execution_count": 38, + "metadata": {}, + "output_type": "execute_result" + }, + { + "data": { + "image/png": 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+ "text/plain": [ + "" + ] + }, + "metadata": {}, + "output_type": "display_data" + } + ], "source": [ "# Extract the scatter tally data from pandas\n", "scatter = df[df['score'] == 'scatter']\n", @@ -2130,11 +2386,32 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 39, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "data": { + "text/plain": [ + "" + ] + }, + "execution_count": 39, + "metadata": {}, + "output_type": "execute_result" + }, + { + "data": { + "image/png": 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+ "text/plain": [ + "" + ] + }, + "metadata": {}, + "output_type": "display_data" + } + ], "source": [ "# Plot a histogram and kernel density estimate for the scattering rates\n", "scatter['mean'].plot(kind='hist', bins=25)\n", diff --git a/openmc/filter.py b/openmc/filter.py index 840482e85..ff21f4e93 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -535,6 +535,9 @@ class Filter(object): Construct columns for distribcell tally filters. The geometric information in the Summary object is embedded into a Multi-index column with a geometric "path" to each distribcell instance. + NOTE: This option assumes that all distribcell paths are of the same + length and do not have the same universes and cells but different + lattice cell indices. Returns ------- @@ -626,25 +629,32 @@ class Filter(object): # Create Pandas Multi-index columns for each level in CSG tree if distribcell_paths: - # FIXME: Make assumption that each path is the same length??? - # NOTE: Just state this caveat in the docstring - + # Make copy of array of distribcell paths to use in + # Pandas Multi-index column construction distribcell_paths = copy.deepcopy(self.distribcell_paths) num_offsets = len(distribcell_paths) - levels_remain = True - level_counter = 0 - # FIXME: Allocate NumPy arrays for each CSG level + # Loop over CSG levels in the distribcell paths + level_counter = 0 + levels_remain = True while levels_remain: + + # Use level key as first index in Pandas Multi-index column level_counter += 1 level_key = 'level {}'.format(level_counter) - first_path = distribcell_paths[0] - level_dict = OrderedDict() + # Use the first distribcell path to determine if level + # is a universe/cell or lattice level + first_path = distribcell_paths[0] next_index = first_path.index('-') level = first_path[:next_index] + + # Trim universe/lattice info from path first_path = first_path[next_index+2:] + # Create a dictionary for this level for Pandas Multi-index + level_dict = OrderedDict() + # This level is a lattice (e.g., ID(x,y,z)) if '(' in level: level_type = 'lattice' @@ -666,14 +676,6 @@ class Filter(object): else: level_type = 'universe' - # Pop off the cell ID from the path - if '-' in first_path: - next_index = first_path.index('-') - level = first_path[:next_index] - first_path = first_path[next_index+2:] - else: - levels_remain = False - # Initialize prefix Multi-index keys univ_key = (level_key, 'univ', 'id') cell_key = (level_key, 'cell', 'id') @@ -683,6 +685,10 @@ class Filter(object): level_dict[univ_key] = np.empty(num_offsets) level_dict[cell_key] = np.empty(num_offsets) + # Determine any levels remain in path + if '-' not in first_path: + levels_remain = False + # Populate Multi-index arrays with all distribcell paths for i, path in enumerate(distribcell_paths): @@ -739,7 +745,7 @@ class Filter(object): else: level_df = pd.concat([level_df, pd.DataFrame(level_dict)], axis=1) - # Create DataFrame column for distribcell instances IDs + # Create DataFrame column for distribcell instance IDs # NOTE: This is performed regardless of whether the user # requests Summary geometric information filter_bins = np.arange(self.num_bins) From 5e6de55a47955167e5c5cc2b50d58f2d112b3a82 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 30 Apr 2016 14:00:24 -0400 Subject: [PATCH 062/147] Updated MGXS.get_pandas_dataframe(...) method to use distribcell_paths parameter --- openmc/mgxs/mgxs.py | 37 +++++++++++++++++-------------------- 1 file changed, 17 insertions(+), 20 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 33255de30..d7ba0117d 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1346,7 +1346,7 @@ class MGXS(object): modified.write('\n\\end{document}') def get_pandas_dataframe(self, groups='all', nuclides='all', - xs_type='macro', summary=None): + xs_type='macro', distribcell_paths=False): """Build a Pandas DataFrame for the MGXS data. This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but @@ -1366,12 +1366,9 @@ class MGXS(object): xs_type: {'macro', 'micro'} Return macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - summary : None or openmc.Summary - An optional Summary object to be used to construct columns for - distribcell tally filters (default is None). The geometric - information in the Summary object is embedded into a multi-index - column with a geometric "path" to each distribcell intance. - NOTE: This option requires the OpenCG Python package. + distribcell_paths : list of str + The paths traversed through the CSG tree to reach each distribcell + instance (for 'distribcell' filters only) Returns ------- @@ -1398,7 +1395,8 @@ class MGXS(object): # Use tally summation to sum across all nuclides query_nuclides = self.get_all_nuclides() xs_tally = self.xs_tally.summation(nuclides=query_nuclides) - df = xs_tally.get_pandas_dataframe(summary=summary) + df = xs_tally.get_pandas_dataframe( + distribcell_paths=distribcell_paths) # Remove nuclide column since it is homogeneous and redundant df.drop('nuclide', axis=1, inplace=True) @@ -1406,14 +1404,16 @@ class MGXS(object): # If the user requested a specific set of nuclides elif self.by_nuclide and nuclides != 'all': xs_tally = self.xs_tally.get_slice(nuclides=nuclides) - df = xs_tally.get_pandas_dataframe(summary=summary) + df = xs_tally.get_pandas_dataframe( + distribcell_paths=distribcell_paths) # If the user requested all nuclides, keep nuclide column in dataframe else: - df = self.xs_tally.get_pandas_dataframe(summary=summary) + df = self.xs_tally.get_pandas_dataframe( + distribcell_paths=distribcell_paths) # Remove the score column since it is homogeneous and redundant - if summary and 'distribcell' in self.domain_type: + if distribcell_paths and 'distribcell' in self.domain_type: df = df.drop('score', level=0, axis=1) else: df = df.drop('score', axis=1) @@ -2557,7 +2557,7 @@ class Chi(MGXS): return xs def get_pandas_dataframe(self, groups='all', nuclides='all', - xs_type='macro', summary=None): + xs_type='macro', distribcell_paths=False): """Build a Pandas DataFrame for the MGXS data. This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but @@ -2577,12 +2577,9 @@ class Chi(MGXS): xs_type: {'macro', 'micro'} Return macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - summary : None or openmc.Summary - An optional Summary object to be used to construct columns for - distribcell tally filters (default is None). The geometric - information in the Summary object is embedded into a multi-index - column with a geometric "path" to each distribcell intance. - NOTE: This option requires the OpenCG Python package. + distribcell_paths : list of str + The paths traversed through the CSG tree to reach each distribcell + instance (for 'distribcell' filters only) Returns ------- @@ -2598,8 +2595,8 @@ class Chi(MGXS): """ # Build the dataframe using the parent class method - df = super(Chi, self).get_pandas_dataframe(groups, nuclides, - xs_type, summary) + df = super(Chi, self).get_pandas_dataframe( + groups, nuclides, xs_type, distribcell_paths=distribcell_paths) # If user requested micro cross sections, multiply by the atom # densities to cancel out division made by the parent class method From d2018de8ec151e4f2239a402f0773bd5a0cd4d97 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 30 Apr 2016 16:08:47 -0400 Subject: [PATCH 063/147] Added ability to set data of the multi-group xs library (openmc.mgxs_library) with MGXS class objects. These are accessible via set_* where * can include total, absorption... . These routines can either take numpy arrays as the former and current setters do, or the appropriate MGXS objects. Also made some changes to meet PEP8 - GUESS WHO HAS A LINTER!!! and finally fixed a documentation issue in settings.py where CROSS_SECTIONS was still referenced instead of OPENMC_CROSS_SECTIONS. --- openmc/mgxs_library.py | 593 ++++++++++++++++++++++++++++++++++++++--- openmc/settings.py | 7 +- 2 files changed, 555 insertions(+), 45 deletions(-) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index d3e49b238..b41a2030c 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -1,19 +1,19 @@ from collections import Iterable from numbers import Real, Integral from xml.etree import ElementTree as ET -import warnings import sys -if sys.version_info[0] >= 3: - basestring = str import numpy as np import openmc -from openmc.mgxs import EnergyGroups +import openmc.mgxs from openmc.checkvalue import check_type, check_value, check_greater_than, \ - check_iterable_type + check_iterable_type from openmc.clean_xml import * +if sys.version_info[0] >= 3: + basestring = str + # Supported incoming particle MGXS angular treatment representations _REPRESENTATIONS = ['isotropic', 'angle'] @@ -133,9 +133,9 @@ class XSdata(object): angles and outer-dimension being the polar angles. absorption : numpy.ndarray Group-wise absorption cross section ordered by increasing group index - (i.e., fast to thermal). If ``representation`` is "isotropic", then the + (i.e., fast to thermal). If ``representation`` is "isotropic", then the length of this list should equal the number of groups described in the - ``groups`` attribute. If ``representation`` is "angle", then the length + ``groups`` attribute. If ``representation`` is "angle", then the length of this list should equal the number of groups times the number of azimuthal angles times the number of polar angles, with the inner-dimension being groups, intermediate-dimension being azimuthal @@ -152,7 +152,7 @@ class XSdata(object): multiplicity : numpy.ndarray Ratio of neutrons produced in scattering collisions to the neutrons which undergo scattering collisions; that is, the multiplicity provides - the code with a scaling factor to account for neutrons being produced in + the code with a scaling factor to account for neutrons produced in (n,xn) reactions. This information is assumed isotropic and therefore does not need to be repeated for every Legendre moment or histogram/tabular bin. This matrix follows the same arrangement as @@ -160,30 +160,30 @@ class XSdata(object): needed to provide the scattering type information. fission : numpy.ndarray Group-wise fission cross section ordered by increasing group index - (i.e., fast to thermal). If ``representation`` is "isotropic", then the + (i.e., fast to thermal). If ``representation`` is "isotropic", then the length of this list should equal the number of groups described in the - ``groups`` attribute. If ``representation`` is "angle", then the length + ``groups`` attribute. If ``representation`` is "angle", then the length of this list should equal the number of groups times the number of azimuthal angles times the number of polar angles, with the inner-dimension being groups, intermediate-dimension being azimuthal angles and outer-dimension being the polar angles. k_fission : numpy.ndarray - Group-wise kappa-fission cross section ordered by increasing group index - (i.e., fast to thermal). If ``representation`` is "isotropic", then the - length of this list should equal the number of groups described in the - ``groups`` attribute. If ``representation`` is "angle", then the length + Group-wise kappa-fission cross section ordered by increasing group + index (i.e., fast to thermal). If ``representation`` is "isotropic", + then the length of this list should equal the number of groups in the + ``groups`` attribute. If ``representation`` is "angle", then the length of this list should equal the number of groups times the number of azimuthal angles times the number of polar angles, with the inner-dimension being groups, intermediate-dimension being azimuthal angles and outer-dimension being the polar angles. chi : numpy.ndarray - Group-wise fission spectra ordered by increasing group index (i.e., fast - to thermal). This attribute should be used if making the common + Group-wise fission spectra ordered by increasing group index (i.e., + fast to thermal). This attribute should be used if making the common approximation that the fission spectra does not depend on incoming - energy. If the user does not wish to make this approximation, then this - should not be provided and this information included in the + energy. If the user does not wish to make this approximation, then + this should not be provided and this information included in the ``nu_fission`` element instead. If ``representation`` is "isotropic", - then the length of this list should equal the number of groups described + then the length of this list should equal the number of groups in the ``groups`` element. If ``representation`` is "angle", then the length of this list should equal the number of groups times the number of azimuthal angles times the number of polar angles, with the @@ -191,12 +191,13 @@ class XSdata(object): angles and outer-dimension being the polar angles. nu_fission : numpy.ndarray Group-wise fission production cross section vector (i.e., if ``chi`` is - provided), or is the group-wise fission production matrix. If providing + provided), or is the group-wise fission production matrix. If providing the vector, it should be ordered the same as the ``fission`` data. If providing the matrix, it should be ordered the same as the ``multiplicity`` matrix. """ + def __init__(self, name, energy_groups, representation="isotropic"): # Initialize class attributes self._name = name @@ -308,11 +309,11 @@ class XSdata(object): @energy_groups.setter def energy_groups(self, energy_groups): # Check validity of energy_groups - check_type("energy_groups", energy_groups, EnergyGroups) + check_type("energy_groups", energy_groups, openmc.mgxs.EnergyGroups) - # Check that there is one or more groups - if ((energy_groups.num_groups is None) or - (energy_groups.num_groups < 1)): + # Check that there are one or more groups + ng = energy_groups.num_groups + if ((ng is None) or (ng < 1)): msg = 'energy_groups object incorrectly initialized.' raise ValueError(msg) @@ -413,7 +414,8 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("absorption", absorption, np.ndarray, expected_iter_type=Real) + check_type("absorption", absorption, np.ndarray, + expected_iter_type=Real) if absorption.shape == shape: self._absorption = np.copy(absorption) else: @@ -447,14 +449,15 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("k_fission", k_fission, np.ndarray, expected_iter_type=Real) + check_type("k_fission", k_fission, np.ndarray, + expected_iter_type=Real) if k_fission.shape == shape: self._k_fission = np.copy(k_fission) if np.sum(self._k_fission) > 0.0: self._fissionable = True else: - msg = 'Shape of provided k_fission "{0}" does not match shape ' \ - 'required, "{1}"'.format(k_fission.shape, shape) + msg = 'Shape of provided k_fission "{0}" does not match ' \ + 'shape required, "{1}"'.format(k_fission.shape, shape) raise ValueError(msg) @chi.setter @@ -462,6 +465,7 @@ class XSdata(object): if not self._use_chi: msg = 'Providing chi when nu_fission already provided as matrix!' raise ValueError(msg) + if self._representation is 'isotropic': shape = (self._energy_groups.num_groups,) elif self._representation is 'angle': @@ -516,18 +520,21 @@ class XSdata(object): if multiplicity.shape == shape: self._multiplicity = np.copy(multiplicity) else: - msg = 'Shape of provided multiplicity "{0}" does not match shape ' \ - 'required, "{1}"'.format(multiplicity.shape, shape) + msg = 'Shape of provided multiplicity "{0}" does not match shape' \ + ' required, "{1}"'.format(multiplicity.shape, shape) raise ValueError(msg) @nu_fission.setter def nu_fission(self, nu_fission): + # The NuFissionXS class does not have the capability to produce + # a fission matrix and therefore if this path is pursued, we know + # chi must be used. # nu_fission can be given as a vector or a matrix # Vector is used when chi also exists. # Matrix is used when chi does not exist. # We have to check that the correct form is given, but only if # chi already has been set. If not, we just check that this is OK - # and set the use_chi flag. + # and set the use_chi flag accordingly # First lets set our dimensions here since they get used repeatedly # throughout this code. @@ -542,8 +549,8 @@ class XSdata(object): self._energy_groups.num_groups, self._energy_groups.num_groups) - # Begin by checking the case when chi has already been given and thus - # the rules for filling in nu_fission are set. + # Begin by checking the case when chi has already been given and + # thus the rules for filling in nu_fission are set. if self._use_chi is not None: if self._use_chi: shape = shape_vec @@ -553,23 +560,524 @@ class XSdata(object): msg = "Invalid Shape of Nu_fission!" raise ValueError(msg) else: - # Get shape of nu_fission so we can figure if we need chi or not + # Get shape of nu_fission to determine if we need chi or not if nu_fission.shape == shape_vec: self._use_chi = True - shape = shape_vec elif nu_fission.shape == shape_mat: self._use_chi = False - shape = shape_mat else: msg = "Invalid Shape of Nu_fission!" raise ValueError(msg) # check we have a numpy list - check_type("nu_fission", nu_fission, np.ndarray, expected_iter_type=Real) + check_type("nu_fission", nu_fission, np.ndarray, + expected_iter_type=Real) self._nu_fission = np.copy(nu_fission) if np.sum(self._nu_fission) > 0.0: self._fissionable = True + def set_total(self, total, **kwargs): + if isinstance(total, openmc.mgxs.TotalXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != total.energy_groups: + msg = 'Group structure of provided TotalXS does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._total = total.get_xs(subdomains=subdomains, + nuclides=nuclides, xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups,) + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + # check we have a numpy list + check_type("total", total, np.ndarray, expected_iter_type=Real) + if total.shape == shape: + self._total = np.copy(total) + else: + msg = 'Shape of provided total "{0}" does not match shape ' \ + 'required, "{1}"'.format(total.shape, shape) + raise ValueError(msg) + + def set_absorption(self, absorption, **kwargs): + if isinstance(absorption, openmc.mgxs.AbsorptionXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != absorption.energy_groups: + msg = 'Group structure of provided AbsorptionXS does not ' \ + ' match group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._absorption = absorption.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups,) + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + # check we have a numpy list + check_type("absorption", absorption, np.ndarray, expected_iter_type=Real) + if absorption.shape == shape: + self._absorption = np.copy(absorption) + else: + msg = 'Shape of provided absorption "{0}" does not match shape ' \ + 'required, "{1}"'.format(absorption.shape, shape) + raise ValueError(msg) + + def set_fission(self, fission, **kwargs): + if isinstance(fission, openmc.mgxs.FissionXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != fission.energy_groups: + msg = 'Group structure of provided FissionXS does not match ' \ + 'group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._fission = fission.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups,) + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + # check we have a numpy list + check_type("fission", fission, np.ndarray, expected_iter_type=Real) + if fission.shape == shape: + self._fission = np.copy(fission) + if np.sum(self._fission) > 0.0: + self._fissionable = True + else: + msg = 'Shape of provided fission "{0}" does not match shape ' \ + 'required, "{1}"'.format(fission.shape, shape) + raise ValueError(msg) + + def set_k_fission(self, k_fission, **kwargs): + if isinstance(k_fission, openmc.mgxs.KappaFissionXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != k_fission.energy_groups: + msg = 'Group structure of provided KappaFissionXS does not ' \ + 'match group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._k_fission = k_fission.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups,) + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + # check we have a numpy list + check_type("k_fission", k_fission, np.ndarray, + expected_iter_type=Real) + if k_fission.shape == shape: + self._k_fission = np.copy(k_fission) + if np.sum(self._k_fission) > 0.0: + self._fissionable = True + else: + msg = 'Shape of provided k_fission "{0}" does not match ' \ + 'shape required, "{1}"'.format(k_fission.shape, shape) + raise ValueError(msg) + + def set_chi(self, chi, **kwargs): + if not self._use_chi: + msg = 'Providing chi when nu_fission already provided as matrix!' + raise ValueError(msg) + + if isinstance(chi, openmc.mgxs.Chi): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != chi.energy_groups: + msg = 'Group structure of provided Chi does not ' \ + 'match group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._chi = chi.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups,) + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + # check we have a numpy list + check_type("chi", chi, np.ndarray, expected_iter_type=Real) + if chi.shape == shape: + self._chi = np.copy(chi) + else: + msg = 'Shape of provided chi "{0}" does not match shape ' \ + 'required, "{1}"'.format(chi.shape, shape) + raise ValueError(msg) + if self._use_chi is not None: + self._use_chi = True + + def set_scatter(self, scatter, **kwargs): + if isinstance(scatter, openmc.mgxs.ScatterMatrixXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != scatter.energy_groups: + msg = 'Group structure of provided ScatterMatrixXS does not ' \ + 'match group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._scatter = scatter.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self.num_orders, self._energy_groups.num_groups, + self._energy_groups.num_groups) + max_depth = 3 + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, self.num_orders, + self._energy_groups.num_groups, + self._energy_groups.num_groups) + max_depth = 5 + # check we have a numpy list + check_iterable_type("scatter", scatter, expected_type=Real, + max_depth=max_depth) + if scatter.shape == shape: + self._scatter = np.copy(scatter) + else: + msg = 'Shape of provided scatter "{0}" does not match shape ' \ + 'required, "{1}"'.format(scatter.shape, shape) + raise ValueError(msg) + + def set_multiplicity(self, multiplicity, scatter=None, **kwargs): + if isinstance(multiplicity, openmc.mgxs.NuScatterMatrixXS): + if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): + msg = "Argument 'scatter' must be provided." + raise ValueError(msg) + # Make sure passed MGXS objects contain correct group structure + if self.energy_groups != multiplicity.energy_groups: + msg = 'Group structure of provided NuScatterMatrixXS does not ' \ + 'match group structure of XSdata object' + raise ValueError(msg) + if self.energy_groups != scatter.energy_groups: + msg = 'Group structure of provided ScatterMatrixXS does not ' \ + 'match group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + nuscatt = multiplicity.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + scatt = scatter.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + self._multiplicity = np.divide(nuscatt, scatt) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + else: + if self._representation is 'isotropic': + shape = (self._energy_groups.num_groups, + self._energy_groups.num_groups) + max_depth = 2 + elif self._representation is 'angle': + shape = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups, + self._energy_groups.num_groups) + max_depth = 4 + # check we have a numpy list + check_iterable_type("multiplicity", multiplicity, expected_type=Real, + max_depth=max_depth) + if multiplicity.shape == shape: + self._multiplicity = np.copy(multiplicity) + else: + msg = 'Shape of provided multiplicity "{0}" does not match shape' \ + ' required, "{1}"'.format(multiplicity.shape, shape) + raise ValueError(msg) + + def set_nu_fission(self, nu_fission, **kwargs): + # The NuFissionXS class does not have the capability to produce + # a fission matrix and therefore if this path is pursued, we know + # chi must be used. + if isinstance(nu_fission, openmc.mgxs.NuFissionXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != nu_fission.energy_groups: + msg = 'Group structure of provided NuFissionXS does not match'\ + ' group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._nu_fission = nu_fission.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + self._use_chi = True + + else: + # nu_fission can be given as a vector or a matrix + # Vector is used when chi also exists. + # Matrix is used when chi does not exist. + # We have to check that the correct form is given, but only if + # chi already has been set. If not, we just check that this is OK + # and set the use_chi flag accordingly + + # First lets set our dimensions here since they get used repeatedly + # throughout this code. + if self._representation is 'isotropic': + shape_vec = (self._energy_groups.num_groups,) + shape_mat = (self._energy_groups.num_groups, + self._energy_groups.num_groups) + elif self._representation is 'angle': + shape_vec = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + shape_mat = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups, + self._energy_groups.num_groups) + + # Begin by checking the case when chi has already been given and + # thus the rules for filling in nu_fission are set. + if self._use_chi is not None: + if self._use_chi: + shape = shape_vec + else: + shape = shape_mat + if nu_fission.shape != shape: + msg = "Invalid Shape of Nu_fission!" + raise ValueError(msg) + else: + # Get shape of nu_fission to determine if we need chi or not + if nu_fission.shape == shape_vec: + self._use_chi = True + elif nu_fission.shape == shape_mat: + self._use_chi = False + else: + msg = "Invalid Shape of Nu_fission!" + raise ValueError(msg) + + # check we have a numpy list + check_type("nu_fission", nu_fission, np.ndarray, + expected_iter_type=Real) + self._nu_fission = np.copy(nu_fission) + if np.sum(self._nu_fission) > 0.0: + self._fissionable = True + def _get_xsdata_xml(self): element = ET.Element("xsdata") element.set("name", self._name) @@ -649,7 +1157,8 @@ class XSdata(object): class MGXSLibrary(object): """Multi-Group Cross Sections file used for an OpenMC simulation. - Corresponds directly to the MG version of the cross_sections.xml input file. + Corresponds directly to the MG version of the cross_sections.xml input + file. Attributes ---------- @@ -684,7 +1193,7 @@ class MGXSLibrary(object): @energy_groups.setter def energy_groups(self, energy_groups): - check_type("energy groups", energy_groups, EnergyGroups) + check_type("energy groups", energy_groups, openmc.mgxs.EnergyGroups) self._energy_groups = energy_groups def add_xsdata(self, xsdata): @@ -721,8 +1230,8 @@ class MGXSLibrary(object): """ if not isinstance(xsdatas, Iterable): - msg = 'Unable to create OpenMC xsdatas.xml file from "{0}" which ' \ - 'is not iterable'.format(xsdatas) + msg = 'Unable to create OpenMC xsdatas.xml file from "{0}" which' \ + ' is not iterable'.format(xsdatas) raise ValueError(msg) for xsdata in xsdatas: @@ -793,4 +1302,4 @@ class MGXSLibrary(object): # Write the XML Tree to the xsdatas.xml file tree = ET.ElementTree(self._cross_sections_file) tree.write(filename, xml_declaration=True, - encoding='utf-8', method="xml") + encoding='utf-8', method="xml") diff --git a/openmc/settings.py b/openmc/settings.py index ec38bf54c..e64935d7a 100644 --- a/openmc/settings.py +++ b/openmc/settings.py @@ -70,9 +70,10 @@ class Settings(object): deviation. cross_sections : str Indicates the path to an XML cross section listing file (usually named - cross_sections.xml). If it is not set, the :envvar:`CROSS_SECTIONS` - environment variable will be used for continuous-energy calculations - and :envvar:`MG_CROSS_SECTIONS` will be used for multi-group + cross_sections.xml). If it is not set, the + :envvar:`OPENMC_CROSS_SECTIONS` environment variable will be used for + continuous-energy calculations and + :envvar:`OPENMC_MG_CROSS_SECTIONS` will be used for multi-group calculations to find the path to the XML cross section file. energy_grid : {'nuclide', 'logarithm', 'material-union'} Set the method used to search energy grids. From e5432e84a8c5398296c6229a1ab073f86697d58a Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 1 May 2016 01:25:45 -0400 Subject: [PATCH 064/147] Improved wording of latest developmental branch URL in docs --- docs/source/index.rst | 4 +++- 1 file changed, 3 insertions(+), 1 deletion(-) diff --git a/docs/source/index.rst b/docs/source/index.rst index 7edc560e2..a79a10de1 100644 --- a/docs/source/index.rst +++ b/docs/source/index.rst @@ -13,7 +13,9 @@ OpenMC was originally developed by members of the `Computational Reactor Physics Group`_ at the `Massachusetts Institute of Technology`_ starting in 2011. Various universities, laboratories, and other organizations now contribute to the development of OpenMC. For more information on OpenMC, feel -free to send a message to the User's Group `mailing list`_. Documentation for the latest version of the develop branch can be found on `Read the Docs`_. +free to send a message to the User's Group `mailing list`_. Documentation for +the latest developmental version of the develop branch can be found on +`Read the Docs`_. .. _Computational Reactor Physics Group: http://crpg.mit.edu .. _Massachusetts Institute of Technology: http://web.mit.edu From e1f70b40d40fcc302c833bb6a1349846f4cbcd65 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 1 May 2016 10:23:20 -0400 Subject: [PATCH 065/147] Incorporated ability to transfer from Library to MGXS_Library. Didnt test yet. --- openmc/mgxs/library.py | 168 +++++++++++++++++++++++++++++++++++++ openmc/mgxs_library.py | 184 ++++++++++++++++++++--------------------- 2 files changed, 260 insertions(+), 92 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index f3bf2018d..7e6f07ce2 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -4,6 +4,8 @@ import copy import pickle from numbers import Integral from collections import OrderedDict +import numpy as np +import warnings.warn as warn import openmc import openmc.mgxs @@ -712,3 +714,169 @@ class Library(object): # Load and return pickled Library object return pickle.load(open(full_filename, 'rb')) + + def write_mg_library(self, xs_type='micro', domain_names=None, xs_ids=None, + filename='mg_cross_sections', directory='./'): + """Create a cross-section data library file for the Multi-Group + mode of OpenMC. + + Parameters + ---------- + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. If the Library object is not tallied by + nuclide this will be set to 'macro' regardless + domain_names : Iterable of str + List of names to apply to the xsdata entries in the + resultant mgxs data file. Defaults to "set1", "set2", ... + xs_ids : str or Iterable of str + Cross section set identifier (i.e., "71c") for all + data sets (if only str) or for each individual one + (if iterable of str). Defaults to '1g' + filename : str + Filename for the pickle file. Defaults to 'mg_cross_sections'. + directory : str + Directory for the pickle file. Defaults to './' (the + current working directory). + + See also + -------- + Library.dump_to_file(mgxs_lib, filename, directory) + + """ + + # Check data types provided + + cv.check_value('xs_type', xs_type, ['macro', 'micro']) + if not self.by_nuclide: + xs_type = 'macro' + if domain_names is not None: + cv.check_iterable_type('domain_names', filename, basestring) + if xs_ids is not None: + if isinstance(xs_ids, basestring): + # If we only have a string lets convert it now to a list + # of strings. + xs_ids = [xs_ids for i in range(len(self.domains))] + else: + cv.check_iterable_type('xs_ids', xs_ids, basestring) + else: + xs_ids = ['.1g'] + cv.check_type('filename', filename, basestring) + cv.check_type('directory', directory, basestring) + + # Make directory if it does not exist + if not os.path.exists(directory): + os.makedirs(directory) + + full_filename = os.path.join(directory, filename + '.xml') + full_filename = full_filename.replace(' ', '-') + + # Initialize file + mgxs_file = openmc.MGXSLibrary(self.energy_groups) + + # Set the scattering order as isotropic until + # support for higher orders are included + order = 0 + + # Build XSdata objects + xsdatas = [] + for i in range(len(self.domains)): + id = self.domains[i].id + if not self.by_nuclide: + # Use k instead of i simply because k will be used for + # the nuclide index in the else part of this conditional + # and using k allows us to use the same code. + k = i + # Build & add metadata to XSdata object + # (Use i here because k in nuclides will add chars to this) + if domain_names is None: + name = 'set' + str(i + 1) + else: + name = domain_names[i] + name += xs_ids[k] + xsdata = openmc.XSdata(name, self.energy_groups) + xsdata.order = order + + # Now get xs data itself + if 'total' in self.mgxs_types: + xsdata.set_total(self.all_mgxs[id]['total'], + xs_type=xs_type, subdomains=(k + 1,)) + if 'absorption' in self.mgxs_types: + xsdata.set_absorption(self.all_mgxs[id]['absorption'], + xs_type=xs_type, subdomains=(k + 1,)) + if 'fission' in self.mgxs_types: + xsdata.set_fission(self.all_mgxs[id]['fission'], + xs_type=xs_type, subdomains=(k + 1,)) + if 'kappa-fission' in self.mgxs_types: + xsdata.set_k_fission(self.all_mgxs[id]['kappa-fission'], + xs_type=xs_type, subdomains=(k + 1,)) + if 'chi' in self.mgxs_types: + xsdata.set_chi(self.all_mgxs[id]['chi'], + xs_type=xs_type, subdomains=(k + 1,)) + if 'nu-fission' in self.mgxs_types: + xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], + xs_type=xs_type, subdomains=(k + 1,)) + # multiplicity requires scatter and nu-scatter + if (('scatter' in self.mgxs_types) and ('nu-scatter' in + self.mgxs_types)): + xsdata.set_multiplicity(self.all_mgxs[id]['nu-scatter'], + self.all_mgxs[id]['scatter'], + xs_type=xs_type, + subdomains=(k + 1,)) + using_multiplicity = True + else: + using_multiplicity = False + + if using_multiplicity: + xsdata.set_scatter(self.all_mgxs[id]['scatter'], + xs_type=xs_type, + subdomains=(k + 1,)) + else: + if 'nu-scatter' in self.mgxs_types: + xsdata.set_scatter(self.all_mgxs[id]['nu-scatter'], + xs_type=xs_type, + subdomains=(k + 1,)) + # Since we are not using multiplicity, then + # scattering multiplication (nu-scatter) must be + # accounted for approximately by using an adjusted + # absorption cross section. + if self.total is not None: + xsdata.absorption = \ + np.subtract(xsdata.total, + np.sum(xsdata.scatter[0, :, :], + axis=1)) + else: + # Total isnt included so we cant do the above + # approximation w/out changing absorption instead. + # That can be done with: + # SigA' = SigA - (nuSigS - SigS) + # Doing so would mean essentially duplicating + # set_scatter from MGXSLibrary to obtain the + # SigS, which would be big and ugly once + # angle filters are available. + # Instead, raise a warning about the + # lack of neutron balance and then use scatter + # instead of nu-scatter + if 'scatter' in self.mgxs_types: + msg = "To properly use the 'nu-scatter' " + \ + "MGXS type and maintain neutron " + \ + "balance, a 'total' MGXS type " + \ + "should be provided." + warn(msg) + xsdata.set_scatter( + self.all_mgxs[id]['scatter'], + xs_type=xs_type, subdomains=(k + 1,)) + else: + # Welp, cant do that either. Quit while ahead. + msg = "Total X/S must be provided if using" + \ + " nu-scatter as the scattering data" + raise ValueError(msg) + + xsdatas.append(xsdata) + else: + pass + + # Add XSdatas to file + + # Finally, write the file + mgxs_file.export_to_xml(full_filename) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index b41a2030c..eae6aa4c1 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -739,6 +739,98 @@ class XSdata(object): 'required, "{1}"'.format(fission.shape, shape) raise ValueError(msg) + def set_nu_fission(self, nu_fission, **kwargs): + # The NuFissionXS class does not have the capability to produce + # a fission matrix and therefore if this path is pursued, we know + # chi must be used. + if isinstance(nu_fission, openmc.mgxs.NuFissionXS): + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != nu_fission.energy_groups: + msg = 'Group structure of provided NuFissionXS does not match'\ + ' group structure of XSdata object' + raise ValueError(msg) + # Get openmc.mgxs.get_xs() arguments from kwargs + # nuclides, xs_type, and value will have sane defaults but can be + # overridden by kwards + if 'nuclides' in kwargs: + nuclides = kwargs['nuclides'] + else: + nuclides = 'sum' + if 'xs_type' in kwargs: + xs_type = kwargs['xs_type'] + else: + xs_type = 'macro' + if 'value' in kwargs: + value = kwargs['value'] + else: + value = 'mean' + # subdomains is required from the kwargs as this is specific to + # this XSdata object. + if 'subdomains' in kwargs: + subdomains = kwargs['subdomains'] + else: + msg = "Argument 'subdomains' is required" + raise ValueError(msg) + + if self._representation is 'isotropic': + self._nu_fission = nu_fission.get_xs(subdomains=subdomains, + nuclides=nuclides, + xs_type=xs_type, + value=value) + elif self._representation is 'angle': + # Not yet implemented as MGXS do not yet support this + pass + + self._use_chi = True + + else: + # nu_fission can be given as a vector or a matrix + # Vector is used when chi also exists. + # Matrix is used when chi does not exist. + # We have to check that the correct form is given, but only if + # chi already has been set. If not, we just check that this is OK + # and set the use_chi flag accordingly + + # First lets set our dimensions here since they get used repeatedly + # throughout this code. + if self._representation is 'isotropic': + shape_vec = (self._energy_groups.num_groups,) + shape_mat = (self._energy_groups.num_groups, + self._energy_groups.num_groups) + elif self._representation is 'angle': + shape_vec = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups) + shape_mat = (self._num_polar, self._num_azimuthal, + self._energy_groups.num_groups, + self._energy_groups.num_groups) + + # Begin by checking the case when chi has already been given and + # thus the rules for filling in nu_fission are set. + if self._use_chi is not None: + if self._use_chi: + shape = shape_vec + else: + shape = shape_mat + if nu_fission.shape != shape: + msg = "Invalid Shape of Nu_fission!" + raise ValueError(msg) + else: + # Get shape of nu_fission to determine if we need chi or not + if nu_fission.shape == shape_vec: + self._use_chi = True + elif nu_fission.shape == shape_mat: + self._use_chi = False + else: + msg = "Invalid Shape of Nu_fission!" + raise ValueError(msg) + + # check we have a numpy list + check_type("nu_fission", nu_fission, np.ndarray, + expected_iter_type=Real) + self._nu_fission = np.copy(nu_fission) + if np.sum(self._nu_fission) > 0.0: + self._fissionable = True + def set_k_fission(self, k_fission, **kwargs): if isinstance(k_fission, openmc.mgxs.KappaFissionXS): # Make sure passed MGXS object contains correct group structure @@ -986,98 +1078,6 @@ class XSdata(object): ' required, "{1}"'.format(multiplicity.shape, shape) raise ValueError(msg) - def set_nu_fission(self, nu_fission, **kwargs): - # The NuFissionXS class does not have the capability to produce - # a fission matrix and therefore if this path is pursued, we know - # chi must be used. - if isinstance(nu_fission, openmc.mgxs.NuFissionXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != nu_fission.energy_groups: - msg = 'Group structure of provided NuFissionXS does not match'\ - ' group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) - - if self._representation is 'isotropic': - self._nu_fission = nu_fission.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass - - self._use_chi = True - - else: - # nu_fission can be given as a vector or a matrix - # Vector is used when chi also exists. - # Matrix is used when chi does not exist. - # We have to check that the correct form is given, but only if - # chi already has been set. If not, we just check that this is OK - # and set the use_chi flag accordingly - - # First lets set our dimensions here since they get used repeatedly - # throughout this code. - if self._representation is 'isotropic': - shape_vec = (self._energy_groups.num_groups,) - shape_mat = (self._energy_groups.num_groups, - self._energy_groups.num_groups) - elif self._representation is 'angle': - shape_vec = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - shape_mat = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - - # Begin by checking the case when chi has already been given and - # thus the rules for filling in nu_fission are set. - if self._use_chi is not None: - if self._use_chi: - shape = shape_vec - else: - shape = shape_mat - if nu_fission.shape != shape: - msg = "Invalid Shape of Nu_fission!" - raise ValueError(msg) - else: - # Get shape of nu_fission to determine if we need chi or not - if nu_fission.shape == shape_vec: - self._use_chi = True - elif nu_fission.shape == shape_mat: - self._use_chi = False - else: - msg = "Invalid Shape of Nu_fission!" - raise ValueError(msg) - - # check we have a numpy list - check_type("nu_fission", nu_fission, np.ndarray, - expected_iter_type=Real) - self._nu_fission = np.copy(nu_fission) - if np.sum(self._nu_fission) > 0.0: - self._fissionable = True - def _get_xsdata_xml(self): element = ET.Element("xsdata") element.set("name", self._name) From 9bff2ab4747873a542a27cd7cfdf7341c23a4405 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 1 May 2016 13:49:51 -0400 Subject: [PATCH 066/147] Updated Mann-Whitney test to reflect lattice cell indexing in new distribcell paths --- .../examples/pandas-dataframes.ipynb | 63 +++++++++---------- 1 file changed, 31 insertions(+), 32 deletions(-) diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index 34b136ee9..87eb50f7b 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -370,7 +370,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -554,9 +554,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 5863cc5c9906ae7b2ec15efbf793b22b9c7f7dcb\n", - " Date/Time: 2016-04-30 09:44:46\n", - " MPI Processes: 1\n", + " Git SHA1: cc27630f7db25b148efab11d182c6c7b34e40a5b\n", + " Date/Time: 2016-05-01 13:49:06\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -620,20 +619,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.1400E-01 seconds\n", - " Reading cross sections = 9.3000E-02 seconds\n", - " Total time in simulation = 4.6240E+00 seconds\n", - " Time in transport only = 4.5580E+00 seconds\n", - " Time in inactive batches = 6.9200E-01 seconds\n", - " Time in active batches = 3.9320E+00 seconds\n", - " Time synchronizing fission bank = 2.0000E-03 seconds\n", - " Sampling source sites = 1.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for initialization = 3.9900E-01 seconds\n", + " Reading cross sections = 9.0000E-02 seconds\n", + " Total time in simulation = 4.8580E+00 seconds\n", + " Time in transport only = 4.8080E+00 seconds\n", + " Time in inactive batches = 7.9400E-01 seconds\n", + " Time in active batches = 4.0640E+00 seconds\n", + " Time synchronizing fission bank = 0.0000E+00 seconds\n", + " Sampling source sites = 0.0000E+00 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 5.0530E+00 seconds\n", - " Calculation Rate (inactive) = 18063.6 neutrons/second\n", - " Calculation Rate (active) = 9537.13 neutrons/second\n", + " Total time elapsed = 5.2710E+00 seconds\n", + " Calculation Rate (inactive) = 15743.1 neutrons/second\n", + " Calculation Rate (active) = 9227.36 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1112,7 +1111,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2267,15 +2266,15 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 6.038663783e-42\n" + "Mann-Whitney Test p-value: 0.303583331507\n" ] } ], "source": [ - "# Extract tally data from pins in the pins divided along y=-x diagonal\n", + "# Extract tally data from pins in the pins divided along y=x diagonal\n", "multi_index = ('level 2', 'lat',)\n", - "lower = df[df[multi_index + ('x',)] > df[multi_index + ('y',)]]\n", - "upper = df[df[multi_index + ('x',)] < df[multi_index + ('y',)]]\n", + "lower = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] < 16]\n", + "upper = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] > 16]\n", "lower = lower[lower['score'] == 'absorption']\n", "upper = upper[upper['score'] == 'absorption']\n", "\n", @@ -2305,15 +2304,15 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 0.303583331507\n" + "Mann-Whitney Test p-value: 6.038663783e-42\n" ] } ], "source": [ - "# Extract tally data from pins in the pins divided along y=x diagonal \n", + "# Extract tally data from pins in the pins divided along y=-x diagonal \n", "multi_index = ('level 2', 'lat',)\n", - "lower = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] < 16]\n", - "upper = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] > 16]\n", + "lower = df[df[multi_index + ('x',)] > df[multi_index + ('y',)]]\n", + "upper = df[df[multi_index + ('x',)] < df[multi_index + ('y',)]]\n", "lower = lower[lower['score'] == 'absorption']\n", "upper = upper[upper['score'] == 'absorption']\n", "\n", @@ -2351,7 +2350,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 38, @@ -2362,7 +2361,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, From 1f17718de845d70732485418de27ee307bb63de2 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 1 May 2016 13:53:21 -0400 Subject: [PATCH 067/147] Tested, works (!!!!). Next up will be some useful features found during this testing --- openmc/mgxs/library.py | 32 ++++++++++++++++++-------------- openmc/mgxs_library.py | 14 ++++++++------ 2 files changed, 26 insertions(+), 20 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 7e6f07ce2..0ce7348b9 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -5,7 +5,7 @@ import pickle from numbers import Integral from collections import OrderedDict import numpy as np -import warnings.warn as warn +from warnings import warn import openmc import openmc.mgxs @@ -715,7 +715,7 @@ class Library(object): # Load and return pickled Library object return pickle.load(open(full_filename, 'rb')) - def write_mg_library(self, xs_type='micro', domain_names=None, xs_ids=None, + def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, filename='mg_cross_sections', directory='./'): """Create a cross-section data library file for the Multi-Group mode of OpenMC. @@ -725,7 +725,7 @@ class Library(object): xs_type: {'macro', 'micro'} Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. If the Library object is not tallied by - nuclide this will be set to 'macro' regardless + nuclide this will be set to 'macro' regardless. domain_names : Iterable of str List of names to apply to the xsdata entries in the resultant mgxs data file. Defaults to "set1", "set2", ... @@ -760,7 +760,7 @@ class Library(object): else: cv.check_iterable_type('xs_ids', xs_ids, basestring) else: - xs_ids = ['.1g'] + xs_ids = ['1g'] cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) @@ -781,6 +781,7 @@ class Library(object): # Build XSdata objects xsdatas = [] for i in range(len(self.domains)): + id = self.domains[i].id if not self.by_nuclide: # Use k instead of i simply because k will be used for @@ -793,7 +794,7 @@ class Library(object): name = 'set' + str(i + 1) else: name = domain_names[i] - name += xs_ids[k] + name += '.' + xs_ids[k] xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order @@ -817,10 +818,10 @@ class Library(object): xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], xs_type=xs_type, subdomains=(k + 1,)) # multiplicity requires scatter and nu-scatter - if (('scatter' in self.mgxs_types) and ('nu-scatter' in - self.mgxs_types)): - xsdata.set_multiplicity(self.all_mgxs[id]['nu-scatter'], - self.all_mgxs[id]['scatter'], + if ((('scatter matrix' in self.mgxs_types) and + ('nu-scatter matrix' in self.mgxs_types))): + xsdata.set_multiplicity(self.all_mgxs[id]['nu-scatter matrix'], + self.all_mgxs[id]['scatter matrix'], xs_type=xs_type, subdomains=(k + 1,)) using_multiplicity = True @@ -828,12 +829,12 @@ class Library(object): using_multiplicity = False if using_multiplicity: - xsdata.set_scatter(self.all_mgxs[id]['scatter'], + xsdata.set_scatter(self.all_mgxs[id]['scatter matrix'], xs_type=xs_type, subdomains=(k + 1,)) else: if 'nu-scatter' in self.mgxs_types: - xsdata.set_scatter(self.all_mgxs[id]['nu-scatter'], + xsdata.set_scatter(self.all_mgxs[id]['nu-scatter matrix'], xs_type=xs_type, subdomains=(k + 1,)) # Since we are not using multiplicity, then @@ -858,8 +859,9 @@ class Library(object): # lack of neutron balance and then use scatter # instead of nu-scatter if 'scatter' in self.mgxs_types: - msg = "To properly use the 'nu-scatter' " + \ - "MGXS type and maintain neutron " + \ + msg = "To properly use the " + \ + "'nu-scatter matrix' MGXS type " + \ + "and maintain neutron " + \ "balance, a 'total' MGXS type " + \ "should be provided." warn(msg) @@ -869,7 +871,8 @@ class Library(object): else: # Welp, cant do that either. Quit while ahead. msg = "Total X/S must be provided if using" + \ - " nu-scatter as the scattering data" + " 'nu-scatter matrix' as the " + \ + "scattering data" raise ValueError(msg) xsdatas.append(xsdata) @@ -877,6 +880,7 @@ class Library(object): pass # Add XSdatas to file + mgxs_file.add_xsdatas(xsdatas) # Finally, write the file mgxs_file.export_to_xml(full_filename) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index eae6aa4c1..ef12c6c8a 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -462,9 +462,10 @@ class XSdata(object): @chi.setter def chi(self, chi): - if not self._use_chi: - msg = 'Providing chi when nu_fission already provided as matrix!' - raise ValueError(msg) + if self._use_chi is not None: + if not self._use_chi: + msg = 'Providing chi when nu_fission already provided as matrix!' + raise ValueError(msg) if self._representation is 'isotropic': shape = (self._energy_groups.num_groups,) @@ -889,9 +890,10 @@ class XSdata(object): raise ValueError(msg) def set_chi(self, chi, **kwargs): - if not self._use_chi: - msg = 'Providing chi when nu_fission already provided as matrix!' - raise ValueError(msg) + if self._use_chi is not None: + if not self._use_chi: + msg = 'Providing chi when nu_fission already provided as matrix!' + raise ValueError(msg) if isinstance(chi, openmc.mgxs.Chi): # Make sure passed MGXS object contains correct group structure From 192523743f8519759f863362927eb8674950dce0 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 1 May 2016 15:20:13 -0400 Subject: [PATCH 068/147] Implemented microscopic nuclidic writing for mgxs_library. May have exposed a bug in OpenMC, need to understand. --- openmc/mgxs/library.py | 177 +++++++++++++++++++++++++++++------------ 1 file changed, 125 insertions(+), 52 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 0ce7348b9..1e9156ce5 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -15,6 +15,11 @@ import openmc.checkvalue as cv if sys.version_info[0] >= 3: basestring = str +# The following represent the most accurate MGXS generation strategy +# for use in the MG mode of OpenMC. +OPENMC_MG_MGXS_TYPES = ['total', 'absorption', 'nu-fission', 'chi', + 'scatter matrix', 'nu-scatter matrix'] + class Library(object): """A multi-group cross section library for some energy group structure. @@ -748,7 +753,10 @@ class Library(object): # Check data types provided cv.check_value('xs_type', xs_type, ['macro', 'micro']) - if not self.by_nuclide: + # Construct the collection of the nuclides to report + if self.by_nuclide: + nuclides = self.all_mgxs[1][self.mgxs_types[-1]].get_all_nuclides() + else: xs_type = 'macro' if domain_names is not None: cv.check_iterable_type('domain_names', filename, basestring) @@ -781,62 +789,58 @@ class Library(object): # Build XSdata objects xsdatas = [] for i in range(len(self.domains)): - id = self.domains[i].id if not self.by_nuclide: - # Use k instead of i simply because k will be used for - # the nuclide index in the else part of this conditional - # and using k allows us to use the same code. - k = i # Build & add metadata to XSdata object # (Use i here because k in nuclides will add chars to this) if domain_names is None: name = 'set' + str(i + 1) else: name = domain_names[i] - name += '.' + xs_ids[k] + name += '.' + xs_ids[i] xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order # Now get xs data itself if 'total' in self.mgxs_types: xsdata.set_total(self.all_mgxs[id]['total'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) if 'absorption' in self.mgxs_types: xsdata.set_absorption(self.all_mgxs[id]['absorption'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) if 'fission' in self.mgxs_types: xsdata.set_fission(self.all_mgxs[id]['fission'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) if 'kappa-fission' in self.mgxs_types: xsdata.set_k_fission(self.all_mgxs[id]['kappa-fission'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) if 'chi' in self.mgxs_types: xsdata.set_chi(self.all_mgxs[id]['chi'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) if 'nu-fission' in self.mgxs_types: xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], - xs_type=xs_type, subdomains=(k + 1,)) + xs_type=xs_type, subdomains=(i + 1,)) # multiplicity requires scatter and nu-scatter if ((('scatter matrix' in self.mgxs_types) and ('nu-scatter matrix' in self.mgxs_types))): - xsdata.set_multiplicity(self.all_mgxs[id]['nu-scatter matrix'], - self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, - subdomains=(k + 1,)) + xsdata.set_multiplicity( + self.all_mgxs[id]['nu-scatter matrix'], + self.all_mgxs[id]['scatter matrix'], + xs_type=xs_type, subdomains=(i + 1,)) + xsdata.multiplicity = np.nan_to_num(xsdata.multiplicity) using_multiplicity = True else: using_multiplicity = False if using_multiplicity: - xsdata.set_scatter(self.all_mgxs[id]['scatter matrix'], + xsdata.set_scatter(self.all_mgxs[id]['nu-scatter matrix'], xs_type=xs_type, - subdomains=(k + 1,)) + subdomains=(i + 1,)) else: - if 'nu-scatter' in self.mgxs_types: - xsdata.set_scatter(self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, - subdomains=(k + 1,)) + if 'nu-scatter matrix' in self.mgxs_types: + xsdata.set_scatter( + self.all_mgxs[id]['nu-scatter matrix'], + xs_type=xs_type, subdomains=(i + 1,)) # Since we are not using multiplicity, then # scattering multiplication (nu-scatter) must be # accounted for approximately by using an adjusted @@ -846,41 +850,110 @@ class Library(object): np.subtract(xsdata.total, np.sum(xsdata.scatter[0, :, :], axis=1)) - else: - # Total isnt included so we cant do the above - # approximation w/out changing absorption instead. - # That can be done with: - # SigA' = SigA - (nuSigS - SigS) - # Doing so would mean essentially duplicating - # set_scatter from MGXSLibrary to obtain the - # SigS, which would be big and ugly once - # angle filters are available. - # Instead, raise a warning about the - # lack of neutron balance and then use scatter - # instead of nu-scatter - if 'scatter' in self.mgxs_types: - msg = "To properly use the " + \ - "'nu-scatter matrix' MGXS type " + \ - "and maintain neutron " + \ - "balance, a 'total' MGXS type " + \ - "should be provided." - warn(msg) - xsdata.set_scatter( - self.all_mgxs[id]['scatter'], - xs_type=xs_type, subdomains=(k + 1,)) - else: - # Welp, cant do that either. Quit while ahead. - msg = "Total X/S must be provided if using" + \ - " 'nu-scatter matrix' as the " + \ - "scattering data" - raise ValueError(msg) + else: + msg = "No nu-scatter matrix data was provided. " + \ + "This means neutron balance cannot be " + \ + "achieved since (n,xn) multiplication is " + \ + "ignored." + warn(msg) + xsdata.set_scatter(self.all_mgxs[id]['scatter matrix'], + xs_type=xs_type, + subdomains=(i + 1,)) xsdatas.append(xsdata) else: - pass + for nuclide in nuclides: + # Build & add metadata to XSdata object + if domain_names is None: + name = 'set' + str(i + 1) + else: + name = domain_names[i] + name += '_' + nuclide + name += '.' + xs_ids[i] + xsdata = openmc.XSdata(name, self.energy_groups) + xsdata.order = order + + # Now get xs data itself + if 'total' in self.mgxs_types: + xsdata.set_total(self.all_mgxs[id]['total'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + if 'absorption' in self.mgxs_types: + xsdata.set_absorption(self.all_mgxs[id]['absorption'], + xs_type=xs_type, + subdomains=(i + 1,), + nuclides=[nuclide]) + if 'fission' in self.mgxs_types: + xsdata.set_fission(self.all_mgxs[id]['fission'], + xs_type=xs_type, + subdomains=(i + 1,), + nuclides=[nuclide]) + if 'kappa-fission' in self.mgxs_types: + xsdata.set_k_fission( + self.all_mgxs[id]['kappa-fission'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + if 'chi' in self.mgxs_types: + xsdata.set_chi(self.all_mgxs[id]['chi'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + if 'nu-fission' in self.mgxs_types: + xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], + xs_type=xs_type, + subdomains=(i + 1,), + nuclides=[nuclide]) + # multiplicity requires scatter and nu-scatter + if ((('scatter matrix' in self.mgxs_types) and + ('nu-scatter matrix' in self.mgxs_types))): + xsdata.set_multiplicity( + self.all_mgxs[id]['nu-scatter matrix'], + self.all_mgxs[id]['scatter matrix'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + xsdata.multiplicity = \ + np.nan_to_num(xsdata.multiplicity) + using_multiplicity = True + else: + using_multiplicity = False + + if using_multiplicity: + xsdata.set_scatter( + self.all_mgxs[id]['nu-scatter matrix'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + else: + if 'nu-scatter matrix' in self.mgxs_types: + xsdata.set_scatter( + self.all_mgxs[id]['nu-scatter matrix'], + xs_type=xs_type, subdomains=(i + 1,), + nuclides=[nuclide]) + # Since we are not using multiplicity, then + # scattering multiplication (nu-scatter) must be + # accounted for approximately by using an adjusted + # absorption cross section. + if self.total is not None: + xsdata.absorption = \ + np.subtract(xsdata.total, + np.sum(xsdata.scatter[0, :, :], + axis=1)) + else: + msg = "No nu-scatter matrix data was provided. " +\ + "This means neutron balance cannot be " + \ + "achieved since (n,xn) multiplication is " +\ + "ignored." + warn(msg) + xsdata.set_scatter( + self.all_mgxs[id]['scatter matrix'], + xs_type=xs_type, + subdomains=(i + 1,), + nuclides=[nuclide]) + + xsdatas.append(xsdata) # Add XSdatas to file mgxs_file.add_xsdatas(xsdatas) # Finally, write the file mgxs_file.export_to_xml(full_filename) + + From b35d37c4fbea2d3ac0b5976dc512eae268414f53 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 1 May 2016 20:02:42 -0400 Subject: [PATCH 069/147] Read in AWR data for MGXS Library if available --- src/mgxs_header.F90 | 5 +++++ 1 file changed, 5 insertions(+) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 56c538a5d..b6f8a2b49 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -221,6 +221,11 @@ module mgxs_header else this % zaid = 0 end if + if (check_for_node(node_xsdata, "awr")) then + call get_node_value(node_xsdata, "awr", this % awr) + else + this % awr = -ONE + end if if (check_for_node(node_xsdata, "scatt_type")) then call get_node_value(node_xsdata, "scatt_type", temp_str) temp_str = trim(to_lower(temp_str)) From f20636565a9fe4c83b4594bb833f2e03afefbdf2 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 1 May 2016 21:16:31 -0400 Subject: [PATCH 070/147] Fixed generation of scatter % mult from complicated nuclidic information --- src/mgxs_data.F90 | 2 -- src/mgxs_header.F90 | 80 ++++++++++++++++++++++++++++++++++++++++----- 2 files changed, 71 insertions(+), 11 deletions(-) diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index 04d76f18c..6cf730cfa 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -164,8 +164,6 @@ contains subroutine create_macro_xs() integer :: i_mat ! index in materials array - integer :: i ! loop index over nuclides - integer :: l ! Loop over score bins type(Material), pointer :: mat ! current material integer :: scatt_type diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index b6f8a2b49..7d4ee275d 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -1333,9 +1333,9 @@ module mgxs_header integer :: i ! loop index over nuclides integer :: gin, gout ! group indices real(8) :: atom_density ! atom density of a nuclide - real(8) :: norm + real(8) :: norm, nuscatt integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:) + real(8), allocatable :: temp_mult(:,:), mult_num(:,:), mult_denom(:,:) real(8), allocatable :: scatt_coeffs(:,:,:) ! Set the meta-data @@ -1417,6 +1417,10 @@ module mgxs_header this % chi = ZERO allocate(temp_mult(groups,groups)) temp_mult = ZERO + allocate(mult_num(groups,groups)) + mult_num = ZERO + allocate(mult_denom(groups,groups)) + mult_denom = ZERO allocate(scatt_coeffs(order_dim,groups,groups)) scatt_coeffs = ZERO @@ -1445,10 +1449,24 @@ module mgxs_header end if ! Get the multiplication matrix + ! To combine from nuclidic data we need to use the final relationship + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / + ! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) + ! Developed as follows: + ! mult_{gg'} = nuScatt{g,g'} / Scatt{g,g'} + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / sum(N_i*scatt_{i,g,g'}) + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / + ! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) + ! nuscatt_{i,g,g'} can be reconstructed from scatter % energy and + ! scatter % scattxs do gin = 1, groups do gout = nuc % scatter % gmin(gin), nuc % scatter % gmax(gin) - temp_mult(gout,gin) = temp_mult(gout,gin) + atom_density * & - nuc % scatter % mult(gin) % data(gout) + nuscatt = nuc % scatter % scattxs(gin) * & + nuc % scatter % energy(gin) % data(gout) + mult_num(gout, gin) = mult_num(gout, gin) + atom_density * & + nuscatt + mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * & + nuscatt / nuc % scatter % mult(gin) % data(gout) end do end do @@ -1464,6 +1482,17 @@ module mgxs_header end select end do + ! Obtain temp_mult + do gin = 1, groups + do gout = 1, groups + if (mult_denom(gout, gin) > ZERO) then + temp_mult(gout, gin) = mult_num(gout, gin) / mult_denom(gout, gin) + else + temp_mult(gout, gin) = ONE + end if + end do + end do + ! Initialize the ScattData Object call this % scatter % init(temp_mult,scatt_coeffs) @@ -1478,7 +1507,7 @@ module mgxs_header end if ! Deallocate temporaries - deallocate(scatt_coeffs, temp_mult) + deallocate(scatt_coeffs, temp_mult, mult_num, mult_denom) end subroutine mgxsiso_combine @@ -1496,9 +1525,9 @@ module mgxs_header integer :: gin, gout ! group indices real(8) :: atom_density ! atom density of a nuclide integer :: ipol, iazi, n_pol, n_azi - real(8) :: norm + real(8) :: norm, nuscatt integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:,:,:) + real(8), allocatable :: temp_mult(:,:,:,:), mult_num(:,:,:,:), mult_denom(:,:,:,:) real(8), allocatable :: scatt_coeffs(:,:,:,:,:) ! Set the meta-data @@ -1617,6 +1646,10 @@ module mgxs_header this % chi = ZERO allocate(temp_mult(groups,groups,n_azi,n_pol)) temp_mult = ZERO + allocate(mult_num(groups,groups,n_azi,n_pol)) + mult_num = ZERO + allocate(mult_denom(groups,groups,n_azi,n_pol)) + mult_denom = ZERO allocate(scatt_coeffs(order_dim,groups,groups,n_azi,n_pol)) scatt_coeffs = ZERO @@ -1647,13 +1680,27 @@ module mgxs_header end if ! Get the multiplication matrix + ! To combine from nuclidic data we need to use the final relationship + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / + ! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) + ! Developed as follows: + ! mult_{gg'} = nuScatt{g,g'} / Scatt{g,g'} + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / sum(N_i*scatt_{i,g,g'}) + ! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / + ! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'})) + ! nuscatt_{i,g,g'} can be reconstructed from scatter % energy and + ! scatter % scattxs do ipol = 1, n_pol do iazi = 1, n_azi do gin = 1, groups do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & nuc % scatter(iazi,ipol) % obj % gmax(gin) - temp_mult(gout,gin,iazi,ipol) = temp_mult(gout,gin,iazi,ipol) + & - atom_density * & + nuscatt = nuc % scatter(iazi,ipol) % obj % scattxs(gin) * & + nuc % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + mult_num(gout,gin,iazi,ipol) = mult_num(gout,gin,iazi,ipol) + & + atom_density * nuscatt + mult_denom(gout,gin,iazi,ipol) = mult_denom(gout,gin,iazi,ipol) + & + atom_density * nuscatt / & nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) end do end do @@ -1674,6 +1721,21 @@ module mgxs_header end select end do + ! Obtain temp_mult + do ipol = 1, n_pol + do iazi = 1, n_azi + do gin = 1, groups + do gout = 1, groups + if (mult_denom(gout,gin,iazi,ipol) > ZERO) then + temp_mult(gout,gin,iazi,ipol) = mult_num(gout,gin,iazi,ipol) / mult_denom(gout,gin,iazi,ipol) + else + temp_mult(gout,gin,iazi,ipol) = ONE + end if + end do + end do + end do + end do + ! Initialize the ScattData Object do ipol = 1, n_pol do iazi = 1, n_azi From 2220fb02a7e65d2d03f16d5bbfce6233a24b1259 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 3 May 2016 04:40:59 -0400 Subject: [PATCH 071/147] Added zaid and awr data to summary so that openmc.mgxs.Library can access that information and pass it forward to the outputted microscopic library. --- openmc/mgxs/library.py | 5 +++++ openmc/mgxs_library.py | 36 ++++++++++++++++++++++++++++++++++ openmc/summary.py | 16 +++++++++++++-- src/summary.F90 | 44 ++++++++++++++++++++++++++++++++++++++++++ 4 files changed, 99 insertions(+), 2 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 1e9156ce5..0ceb154b8 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -410,6 +410,7 @@ class Library(object): self._sp_filename = statepoint._f.filename self._openmc_geometry = statepoint.summary.openmc_geometry + self._nuclides = statepoint.summary.nuclides if statepoint.run_mode == 'k-eigenvalue': self._keff = statepoint.k_combined[0] @@ -872,6 +873,10 @@ class Library(object): name += '.' + xs_ids[i] xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order + print(self._nuclides) + print(nuclide) + xsdata.zaid = self._nuclides[nuclide][0] + xsdata.awr = self._nuclides[nuclide][1] # Now get xs data itself if 'total' in self.mgxs_types: diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index ef12c6c8a..9f16888c1 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -204,6 +204,8 @@ class XSdata(object): self._energy_groups = energy_groups self._representation = representation self._alias = None + self._zaid = None + self._awr = None self._kT = None self._fissionable = False self._scatt_type = 'legendre' @@ -237,6 +239,14 @@ class XSdata(object): def alias(self): return self._alias + @property + def zaid(self): + return self._zaid + + @property + def awr(self): + return self._awr + @property def kT(self): return self._kT @@ -334,6 +344,20 @@ class XSdata(object): else: self._alias = self._name + @zaid.setter + def zaid(self, zaid): + # Check type and value + check_type("zaid", zaid, Integral) + check_greater_than("zaid", zaid, 0, equality=False) + self._zaid = zaid + + @awr.setter + def awr(self, awr): + # Check validity of type and that the awr value is > 0 + check_type("awr", awr, Real) + check_greater_than("awr", awr, 0.0, equality=False) + self._awr = awr + @kT.setter def kT(self, kT): # Check validity of type and that the kT value is >= 0 @@ -1092,6 +1116,18 @@ class XSdata(object): subelement = ET.SubElement(element, 'kT') subelement.text = str(self._kT) + if self._zaid is not None: + subelement = ET.SubElement(element, 'zaid') + subelement.text = str(self._zaid) + + if self._awr is not None: + subelement = ET.SubElement(element, 'awr') + subelement.text = str(self._awr) + + if self._kT is not None: + subelement = ET.SubElement(element, 'kT') + subelement.text = str(self._kT) + if self._fissionable is not None: subelement = ET.SubElement(element, 'fissionable') subelement.text = str(self._fissionable) diff --git a/openmc/summary.py b/openmc/summary.py index 9b1c451f3..f33397d72 100644 --- a/openmc/summary.py +++ b/openmc/summary.py @@ -38,6 +38,7 @@ class Summary(object): self._opencg_geometry = None self._read_metadata() + self._read_nuclides() self._read_geometry() self._read_tallies() @@ -55,8 +56,8 @@ class Summary(object): def _read_metadata(self): # Read OpenMC version self.version = [self._f['version_major'].value, - self._f['version_minor'].value, - self._f['version_release'].value] + self._f['version_minor'].value, + self._f['version_release'].value] # Read date and time self.date_and_time = self._f['date_and_time'][...] @@ -70,6 +71,17 @@ class Summary(object): self.gen_per_batch = self._f['gen_per_batch'].value self.n_procs = self._f['n_procs'].value + def _read_nuclides(self): + self.nuclides = {} + n_nuclides = self._f['nuclides/n_nuclides_total'].value + names = self._f['nuclides/names'].value + awrs = self._f['nuclides/awrs'].value + zaids = self._f['nuclides/zaids'].value + for n in range(n_nuclides): + name = names[n].decode() + name = name[:name.find('.')] + self.nuclides[name] = (zaids[n], awrs[n]) + def _read_geometry(self): # Read in and initialize the Materials and Geometry self._read_materials() diff --git a/src/summary.F90 b/src/summary.F90 index 4502058ca..9defcc92f 100644 --- a/src/summary.F90 +++ b/src/summary.F90 @@ -68,6 +68,7 @@ contains "description", "Number of generations per batch") end if + call write_nuclides(file_id) call write_geometry(file_id) call write_materials(file_id) if (n_tallies > 0) then @@ -105,6 +106,49 @@ contains end subroutine write_header +!=============================================================================== +! WRITE_NUCLIDES +!=============================================================================== + + subroutine write_nuclides(file_id) + integer(HID_T), intent(in) :: file_id + integer(HID_T) :: nuclide_group + integer :: i + character(12), allocatable :: nucnames(:) + real(8), allocatable :: awrs(:) + integer, allocatable :: zaids(:) + + ! Use H5LT interface to write useful data from nuclide objects + nuclide_group = create_group(file_id, "nuclides") + call write_dataset(nuclide_group, "n_nuclides_total", n_nuclides_total) + + ! Build array of nuclide names, awrs, and zaids + allocate(nucnames(n_nuclides_total)) + allocate(awrs(n_nuclides_total)) + allocate(zaids(n_nuclides_total)) + do i = 1, n_nuclides_total + if (run_CE) then + nucnames(i) = xs_listings(nuclides(i) % listing) % alias + awrs(i) = nuclides(i) % awr + zaids(i) = nuclides(i) % zaid + else + nucnames(i) = xs_listings(nuclides_MG(i) % obj % listing) % alias + awrs(i) = nuclides_MG(i) % obj % awr + zaids(i) = nuclides_MG(i) % obj % zaid + end if + end do + + ! Write nuclide names, awrs and zaids + call write_dataset(nuclide_group, "names", nucnames) + call write_dataset(nuclide_group, "awrs", awrs) + call write_dataset(nuclide_group, "zaids", zaids) + + call close_group(nuclide_group) + + deallocate(nucnames, awrs, zaids) + + end subroutine write_nuclides + !=============================================================================== ! WRITE_GEOMETRY !=============================================================================== From 879728ea5d5b5b46c1f1b15b87357dc3acfa170c Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 3 May 2016 14:46:52 -0600 Subject: [PATCH 072/147] Add ability to expand natural elements in Python API --- openmc/data/__init__.py | 1 + openmc/data/data.py | 101 ++++++++++++++++++++++++++++++++++++++++ openmc/element.py | 21 +++++++++ openmc/material.py | 29 ++++++++++-- setup.py | 2 +- 5 files changed, 149 insertions(+), 5 deletions(-) create mode 100644 openmc/data/__init__.py create mode 100644 openmc/data/data.py diff --git a/openmc/data/__init__.py b/openmc/data/__init__.py new file mode 100644 index 000000000..df22d8bbb --- /dev/null +++ b/openmc/data/__init__.py @@ -0,0 +1 @@ +from .data import * diff --git a/openmc/data/data.py b/openmc/data/data.py new file mode 100644 index 000000000..c6dd81ba6 --- /dev/null +++ b/openmc/data/data.py @@ -0,0 +1,101 @@ +# Isotopic abundances from M. Berglund and M. E. Wieser, "Isotopic compositions +# of the elements 2009 (IUPAC Technical Report)", Pure. Appl. Chem. 83 (2), +# pp. 397--410 (2011). +natural_abundance = { + 'H-1': 0.999885, 'H-2': 0.000115, 'He-3': 1.34e-06, + 'He-4': 0.99999866, 'Li-6': 0.0759, 'Li-7': 0.9241, + 'Be-9': 1.0, 'B-10': 0.199, 'B-11': 0.801, + 'C-12': 0.9893, 'C-13': 0.0107, 'N-14': 0.99636, + 'N-15': 0.00364, 'O-16': 0.99757, 'O-17': 0.00038, + 'O-18': 0.00205, 'F-19': 1.0, 'Ne-20': 0.9048, + 'Ne-21': 0.0027, 'Ne-22': 0.0925, 'Na-23': 1.0, + 'Mg-24': 0.7899, 'Mg-25': 0.1, 'Mg-26': 0.1101, + 'Al-27': 1.0, 'Si-28': 0.92223, 'Si-29': 0.04685, + 'Si-30': 0.03092, 'P-31': 1.0, 'S-32': 0.9499, + 'S-33': 0.0075, 'S-34': 0.0425, 'S-36': 0.0001, + 'Cl-35': 0.7576, 'Cl-37': 0.2424, 'Ar-36': 0.003336, + 'Ar-38': 0.000629, 'Ar-40': 0.996035, 'K-39': 0.932581, + 'K-40': 0.000117, 'K-41': 0.067302, 'Ca-40': 0.96941, + 'Ca-42': 0.00647, 'Ca-43': 0.00135, 'Ca-44': 0.02086, + 'Ca-46': 4e-05, 'Ca-48': 0.00187, 'Sc-45': 1.0, + 'Ti-46': 0.0825, 'Ti-47': 0.0744, 'Ti-48': 0.7372, + 'Ti-49': 0.0541, 'Ti-50': 0.0518, 'V-50': 0.0025, + 'V-51': 0.9975, 'Cr-50': 0.04345, 'Cr-52': 0.83789, + 'Cr-53': 0.09501, 'Cr-54': 0.02365, 'Mn-55': 1.0, + 'Fe-54': 0.05845, 'Fe-56': 0.91754, 'Fe-57': 0.02119, + 'Fe-58': 0.00282, 'Co-59': 1.0, 'Ni-58': 0.68077, + 'Ni-60': 0.26223, 'Ni-61': 0.011399, 'Ni-62': 0.036346, + 'Ni-64': 0.009255, 'Cu-63': 0.6915, 'Cu-65': 0.3085, + 'Zn-64': 0.4917, 'Zn-66': 0.2773, 'Zn-67': 0.0404, + 'Zn-68': 0.1845, 'Zn-70': 0.0061, 'Ga-69': 0.60108, + 'Ga-71': 0.39892, 'Ge-70': 0.2057, 'Ge-72': 0.2745, + 'Ge-73': 0.0775, 'Ge-74': 0.365, 'Ge-76': 0.0773, + 'As-75': 1.0, 'Se-74': 0.0089, 'Se-76': 0.0937, + 'Se-77': 0.0763, 'Se-78': 0.2377, 'Se-80': 0.4961, + 'Se-82': 0.0873, 'Br-79': 0.5069, 'Br-81': 0.4931, + 'Kr-78': 0.00355, 'Kr-80': 0.02286, 'Kr-82': 0.11593, + 'Kr-83': 0.115, 'Kr-84': 0.56987, 'Kr-86': 0.17279, + 'Rb-85': 0.7217, 'Rb-87': 0.2783, 'Sr-84': 0.0056, + 'Sr-86': 0.0986, 'Sr-87': 0.07, 'Sr-88': 0.8258, + 'Y-89': 1.0, 'Zr-90': 0.5145, 'Zr-91': 0.1122, + 'Zr-92': 0.1715, 'Zr-94': 0.1738, 'Zr-96': 0.028, + 'Nb-93': 1.0, 'Mo-92': 0.1453, 'Mo-94': 0.0915, + 'Mo-95': 0.1584, 'Mo-96': 0.1667, 'Mo-97': 0.096, + 'Mo-98': 0.2439, 'Mo-100': 0.0982, 'Ru-96': 0.0554, + 'Ru-98': 0.0187, 'Ru-99': 0.1276, 'Ru-100': 0.126, + 'Ru-101': 0.1706, 'Ru-102': 0.3155, 'Ru-104': 0.1862, + 'Rh-103': 1.0, 'Pd-102': 0.0102, 'Pd-104': 0.1114, + 'Pd-105': 0.2233, 'Pd-106': 0.2733, 'Pd-108': 0.2646, + 'Pd-110': 0.1172, 'Ag-107': 0.51839, 'Ag-109': 0.48161, + 'Cd-106': 0.0125, 'Cd-108': 0.0089, 'Cd-110': 0.1249, + 'Cd-111': 0.128, 'Cd-112': 0.2413, 'Cd-113': 0.1222, + 'Cd-114': 0.2873, 'Cd-116': 0.0749, 'In-113': 0.0429, + 'In-115': 0.9571, 'Sn-112': 0.0097, 'Sn-114': 0.0066, + 'Sn-115': 0.0034, 'Sn-116': 0.1454, 'Sn-117': 0.0768, + 'Sn-118': 0.2422, 'Sn-119': 0.0859, 'Sn-120': 0.3258, + 'Sn-122': 0.0463, 'Sn-124': 0.0579, 'Sb-121': 0.5721, + 'Sb-123': 0.4279, 'Te-120': 0.0009, 'Te-122': 0.0255, + 'Te-123': 0.0089, 'Te-124': 0.0474, 'Te-125': 0.0707, + 'Te-126': 0.1884, 'Te-128': 0.3174, 'Te-130': 0.3408, + 'I-127': 1.0, 'Xe-124': 0.000952, 'Xe-126': 0.00089, + 'Xe-128': 0.019102, 'Xe-129': 0.264006, 'Xe-130': 0.04071, + 'Xe-131': 0.212324, 'Xe-132': 0.269086, 'Xe-134': 0.104357, + 'Xe-136': 0.088573, 'Cs-133': 1.0, 'Ba-130': 0.00106, + 'Ba-132': 0.00101, 'Ba-134': 0.02417, 'Ba-135': 0.06592, + 'Ba-136': 0.07854, 'Ba-137': 0.11232, 'Ba-138': 0.71698, + 'La-138': 0.0008881, 'La-139': 0.9991119, 'Ce-136': 0.00185, + 'Ce-138': 0.00251, 'Ce-140': 0.8845, 'Ce-142': 0.11114, + 'Pr-141': 1.0, 'Nd-142': 0.27152, 'Nd-143': 0.12174, + 'Nd-144': 0.23798, 'Nd-145': 0.08293, 'Nd-146': 0.17189, + 'Nd-148': 0.05756, 'Nd-150': 0.05638, 'Sm-144': 0.0307, + 'Sm-147': 0.1499, 'Sm-148': 0.1124, 'Sm-149': 0.1382, + 'Sm-150': 0.0738, 'Sm-152': 0.2675, 'Sm-154': 0.2275, + 'Eu-151': 0.4781, 'Eu-153': 0.5219, 'Gd-152': 0.002, + 'Gd-154': 0.0218, 'Gd-155': 0.148, 'Gd-156': 0.2047, + 'Gd-157': 0.1565, 'Gd-158': 0.2484, 'Gd-160': 0.2186, + 'Tb-159': 1.0, 'Dy-156': 0.00056, 'Dy-158': 0.00095, + 'Dy-160': 0.02329, 'Dy-161': 0.18889, 'Dy-162': 0.25475, + 'Dy-163': 0.24896, 'Dy-164': 0.2826, 'Ho-165': 1.0, + 'Er-162': 0.00139, 'Er-164': 0.01601, 'Er-166': 0.33503, + 'Er-167': 0.22869, 'Er-168': 0.26978, 'Er-170': 0.1491, + 'Tm-169': 1.0, 'Yb-168': 0.00123, 'Yb-170': 0.02982, + 'Yb-171': 0.1409, 'Yb-172': 0.2168, 'Yb-173': 0.16103, + 'Yb-174': 0.32026, 'Yb-176': 0.12996, 'Lu-175': 0.97401, + 'Lu-176': 0.02599, 'Hf-174': 0.0016, 'Hf-176': 0.0526, + 'Hf-177': 0.186, 'Hf-178': 0.2728, 'Hf-179': 0.1362, + 'Hf-180': 0.3508, 'Ta-180': 0.0001201, 'Ta-181': 0.9998799, + 'W-180': 0.0012, 'W-182': 0.265, 'W-183': 0.1431, + 'W-184': 0.3064, 'W-186': 0.2843, 'Re-185': 0.374, + 'Re-187': 0.626, 'Os-184': 0.0002, 'Os-186': 0.0159, + 'Os-187': 0.0196, 'Os-188': 0.1324, 'Os-189': 0.1615, + 'Os-190': 0.2626, 'Os-192': 0.4078, 'Ir-191': 0.373, + 'Ir-193': 0.627, 'Pt-190': 0.00012, 'Pt-192': 0.00782, + 'Pt-194': 0.3286, 'Pt-195': 0.3378, 'Pt-196': 0.2521, + 'Pt-198': 0.07356, 'Au-197': 1.0, 'Hg-196': 0.0015, + 'Hg-198': 0.0997, 'Hg-199': 0.1687, 'Hg-200': 0.231, + 'Hg-201': 0.1318, 'Hg-202': 0.2986, 'Hg-204': 0.0687, + 'Tl-203': 0.2952, 'Tl-205': 0.7048, 'Pb-204': 0.014, + 'Pb-206': 0.241, 'Pb-207': 0.221, 'Pb-208': 0.524, + 'Bi-209': 1.0, 'Th-232': 1.0, 'Pa-231': 1.0, + 'U-234': 5.4e-05, 'U-235': 0.007204, 'U-238': 0.992742 +} diff --git a/openmc/element.py b/openmc/element.py index 219aafbdf..39564add4 100644 --- a/openmc/element.py +++ b/openmc/element.py @@ -1,6 +1,8 @@ import sys +import openmc from openmc.checkvalue import check_type +from openmc.data import natural_abundance if sys.version_info[0] >= 3: basestring = str @@ -109,3 +111,22 @@ class Element(object): raise ValueError(msg) self._scattering = scattering + + def expand(self): + """Expand natural element into its naturally-occurring isotopes. + + Returns + ------- + isotopes : list + Naturally-occurring isotopes of the element. Each item of the list + is a tuple consisting of an openmc.Nuclide instance and the natural + abundance of the isotope. + + """ + + isotopes = [] + for isotope, abundance in natural_abundance.items(): + if isotope.startswith(self.name): + nuc = openmc.Nuclide(isotope, self.xs) + isotopes.append((nuc, abundance)) + return isotopes diff --git a/openmc/material.py b/openmc/material.py index b3c281341..c617015a3 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -10,6 +10,7 @@ if sys.version_info[0] >= 3: import openmc import openmc.checkvalue as cv from openmc.clean_xml import * +from openmc.data import natural_abundance # A static variable for auto-generated Material IDs @@ -382,7 +383,7 @@ class Material(object): if macroscopic._name == self._macroscopic.name: self._macroscopic = None - def add_element(self, element, percent, percent_type='ao'): + def add_element(self, element, percent, percent_type='ao', expand=False): """Add a natural element to the material Parameters @@ -391,8 +392,12 @@ class Material(object): Element to add percent : float Atom or weight percent - percent_type : {'ao', 'wo'} - 'ao' for atom percent and 'wo' for weight percent + percent_type : {'ao', 'wo'}, optional + 'ao' for atom percent and 'wo' for weight percent. Defaults to atom + percent. + expand : bool, optional + Whether to expand the natural element into its naturally-occurring + isotopes. Defaults to False. """ @@ -422,7 +427,15 @@ class Material(object): else: element = openmc.Element(element) - self._elements[element._name] = (element, percent, percent_type) + if expand: + if percent_type == 'wo': + raise NotImplementedError('Expanding natural element based on ' + 'weight percent is not yet supported.') + for isotope, abundance in element.expand(): + self._nuclides[isotope.name] = ( + isotope, percent*abundance, percent_type) + else: + self._elements[element.name] = (element, percent, percent_type) def remove_element(self, element): """Remove a natural element from the material @@ -491,6 +504,14 @@ class Material(object): density = nuclide_tuple[1] nuclides[nuclide._name] = (nuclide, density) + for element_name, element_tuple in self._elements.items(): + element = element_tuple[0] + density = element_tuple[1] + + # Expand natural element into isotopes + for isotope, abundance in element.expand(): + nuclides[isotope.name] = (isotope, density*abundance) + return nuclides def _get_nuclide_xml(self, nuclide, distrib=False): diff --git a/setup.py b/setup.py index e66b0b7a0..770f280ad 100644 --- a/setup.py +++ b/setup.py @@ -11,7 +11,7 @@ except ImportError: kwargs = {'name': 'openmc', 'version': '0.7.1', - 'packages': ['openmc', 'openmc.mgxs', 'openmc.stats'], + 'packages': ['openmc', 'openmc.data', 'openmc.mgxs', 'openmc.stats'], 'scripts': glob.glob('scripts/openmc-*'), # Metadata From 7eae7a629d5599f5f157ebf28aa6f9faf89583ba Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 4 May 2016 11:32:23 -0600 Subject: [PATCH 073/147] Add nuclides and elements properties on openmc.Material --- openmc/material.py | 16 ++++++++++++++++ 1 file changed, 16 insertions(+) diff --git a/openmc/material.py b/openmc/material.py index c617015a3..ff690aa9a 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -50,6 +50,14 @@ class Material(object): Units used for `density`. Can be one of 'g/cm3', 'g/cc', 'kg/cm3', 'atom/b-cm', 'atom/cm3', 'sum', or 'macro'. The 'macro' unit only applies in the case of a multi-group calculation. + elements : collections.OrderedDict + Dictionary whose keys are element names and values are 3-tuples + consisting of an :class:`openmc.Element` instance, the percent density, + and the percent type (atom or weight fraction). + nuclides : collections.OrderedDict + Dictionary whose keys are nuclide names and values are 3-tuples + consisting of an :class:`openmc.Nuclide` instance, the percent density, + and the percent type (atom or weight fraction). """ @@ -187,6 +195,14 @@ class Material(object): def density_units(self): return self._density_units + @property + def elements(self): + return self._elements + + @property + def nuclides(self): + return self._nuclides + @property def convert_to_distrib_comps(self): return self._convert_to_distrib_comps From 179e9ab147e505563d118ed58096b3d225160ffa Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 5 May 2016 20:08:42 -0400 Subject: [PATCH 074/147] Added ability to use transport-corrected x/s and cleaned up some comments --- openmc/mgxs/library.py | 144 +++++++++++++++++++++++++++++------------ openmc/mgxs_library.py | 5 +- 2 files changed, 106 insertions(+), 43 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 0ceb154b8..34221f707 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -722,8 +722,9 @@ class Library(object): return pickle.load(open(full_filename, 'rb')) def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, - filename='mg_cross_sections', directory='./'): - """Create a cross-section data library file for the Multi-Group + filename='mg_cross_sections', directory='./', + return_names=True): + """Creates a cross-section data library file for the Multi-Group mode of OpenMC. Parameters @@ -744,6 +745,23 @@ class Library(object): directory : str Directory for the pickle file. Defaults to './' (the current working directory). + return_names : bool + Flag to indicate if the user would like the names of the + materials generated by this function returned with completion. + Defaults to True. + + Returns + ------- + mat_names : Iterable of str + Iterable of material names generated during this routine and + applies to the cross section library. Note this is returned if + the return_names parameter is provided. + + Raises + ------ + ValueError + When the Library object is initialized with insufficient types of + cross sections for the Library. See also -------- @@ -751,14 +769,8 @@ class Library(object): """ - # Check data types provided - + # Check the provided parameters cv.check_value('xs_type', xs_type, ['macro', 'micro']) - # Construct the collection of the nuclides to report - if self.by_nuclide: - nuclides = self.all_mgxs[1][self.mgxs_types[-1]].get_all_nuclides() - else: - xs_type = 'macro' if domain_names is not None: cv.check_iterable_type('domain_names', filename, basestring) if xs_ids is not None: @@ -769,14 +781,19 @@ class Library(object): else: cv.check_iterable_type('xs_ids', xs_ids, basestring) else: - xs_ids = ['1g'] + xs_ids = ['1g' for i in range(len(self.domains))] cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) - # Make directory if it does not exist + # Construct the collection of the nuclides to report + if self.by_nuclide: + nuclides = self.all_mgxs[1][self.mgxs_types[-1]].get_all_nuclides() + else: + xs_type = 'macro' + + # Make directory if it does not exist and build our filename if not os.path.exists(directory): os.makedirs(directory) - full_filename = os.path.join(directory, filename + '.xml') full_filename = full_filename.replace(' ', '-') @@ -784,12 +801,15 @@ class Library(object): mgxs_file = openmc.MGXSLibrary(self.energy_groups) # Set the scattering order as isotropic until - # support for higher orders are included + # support for higher orders are included in openmc.mgxs order = 0 # Build XSdata objects xsdatas = [] + + mat_names = {} for i in range(len(self.domains)): + id = self.domains[i].id if not self.by_nuclide: # Build & add metadata to XSdata object @@ -802,32 +822,46 @@ class Library(object): xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order + mat_names[id] = name + # Now get xs data itself - if 'total' in self.mgxs_types: + if 'transport' in self.mgxs_types: + if self.correction == 'P0': + xsdata.set_total(self.all_mgxs[id]['transport'], + xs_type=xs_type, subdomains=(id,)) + else: + msg = "The use of a transport cross section " + \ + "requires the correction attribute to be" + \ + "set to 'P0' to produce valid cross " + \ + "section libraries" + raise ValueError(msg) + elif 'total' in self.mgxs_types: xsdata.set_total(self.all_mgxs[id]['total'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) if 'absorption' in self.mgxs_types: xsdata.set_absorption(self.all_mgxs[id]['absorption'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, + subdomains=(id,)) if 'fission' in self.mgxs_types: xsdata.set_fission(self.all_mgxs[id]['fission'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) if 'kappa-fission' in self.mgxs_types: xsdata.set_k_fission(self.all_mgxs[id]['kappa-fission'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) if 'chi' in self.mgxs_types: xsdata.set_chi(self.all_mgxs[id]['chi'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) if 'nu-fission' in self.mgxs_types: xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, + subdomains=(id,)) # multiplicity requires scatter and nu-scatter if ((('scatter matrix' in self.mgxs_types) and ('nu-scatter matrix' in self.mgxs_types))): xsdata.set_multiplicity( self.all_mgxs[id]['nu-scatter matrix'], self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) xsdata.multiplicity = np.nan_to_num(xsdata.multiplicity) using_multiplicity = True else: @@ -836,21 +870,29 @@ class Library(object): if using_multiplicity: xsdata.set_scatter(self.all_mgxs[id]['nu-scatter matrix'], xs_type=xs_type, - subdomains=(i + 1,)) + subdomains=(id,)) else: if 'nu-scatter matrix' in self.mgxs_types: xsdata.set_scatter( self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(i + 1,)) + xs_type=xs_type, subdomains=(id,)) # Since we are not using multiplicity, then # scattering multiplication (nu-scatter) must be # accounted for approximately by using an adjusted # absorption cross section. - if self.total is not None: + # We can not do this with a transport x/s so check + # for that. + if 'total' in self.mgxs_types: xsdata.absorption = \ np.subtract(xsdata.total, np.sum(xsdata.scatter[0, :, :], axis=1)) + else: + msg = "Absorption cross section must be " + \ + "provided if using a transport cross" + \ + " section and while not providing a " + \ + "scattering matrix" + raise ValueError(msg) else: msg = "No nu-scatter matrix data was provided. " + \ "This means neutron balance cannot be " + \ @@ -859,10 +901,11 @@ class Library(object): warn(msg) xsdata.set_scatter(self.all_mgxs[id]['scatter matrix'], xs_type=xs_type, - subdomains=(i + 1,)) + subdomains=(id,)) xsdatas.append(xsdata) else: + mat_names[id] = {} for nuclide in nuclides: # Build & add metadata to XSdata object if domain_names is None: @@ -871,41 +914,53 @@ class Library(object): name = domain_names[i] name += '_' + nuclide name += '.' + xs_ids[i] + + mat_names[id][nuclide] = name + xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order - print(self._nuclides) - print(nuclide) xsdata.zaid = self._nuclides[nuclide][0] - xsdata.awr = self._nuclides[nuclide][1] + xsdata.awr = self._nuclides[nuclide][1] # Now get xs data itself - if 'total' in self.mgxs_types: + if 'transport' in self.mgxs_types: + if self.correction == 'P0': + xsdata.set_total(self.all_mgxs[id]['transport'], + xs_type=xs_type, subdomains=(id,), + nuclides=[nuclide]) + else: + msg = "The use of a transport cross section " + \ + "requires the correction attribute to be" + \ + "set to 'P0' to produce valid cross " + \ + "section libraries" + raise ValueError(msg) + elif 'total' in self.mgxs_types: xsdata.set_total(self.all_mgxs[id]['total'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) if 'absorption' in self.mgxs_types: xsdata.set_absorption(self.all_mgxs[id]['absorption'], xs_type=xs_type, - subdomains=(i + 1,), + subdomains=(id,), nuclides=[nuclide]) if 'fission' in self.mgxs_types: xsdata.set_fission(self.all_mgxs[id]['fission'], xs_type=xs_type, - subdomains=(i + 1,), + subdomains=(id,), nuclides=[nuclide]) if 'kappa-fission' in self.mgxs_types: xsdata.set_k_fission( self.all_mgxs[id]['kappa-fission'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) if 'chi' in self.mgxs_types: xsdata.set_chi(self.all_mgxs[id]['chi'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) if 'nu-fission' in self.mgxs_types: xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], xs_type=xs_type, - subdomains=(i + 1,), + subdomains=(id,), nuclides=[nuclide]) # multiplicity requires scatter and nu-scatter if ((('scatter matrix' in self.mgxs_types) and @@ -913,7 +968,7 @@ class Library(object): xsdata.set_multiplicity( self.all_mgxs[id]['nu-scatter matrix'], self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) xsdata.multiplicity = \ np.nan_to_num(xsdata.multiplicity) @@ -924,23 +979,29 @@ class Library(object): if using_multiplicity: xsdata.set_scatter( self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) else: if 'nu-scatter matrix' in self.mgxs_types: xsdata.set_scatter( self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(i + 1,), + xs_type=xs_type, subdomains=(id,), nuclides=[nuclide]) # Since we are not using multiplicity, then # scattering multiplication (nu-scatter) must be # accounted for approximately by using an adjusted # absorption cross section. - if self.total is not None: + if 'total' in self.mgxs_types: xsdata.absorption = \ np.subtract(xsdata.total, np.sum(xsdata.scatter[0, :, :], axis=1)) + else: + msg = "Absorption cross section must be " + \ + "provided if using a transport cross" + \ + " section and while not providing a " + \ + "scattering matrix" + raise ValueError(msg) else: msg = "No nu-scatter matrix data was provided. " +\ "This means neutron balance cannot be " + \ @@ -950,7 +1011,7 @@ class Library(object): xsdata.set_scatter( self.all_mgxs[id]['scatter matrix'], xs_type=xs_type, - subdomains=(i + 1,), + subdomains=(id,), nuclides=[nuclide]) xsdatas.append(xsdata) @@ -961,4 +1022,5 @@ class Library(object): # Finally, write the file mgxs_file.export_to_xml(full_filename) - + if return_names: + return mat_names diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 9f16888c1..bae23b0bc 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -602,10 +602,11 @@ class XSdata(object): self._fissionable = True def set_total(self, total, **kwargs): - if isinstance(total, openmc.mgxs.TotalXS): + if (isinstance(total, openmc.mgxs.TotalXS) or + isinstance(total, openmc.mgxs.TransportXS)): # Make sure passed MGXS object contains correct group structure if self.energy_groups != total.energy_groups: - msg = 'Group structure of provided TotalXS does not match' \ + msg = 'Group structure of provided data does not match' \ ' group structure of XSdata object' raise ValueError(msg) # Get openmc.mgxs.get_xs() arguments from kwargs From ff198abf3a704767f8195e002b8b5a4e6c2b4f04 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 2 May 2016 10:41:45 -0600 Subject: [PATCH 075/147] Improve constructors for Universe and Cell --- openmc/cell.py | 11 ++++++++++- openmc/universe.py | 10 ++++++---- 2 files changed, 16 insertions(+), 5 deletions(-) diff --git a/openmc/cell.py b/openmc/cell.py index ed1f3178b..37828d8fc 100644 --- a/openmc/cell.py +++ b/openmc/cell.py @@ -33,6 +33,10 @@ class Cell(object): automatically be assigned. name : str, optional Name of the cell. If not specified, the name is the empty string. + fill : openmc.Material or openmc.Universe or openmc.Lattice or 'void' or iterable of openmc.Material, optional + Indicates what the region of space is filled with + region : openmc.Region, optional + Region of space that is assigned to the cell. Attributes ---------- @@ -58,7 +62,7 @@ class Cell(object): """ - def __init__(self, cell_id=None, name=''): + def __init__(self, cell_id=None, name='', fill=None, region=None): # Initialize Cell class attributes self.id = cell_id self.name = name @@ -70,6 +74,11 @@ class Cell(object): self._offsets = None self._distribcell_index = None + if fill is not None: + self.fill = fill + if region is not None: + self.region = region + def __eq__(self, other): if not isinstance(other, Cell): return False diff --git a/openmc/universe.py b/openmc/universe.py index eb6d13233..8834eaa52 100644 --- a/openmc/universe.py +++ b/openmc/universe.py @@ -36,6 +36,8 @@ class Universe(object): automatically be assigned name : str, optional Name of the universe. If not specified, the name is the empty string. + cells : Iterable of openmc.Cell + Cells to add to the universe Attributes ---------- @@ -49,7 +51,7 @@ class Universe(object): """ - def __init__(self, universe_id=None, name=''): + def __init__(self, universe_id=None, name='', cells=None): # Initialize Cell class attributes self.id = universe_id self.name = name @@ -61,7 +63,9 @@ class Universe(object): # Keys - Cell IDs # Values - Offsets self._cell_offsets = OrderedDict() - self._num_regions = 0 + + if cells is not None: + self.add_cells(cells) def __eq__(self, other): if not isinstance(other, Universe): @@ -87,8 +91,6 @@ class Universe(object): string += '{0: <16}{1}{2}\n'.format('\tName', '=\t', self._name) string += '{0: <16}{1}{2}\n'.format('\tCells', '=\t', list(self._cells.keys())) - string += '{0: <16}{1}{2}\n'.format('\t# Regions', '=\t', - self._num_regions) return string @property From 744ed3c5f81712416a6144b5a7f598475dc17682 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 2 May 2016 10:42:53 -0600 Subject: [PATCH 076/147] Fix up docstrings for Lattice and its subclasses --- openmc/lattice.py | 24 +++++++++++++++++++----- 1 file changed, 19 insertions(+), 5 deletions(-) diff --git a/openmc/lattice.py b/openmc/lattice.py index baccbad90..f1e775920 100644 --- a/openmc/lattice.py +++ b/openmc/lattice.py @@ -32,11 +32,11 @@ class Lattice(object): Name of the lattice pitch : float Pitch of the lattice in cm - outer : int - The unique identifier of a universe to fill all space outside the - lattice - universes : numpy.ndarray of openmc.Universe - An array of universes filling each element of the lattice + outer : openmc.Universe + A universe to fill all space outside the lattice + universes : Iterable of Iterable of openmc.Universe + A two- or three-dimensional list/array of universes filling each element + of the lattice """ @@ -259,6 +259,13 @@ class RectLattice(Lattice): lower_left : Iterable of float The coordinates of the lower-left corner of the lattice. If the lattice is two-dimensional, only the x- and y-coordinates are specified. + pitch : float + Pitch of the lattice in cm + outer : openmc.Universe + A universe to fill all space outside the lattice + universes : Iterable of Iterable of openmc.Universe + A two- or three-dimensional list/array of universes filling each element + of the lattice """ @@ -505,6 +512,13 @@ class HexLattice(Lattice): center : Iterable of float Coordinates of the center of the lattice. If the lattice does not have axial sections then only the x- and y-coordinates are specified + pitch : float + Pitch of the lattice in cm + outer : openmc.Universe + A universe to fill all space outside the lattice + universes : Iterable of Iterable of openmc.Universe + A two- or three-dimensional list/array of universes filling each element + of the lattice """ From e1a1e081fd7e84c38ed74e1a96f4b02484a056c1 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 2 May 2016 10:50:56 -0600 Subject: [PATCH 077/147] Automatically link summary.h5 by default when present --- openmc/statepoint.py | 25 +++++++++++++++++++++++-- 1 file changed, 23 insertions(+), 2 deletions(-) diff --git a/openmc/statepoint.py b/openmc/statepoint.py index 7b75ac767..6c8af88a7 100644 --- a/openmc/statepoint.py +++ b/openmc/statepoint.py @@ -1,5 +1,6 @@ import sys import re +import os import numpy as np import openmc @@ -14,6 +15,14 @@ class StatePoint(object): of a given batch). Statepoints can be used to analyze tally results as well as restart a simulation. + Parameters + ---------- + filename : str + Path to file to load + autolink : bool, optional + Whether to automatically link in metadata from a summary.h5 + file. Defaults to True. + Attributes ---------- cmfd_on : bool @@ -93,7 +102,7 @@ class StatePoint(object): """ - def __init__(self, filename): + def __init__(self, filename, autolink=True): import h5py self._f = h5py.File(filename, 'r') @@ -116,10 +125,17 @@ class StatePoint(object): # Set flags for what data has been read self._meshes_read = False self._tallies_read = False - self._summary = False + self._summary = None self._global_tallies = None self._sparse = False + # Automatically link in a summary file if one exists + if autolink: + path_summary = os.path.join(os.path.dirname(filename), 'summary.h5') + if os.path.exists(path_summary): + su = openmc.Summary(path_summary) + self.link_with_summary(su) + def close(self): self._f.close() @@ -606,12 +622,17 @@ class StatePoint(object): Raises ------ + RuntimeError + If a Summary object has already been linked. ValueError An error when the argument passed to the 'summary' parameter is not an openmc.Summary object. """ + if self.summary is not None: + raise RuntimeError('A Summary object has already been linked.') + if not isinstance(summary, openmc.summary.Summary): msg = 'Unable to link statepoint with "{0}" which ' \ 'is not a Summary object'.format(summary) From 6558fd8a34032e143a34b9ffdcf06e9acb4ee0a7 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 3 May 2016 10:44:16 -0600 Subject: [PATCH 078/147] Fix reading hexagonal lattices in Summary --- openmc/summary.py | 6 +++--- 1 file changed, 3 insertions(+), 3 deletions(-) diff --git a/openmc/summary.py b/openmc/summary.py index 9b1c451f3..ea13284bd 100644 --- a/openmc/summary.py +++ b/openmc/summary.py @@ -378,11 +378,11 @@ class Summary(object): self.lattices[index] = lattice if lattice_type == 'hexagonal': - n_rings = self._f['geometry/lattices'][key]['n_rings'][0] - n_axial = self._f['geometry/lattices'][key]['n_axial'][0] + n_rings = self._f['geometry/lattices'][key]['n_rings'].value + n_axial = self._f['geometry/lattices'][key]['n_axial'].value center = self._f['geometry/lattices'][key]['center'][...] pitch = self._f['geometry/lattices'][key]['pitch'][...] - outer = self._f['geometry/lattices'][key]['outer'][0] + outer = self._f['geometry/lattices'][key]['outer'].value universe_ids = self._f[ 'geometry/lattices'][key]['universes'][...] From 5947bbefd2f833b03dfb78453cee296810a9ee4f Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 4 May 2016 14:09:12 -0600 Subject: [PATCH 079/147] Don't read eigenvalue-related data in summary.h5 if fixed source --- openmc/summary.py | 7 ++++--- 1 file changed, 4 insertions(+), 3 deletions(-) diff --git a/openmc/summary.py b/openmc/summary.py index ea13284bd..34c51bc51 100644 --- a/openmc/summary.py +++ b/openmc/summary.py @@ -65,9 +65,10 @@ class Summary(object): self.n_batches = self._f['n_batches'].value self.n_particles = self._f['n_particles'].value - self.n_active = self._f['n_active'].value - self.n_inactive = self._f['n_inactive'].value - self.gen_per_batch = self._f['gen_per_batch'].value + if 'n_inactive' in self._f: + self.n_active = self._f['n_active'].value + self.n_inactive = self._f['n_inactive'].value + self.gen_per_batch = self._f['gen_per_batch'].value self.n_procs = self._f['n_procs'].value def _read_geometry(self): From 049b04d99595b4115ce3170dc7c83bec426423f6 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 5 May 2016 13:40:34 -0600 Subject: [PATCH 080/147] Fix tests which autolink summary metadata now --- tests/test_asymmetric_lattice/test_asymmetric_lattice.py | 9 ++------- .../test_mgxs_library_condense.py | 5 ----- .../test_mgxs_library_distribcell.py | 5 ----- tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py | 5 ----- .../test_mgxs_library_no_nuclides.py | 5 ----- .../test_mgxs_library_nuclides.py | 5 ----- tests/test_tally_aggregation/test_tally_aggregation.py | 5 ----- tests/test_tally_arithmetic/test_tally_arithmetic.py | 5 ----- tests/test_tally_slice_merge/test_tally_slice_merge.py | 5 ----- 9 files changed, 2 insertions(+), 47 deletions(-) diff --git a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py index 03e55d32f..504cc4746 100644 --- a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py +++ b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py @@ -82,11 +82,6 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Extract the tally of interest tally = sp.get_tally(name='distribcell tally') @@ -96,8 +91,8 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness): outstr += ', '.join(map(str, tally.std_dev.flatten())) + '\n' # Extract fuel assembly lattices from the summary - core = su.get_cell_by_id(1) - fuel = su.get_cell_by_id(80) + core = sp.summary.get_cell_by_id(1) + fuel = sp.summary.get_cell_by_id(80) fuel = fuel.fill core = core.fill diff --git a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py index 97bb853b6..3ca98904f 100644 --- a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py +++ b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py @@ -43,11 +43,6 @@ class MGXSTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) diff --git a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py index 681266186..d488e8ec9 100644 --- a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py +++ b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py @@ -46,11 +46,6 @@ class MGXSTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) diff --git a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py index 30be46b4c..91bb036e3 100644 --- a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py +++ b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py @@ -44,11 +44,6 @@ class MGXSTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) diff --git a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py index 381b5b87c..15f90cb87 100644 --- a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py +++ b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py @@ -43,11 +43,6 @@ class MGXSTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) diff --git a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py index c3e4f5f77..113f2aa41 100644 --- a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py +++ b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py @@ -43,11 +43,6 @@ class MGXSTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the MGXS library from the statepoint self.mgxs_lib.load_from_statepoint(sp) diff --git a/tests/test_tally_aggregation/test_tally_aggregation.py b/tests/test_tally_aggregation/test_tally_aggregation.py index 359afbe34..fdc086e68 100644 --- a/tests/test_tally_aggregation/test_tally_aggregation.py +++ b/tests/test_tally_aggregation/test_tally_aggregation.py @@ -43,11 +43,6 @@ class TallyAggregationTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Extract the tally of interest tally = sp.get_tally(name='distribcell tally') diff --git a/tests/test_tally_arithmetic/test_tally_arithmetic.py b/tests/test_tally_arithmetic/test_tally_arithmetic.py index 8e2d2b349..a5919909f 100644 --- a/tests/test_tally_arithmetic/test_tally_arithmetic.py +++ b/tests/test_tally_arithmetic/test_tally_arithmetic.py @@ -62,11 +62,6 @@ class TallyArithmeticTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Load the tallies tally_1 = sp.get_tally(name='tally 1') tally_2 = sp.get_tally(name='tally 2') diff --git a/tests/test_tally_slice_merge/test_tally_slice_merge.py b/tests/test_tally_slice_merge/test_tally_slice_merge.py index 85dd532c6..4dbb993d5 100644 --- a/tests/test_tally_slice_merge/test_tally_slice_merge.py +++ b/tests/test_tally_slice_merge/test_tally_slice_merge.py @@ -83,11 +83,6 @@ class TallySliceMergeTestHarness(PyAPITestHarness): statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] sp = openmc.StatePoint(statepoint) - # Read the summary file. - summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] - su = openmc.Summary(summary) - sp.link_with_summary(su) - # Extract the cell tally tallies = [sp.get_tally(name='cell tally')] From 8923e1b8f2731cd21b66088c79916fa1c6ef3ad0 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Thu, 5 May 2016 15:14:26 -0600 Subject: [PATCH 081/147] Update Jupyter notebook examples --- .../pythonapi/examples/mgxs-part-i.ipynb | 124 ++- .../pythonapi/examples/mgxs-part-ii.ipynb | 690 ++++++++--------- .../pythonapi/examples/mgxs-part-iii.ipynb | 206 +++-- .../examples/pandas-dataframes.ipynb | 721 +++++++++--------- .../pythonapi/examples/post-processing.ipynb | 75 +- .../pythonapi/examples/tally-arithmetic.ipynb | 161 ++-- src/output.F90 | 2 +- 7 files changed, 927 insertions(+), 1052 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index a450af97e..610e82ec1 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -417,24 +417,22 @@ "data": { "text/plain": [ "OrderedDict([('flux', Tally\n", - "\tID =\t10000\n", - "\tName =\t\n", - "\tFilters =\t\n", - " \t\tcell\t[1]\n", - " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", - "\tNuclides =\ttotal \n", - "\tScores =\t['flux']\n", - "\tEstimator =\ttracklength\n", - "), ('absorption', Tally\n", - "\tID =\t10001\n", - "\tName =\t\n", - "\tFilters =\t\n", - " \t\tcell\t[1]\n", - " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", - "\tNuclides =\ttotal \n", - "\tScores =\t['absorption']\n", - "\tEstimator =\ttracklength\n", - ")])" + " \tID =\t10000\n", + " \tName =\t\n", + " \tFilters =\t\n", + " \t\tcell\t[1]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", + " \tNuclides =\ttotal \n", + " \tScores =\t['flux']\n", + " \tEstimator =\ttracklength), ('absorption', Tally\n", + " \tID =\t10001\n", + " \tName =\t\n", + " \tFilters =\t\n", + " \t\tcell\t[1]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", + " \tNuclides =\ttotal \n", + " \tScores =\t['absorption']\n", + " \tEstimator =\ttracklength)])" ] }, "execution_count": 13, @@ -508,12 +506,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:24:09\n", - " MPI Processes: 1\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 13:43:54\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -598,20 +595,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.6300E-01 seconds\n", - " Reading cross sections = 1.2100E-01 seconds\n", - " Total time in simulation = 1.6504E+01 seconds\n", - " Time in transport only = 1.6479E+01 seconds\n", - " Time in inactive batches = 1.9620E+00 seconds\n", - " Time in active batches = 1.4542E+01 seconds\n", - " Time synchronizing fission bank = 1.0000E-02 seconds\n", - " Sampling source sites = 4.0000E-03 seconds\n", - " SEND/RECV source sites = 3.0000E-03 seconds\n", + " Total time for initialization = 5.7300E-01 seconds\n", + " Reading cross sections = 1.7600E-01 seconds\n", + " Total time in simulation = 2.1188E+01 seconds\n", + " Time in transport only = 2.1173E+01 seconds\n", + " Time in inactive batches = 2.6880E+00 seconds\n", + " Time in active batches = 1.8500E+01 seconds\n", + " Time synchronizing fission bank = 3.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.6977E+01 seconds\n", - " Calculation Rate (inactive) = 12742.1 neutrons/second\n", - " Calculation Rate (active) = 6876.63 neutrons/second\n", + " Total time elapsed = 2.1776E+01 seconds\n", + " Calculation Rate (inactive) = 9300.60 neutrons/second\n", + " Calculation Rate (active) = 5405.41 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -669,20 +666,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint." - ] - }, - { - "cell_type": "code", - "execution_count": 17, - "metadata": { - "collapsed": false - }, - "outputs": [], - "source": [ - "# Load the summary file and link it with the statepoint\n", - "su = openmc.Summary('summary.h5')\n", - "sp.link_with_summary(su)" + "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. By default, a `Summary` object is automatically linked when a `StatePoint` is loaded. This is necessary for the `openmc.mgxs` module to properly process the tally data." ] }, { @@ -694,7 +678,7 @@ }, { "cell_type": "code", - "execution_count": 18, + "execution_count": 17, "metadata": { "collapsed": false }, @@ -729,7 +713,7 @@ }, { "cell_type": "code", - "execution_count": 19, + "execution_count": 18, "metadata": { "collapsed": false }, @@ -764,7 +748,7 @@ }, { "cell_type": "code", - "execution_count": 20, + "execution_count": 19, "metadata": { "collapsed": false }, @@ -811,7 +795,7 @@ "0 1 2 total 1.292013 0.007642" ] }, - "execution_count": 20, + "execution_count": 19, "metadata": {}, "output_type": "execute_result" } @@ -830,7 +814,7 @@ }, { "cell_type": "code", - "execution_count": 21, + "execution_count": 20, "metadata": { "collapsed": true }, @@ -848,7 +832,7 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 21, "metadata": { "collapsed": false }, @@ -875,7 +859,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 22, "metadata": { "collapsed": false }, @@ -932,7 +916,7 @@ "1 (((total / flux) - (absorption / flux)) - (sca... 1.44e-15 2.57e-03 " ] }, - "execution_count": 23, + "execution_count": 22, "metadata": {}, "output_type": "execute_result" } @@ -954,7 +938,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 23, "metadata": { "collapsed": false }, @@ -1011,7 +995,7 @@ "1 ((absorption / flux) / (total / flux)) 1.93e-02 9.46e-05 " ] }, - "execution_count": 24, + "execution_count": 23, "metadata": {}, "output_type": "execute_result" } @@ -1026,7 +1010,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 24, "metadata": { "collapsed": false }, @@ -1083,7 +1067,7 @@ "1 ((scatter / flux) / (total / flux)) 9.81e-01 3.74e-03 " ] }, - "execution_count": 25, + "execution_count": 24, "metadata": {}, "output_type": "execute_result" } @@ -1105,7 +1089,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 25, "metadata": { "collapsed": false }, @@ -1135,7 +1119,7 @@ " 6.250000e-07\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1\n", + " 1.0\n", " 0.007763\n", " \n", " \n", @@ -1145,7 +1129,7 @@ " 2.000000e+01\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1\n", + " 1.0\n", " 0.003739\n", " \n", " \n", @@ -1162,7 +1146,7 @@ "1 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 3.74e-03 " ] }, - "execution_count": 26, + "execution_count": 25, "metadata": {}, "output_type": "execute_result" } @@ -1178,21 +1162,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index 793d88436..fd8d09052 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -13,7 +13,7 @@ "* The use of **[PyNE](http://pyne.io/) to plot** continuous-energy vs. multi-group cross sections\n", "* **Validation** of multi-group cross sections with **[OpenMOC](https://mit-crpg.github.io/OpenMOC/)**\n", "\n", - "**Note:** This Notebook was created using [OpenMOC](https://mit-crpg.github.io/OpenMOC/) to verify the multi-group cross-sections generated by OpenMC. In order to run this Notebook in its entirety, you must have [OpenMOC](https://mit-crpg.github.io/OpenMOC/) installed on your system, along with OpenCG to convert the OpenMC geometries into OpenMOC geometries. In addition, this Notebook illustrates the use of [Pandas](http://pandas.pydata.org/) `DataFrames` to containerize multi-group cross section data. We recommend using [Pandas](http://pandas.pydata.org/) >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of [Pandas](http://pandas.pydata.org/)." + "**Note:** This Notebook was created using [OpenMOC](https://mit-crpg.github.io/OpenMOC/) to verify the multi-group cross-sections generated by OpenMC. In order to run this Notebook in its entirety, you must have [OpenMOC](https://mit-crpg.github.io/OpenMOC/) installed on your system, along with OpenCG to convert the OpenMC geometries into OpenMOC geometries. In addition, this Notebook illustrates the use of [Pandas](http://pandas.pydata.org/) `DataFrames` to containerize multi-group cross section data." ] }, { @@ -34,16 +34,16 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:884: UserWarning: axes.color_cycle is deprecated and replaced with axes.prop_cycle; please use the latter.\n", - " warnings.warn(self.msg_depr % (key, alt_key))\n", - "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", + "/home/romano/miniconda3/envs/default/lib/python3.5/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", "\n", " warnings.warn(_use_error_msg)\n", - "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:9: QAWarning: pyne.rxname is not yet QA compliant.\n", - "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:9: QAWarning: pyne.ace is not yet QA compliant.\n" + "/home/romano/miniconda3/envs/default/lib/python3.5/importlib/_bootstrap.py:222: QAWarning: pyne.rxname is not yet QA compliant.\n", + " return f(*args, **kwds)\n", + "/home/romano/miniconda3/envs/default/lib/python3.5/importlib/_bootstrap.py:222: QAWarning: pyne.ace is not yet QA compliant.\n", + " return f(*args, **kwds)\n" ] } ], @@ -442,12 +442,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:59:39\n", - " MPI Processes: 1\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 15:00:51\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -523,7 +522,7 @@ " 48/1 1.21610 1.22612 +/- 0.00251\n", " 49/1 1.22199 1.22602 +/- 0.00245\n", " 50/1 1.20860 1.22558 +/- 0.00243\n", - " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10050\n", + " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10056\n", " The estimated number of batches is 73\n", " Creating state point statepoint.050.h5...\n", " 51/1 1.21850 1.22541 +/- 0.00237\n", @@ -549,7 +548,7 @@ " 71/1 1.19720 1.22444 +/- 0.00195\n", " 72/1 1.23770 1.22465 +/- 0.00193\n", " 73/1 1.23894 1.22488 +/- 0.00191\n", - " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10050\n", + " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10056\n", " The estimated number of batches is 74\n", " 74/1 1.22437 1.22487 +/- 0.00188\n", " Triggers satisfied for batch 74\n", @@ -562,20 +561,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.0100E-01 seconds\n", - " Reading cross sections = 8.8000E-02 seconds\n", - " Total time in simulation = 2.3897E+02 seconds\n", - " Time in transport only = 2.3892E+02 seconds\n", - " Time in inactive batches = 1.6456E+01 seconds\n", - " Time in active batches = 2.2251E+02 seconds\n", - " Time synchronizing fission bank = 1.8000E-02 seconds\n", - " Sampling source sites = 1.3000E-02 seconds\n", - " SEND/RECV source sites = 4.0000E-03 seconds\n", + " Total time for initialization = 3.8600E-01 seconds\n", + " Reading cross sections = 1.1000E-01 seconds\n", + " Total time in simulation = 2.3697E+02 seconds\n", + " Time in transport only = 2.3690E+02 seconds\n", + " Time in inactive batches = 1.5640E+01 seconds\n", + " Time in active batches = 2.2133E+02 seconds\n", + " Time synchronizing fission bank = 3.0000E-02 seconds\n", + " Sampling source sites = 1.9000E-02 seconds\n", + " SEND/RECV source sites = 1.1000E-02 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 1.2000E-02 seconds\n", - " Total time elapsed = 2.3943E+02 seconds\n", - " Calculation Rate (inactive) = 6076.81 neutrons/second\n", - " Calculation Rate (active) = 1797.66 neutrons/second\n", + " Total time for finalization = 1.0000E-02 seconds\n", + " Total time elapsed = 2.3743E+02 seconds\n", + " Calculation Rate (inactive) = 6393.86 neutrons/second\n", + " Calculation Rate (active) = 1807.26 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -629,26 +628,6 @@ "sp = openmc.StatePoint('statepoint.074.h5')" ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint." - ] - }, - { - "cell_type": "code", - "execution_count": 16, - "metadata": { - "collapsed": false - }, - "outputs": [], - "source": [ - "# Load the summary file and link it with the statepoint\n", - "su = openmc.Summary('summary.h5')\n", - "sp.link_with_summary(su)" - ] - }, { "cell_type": "markdown", "metadata": {}, @@ -658,7 +637,7 @@ }, { "cell_type": "code", - "execution_count": 17, + "execution_count": 16, "metadata": { "collapsed": false }, @@ -693,7 +672,7 @@ }, { "cell_type": "code", - "execution_count": 18, + "execution_count": 17, "metadata": { "collapsed": false }, @@ -747,7 +726,7 @@ }, { "cell_type": "code", - "execution_count": 19, + "execution_count": 18, "metadata": { "collapsed": false }, @@ -789,7 +768,7 @@ }, { "cell_type": "code", - "execution_count": 20, + "execution_count": 19, "metadata": { "collapsed": false }, @@ -919,7 +898,7 @@ "119 10002 1 5 O-16 0.000000 0.000000" ] }, - "execution_count": 20, + "execution_count": 19, "metadata": {}, "output_type": "execute_result" } @@ -939,7 +918,7 @@ }, { "cell_type": "code", - "execution_count": 21, + "execution_count": 20, "metadata": { "collapsed": true }, @@ -961,7 +940,7 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 21, "metadata": { "collapsed": false }, @@ -1000,7 +979,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 22, "metadata": { "collapsed": false }, @@ -1083,7 +1062,7 @@ "2 10000 2 O-16 3.794859 0.011139" ] }, - "execution_count": 23, + "execution_count": 22, "metadata": {}, "output_type": "execute_result" } @@ -1109,14 +1088,14 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 23, "metadata": { "collapsed": false }, "outputs": [], "source": [ "# Create an OpenMOC Geometry from the OpenCG Geometry\n", - "openmoc_geometry = get_openmoc_geometry(su.opencg_geometry)" + "openmoc_geometry = get_openmoc_geometry(sp.summary.opencg_geometry)" ] }, { @@ -1128,7 +1107,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 24, "metadata": { "collapsed": false }, @@ -1173,7 +1152,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 25, "metadata": { "collapsed": false }, @@ -1187,81 +1166,81 @@ "[ NORMAL ] Iteration 0:\tk_eff = 0.574672\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.679815\tres = 4.253E-01\n", "[ NORMAL ] Iteration 2:\tk_eff = 0.660826\tres = 1.830E-01\n", - "[ NORMAL ] Iteration 3:\tk_eff = 0.658940\tres = 2.793E-02\n", - "[ NORMAL ] Iteration 4:\tk_eff = 0.643012\tres = 2.853E-03\n", + "[ NORMAL ] Iteration 3:\tk_eff = 0.658941\tres = 2.793E-02\n", + "[ NORMAL ] Iteration 4:\tk_eff = 0.643012\tres = 2.852E-03\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.625810\tres = 2.417E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.606678\tres = 2.675E-02\n", "[ NORMAL ] Iteration 7:\tk_eff = 0.587485\tres = 3.057E-02\n", "[ NORMAL ] Iteration 8:\tk_eff = 0.569029\tres = 3.164E-02\n", - "[ NORMAL ] Iteration 9:\tk_eff = 0.551707\tres = 3.142E-02\n", + "[ NORMAL ] Iteration 9:\tk_eff = 0.551708\tres = 3.142E-02\n", "[ NORMAL ] Iteration 10:\tk_eff = 0.536035\tres = 3.044E-02\n", "[ NORMAL ] Iteration 11:\tk_eff = 0.522275\tres = 2.841E-02\n", "[ NORMAL ] Iteration 12:\tk_eff = 0.510610\tres = 2.567E-02\n", - "[ NORMAL ] Iteration 13:\tk_eff = 0.501106\tres = 2.234E-02\n", + "[ NORMAL ] Iteration 13:\tk_eff = 0.501107\tres = 2.233E-02\n", "[ NORMAL ] Iteration 14:\tk_eff = 0.493832\tres = 1.861E-02\n", "[ NORMAL ] Iteration 15:\tk_eff = 0.488781\tres = 1.452E-02\n", "[ NORMAL ] Iteration 16:\tk_eff = 0.485924\tres = 1.023E-02\n", - "[ NORMAL ] Iteration 17:\tk_eff = 0.485211\tres = 5.846E-03\n", - "[ NORMAL ] Iteration 18:\tk_eff = 0.486571\tres = 1.467E-03\n", - "[ NORMAL ] Iteration 19:\tk_eff = 0.489905\tres = 2.802E-03\n", - "[ NORMAL ] Iteration 20:\tk_eff = 0.495105\tres = 6.853E-03\n", + "[ NORMAL ] Iteration 17:\tk_eff = 0.485212\tres = 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get_openmoc_geometry(sp.summary.opencg_geometry)\n", "openmoc_cells = openmoc_geometry.getRootUniverse().getAllCells()\n", "\n", "# Inject multi-group cross sections into OpenMOC Materials\n", @@ -1444,7 +1423,7 @@ }, { "cell_type": "code", - "execution_count": 29, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -1456,14 +1435,14 @@ "[ NORMAL ] Importing ray tracing data from file...\n", "[ NORMAL ] Computing the eigenvalue...\n", "[ NORMAL ] Iteration 0:\tk_eff = 0.495816\tres = 0.000E+00\n", - "[ NORMAL ] Iteration 1:\tk_eff = 0.557477\tres = 5.042E-01\n", + "[ NORMAL ] Iteration 1:\tk_eff = 0.557478\tres = 5.042E-01\n", "[ NORMAL ] Iteration 2:\tk_eff = 0.518301\tres = 1.244E-01\n", "[ NORMAL ] Iteration 3:\tk_eff = 0.509212\tres = 7.027E-02\n", - "[ NORMAL ] Iteration 4:\tk_eff = 0.496489\tres = 1.754E-02\n", + "[ NORMAL ] Iteration 4:\tk_eff = 0.496490\tres = 1.754E-02\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.488581\tres = 2.498E-02\n", "[ NORMAL ] Iteration 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221:\tk_eff = 1.223132\tres = 1.429E-05\n", + "[ NORMAL ] Iteration 222:\tk_eff = 1.223149\tres = 1.394E-05\n", + "[ NORMAL ] Iteration 223:\tk_eff = 1.223165\tres = 1.330E-05\n", + "[ NORMAL ] Iteration 224:\tk_eff = 1.223180\tres = 1.299E-05\n", + "[ NORMAL ] Iteration 225:\tk_eff = 1.223194\tres = 1.241E-05\n", + "[ NORMAL ] Iteration 226:\tk_eff = 1.223208\tres = 1.167E-05\n", + "[ NORMAL ] Iteration 227:\tk_eff = 1.223221\tres = 1.151E-05\n", + "[ NORMAL ] Iteration 228:\tk_eff = 1.223234\tres = 1.073E-05\n", + "[ NORMAL ] Iteration 229:\tk_eff = 1.223246\tres = 1.051E-05\n", + "[ NORMAL ] Iteration 230:\tk_eff = 1.223258\tres = 1.000E-05\n" ] } ], @@ -1701,7 +1680,7 @@ }, { "cell_type": "code", - "execution_count": 30, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -1758,7 +1737,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 30, "metadata": { "collapsed": false }, @@ -1784,7 +1763,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -1795,15 +1774,15 @@ "(9.9999999999999994e-12, 20.0)" ] }, - "execution_count": 32, + "execution_count": 31, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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QJiJHAEOBeSJSCOyS3GKpXGezwaRJzc+lXLvWxpIlmb+bbaKXz6irs7XoeUol\nSizzHO7BWlPpIWPMRhG5C3gmucVSrYEjaCBOuM7pCqDKVsbHg6+nx/SLU1OwFmjpJ3xdk0llqmY/\nkhljZgKHGWPu89YaHjDG3JP8oqnWIJYhr2WeKnq/difV1SkoUIbR5KDSJZZVWScCl4lICfAp8IKI\n3Jb0kqlWIdY5EeVU8eKL+SkoUcskqwZgs2mng0qPWBpzhwD3Ab8HZhtjjkTnPqgEqb1oApu+Wc/G\nDb+G/efv5ZdjaQVND3eClo3SDmiVKWJJDo3GGA9wMvCK95hO21Qp98UXDn75JTvbWVpac2hoyM7X\nq7JfLMlhq4jMAQ4yxnwgIqcAubu8pspY/fs7ef31zKw9JOoTf3AS0T4HlS6xJIdzsEYrneh9XA+M\nTFqJlIpg8GAnr72W/uTw2mt5PPNMYDni6XNwxTG9w2aDqiqorIxtwqDHA198kflDf1Xmi7bwnm8r\n0LOAXYEhIjIK6ExTolAqZU480cnixQ62bk1vOa68sojLLy+Oek60T/x77FFOQ0Nssex2WL/ezpIl\nsbXkLljg4IQTSkOOacJQ8Yr2MawX8DrQL8z3PMD0ZBTIu2f1YKANMM0Y80Yy4qjsU1YG/fo5mTcv\nj+HDnWkrhzWCKPDuH2+zUmMjFBTEEiv69086qYTjjnNyww1WtqkPM69w2LAS9tnHzeLFrXAssGqx\naMnhdQBjzB8ARKS9MWZTS4KIyHTgFGCDMeZgv+OVWCOhHMCjxpi7jTGvAK+IyC7A3wFNDgqwJsnN\nBes389LQ76dq0yB7mA/hX3+dnk/mS5c6cLnYkRyUSpRov9H3Bj1+fifiPA5U+h8QEQcwBWsUVHfg\nbBHp7nfKDd7vq1Ysnn0hfJsGBYu1CWdn/PBD9OQQXAOIVNMIPu4/z+G995pvWvJ4tAdbJUa03+jg\n37IW/9YZYxYCm4MO9wVWG2PWGGMagOeA00TEJiJ/BV43xixpaUyVG+LdOCh406Bt22CvvcpZty75\nN8145zps29b8zfx//2tKCL//fQnnnVeMM4YWtTVrbGGbmJSKVbTkEPzZJtHTc/YEvvd7vM57bAJW\nh/dQEdHtSVu5cJPkJv+rhhNPaIw4Wc6fMdb/q1YlrtknUhKI5abt89NPNrp1Kw/7veOOaxqZtHq1\nI6DW8cYbedTUBJ6/bJmDgw4K7IQ+6qgy7r8/hk4NpSJI/7jAIMaY+4lzv4iKivB/ZMmQq7FSHW9n\nYo0aZe1YgIvuAAAgAElEQVQJUVtbzt57R7/2G94eq9raEioq4ovj8YTvEPY1/ZSUlFPqd092Opti\nOxyOgHIUFgZeo6DAqg3l5wc2FbVvX8bKlYHn7rJLadA55bRrF3jOpk12KirKaeO3dqHLVUhFhRU4\nL8++0z/fbPn90FiJiRctOfwmaK/oDt7HNqw9HsL8WcblB6xhsT57eY/FbePG7TtZlNhUVJTnZKxU\nx0tErNNPL+Rf//Lw5z9bHQr+933/a69aZf1xrF9fx8aNjTFff9EiB2eeWcKGDaHldLvLABtlZXi/\nb8VwOn2xy3G5XGzcaH3Eb2iAefOs5/hs3lwNlNLY6MJ/wYHNm6uAwGY037n+r6+xMfQPf+PG7Wzd\nmgdYw2xrahrYuLEeKOfrr2Hlyip2261lDQDZ9vvR2mPFEq+5xBEtOUgLyxSrxUA3EemClRSGY024\nU6pZ553XyLnnFnP55Q1Rh4SuWgW77+5m+/b4+hyi9VFE6kz2b1ZatcrOuecW8/TTtcydmxeyU5xv\nv4ZYxNqZ3ZwffrC1ODmo1idicvDuGZ0QIvIscDywm4isA242xkwTkUuA+VgfnaYbY5YnKqbKbQcf\n7Gb//d289FL0OQ9ffw29ern59df4kkO0+QXR+hx8z/v1VxtvvpnHmjU2LrwwdMLcqaeGn/H8/POJ\nW3n2wQcL6Ns3d3fbU8mVkj4HY8zZEY7PBWvoulLxuuyyBiZOLGTYsOjJYeRIFxs3xpccoo088v+e\n/6d4pxNqawPPPeqo2EdaAfzlL4XNnvPppw4GDAi96d92WwGHHx5Y8IsuKgp4/O67DqqrbZxySvom\nEarsoHPqVdbq189FmzbwwgvhP+P8+qt1s+7a1U1VVbzJIbZmpeDkMHFiUegTEmz48BJeeSWPjz4K\nPD55cmhiCW6+uvDCYkaNir70h1IQY81BRPoBR2ANZ/3QGPNBUkulVAxsNrjllnrGjSsi3Aaiq1fb\n2X9/a9mN6urk1Bzcbmuimt0OTqctZJhpslx4YTGHHBJ6fNs2nQSnEiOWneBuA/4G7IE1D+F+7+5w\nSqXdkUe6OOyw8O3qS5c66N0bSks9cd+0oyUH/9qC2w15ebDPPp645jmEu1a8li4NPXbFFdFrLrqZ\nkIpVLDWH/sBvjDFuABHJAxYCoesUKJUGd9xRD6+FHl+yxMHxx1vJIZE1h+DkYLdDXp6HxthHyiqV\n8WLpc7D7EgOAMcaJbvajMkinTqEfh51OeOstB5WVUFIC1XEuSBrtE7b/fgy+5OBwxDdDOh7Juq7P\no4/m88kn2v2oAsVSc1giIq8Cb3kfn4Q1R0GpjLR+vY3XX8/jwAPd7LuvnU2b4q85REsO/p3VvlnU\n+fnJu4mvX5+YfoTJk0MnhDz2WD7XXVfEgAFOnnuuNsyzVGsVS3K4DBgGHInVIf0kO7dCq1JJ9X//\nV0qbNh5mzaoF8igtja9DeuLEQkpKYmuctzqkrX6HZCWHRPUT/Pvf+bRpE3ixa64pSmgMlTtiSQ4T\njTF3Yq2aqlTG++qrKhyOpn0XrD6H2J8/bVoBBxwQ2+Qxl8tqUmpps9LHH8eyDHf8143lWlu2NH3t\ncllzIu67r478xM3DU1kslobGg0Rk/6SXRKkEyc8P3JCnsNC6+cXTYRzr8tsulw2Hw+qQTlbNId6l\nwGMl0rS2zsKFebzwQj4bNuhQWGWJpebQC1gpIpuABhK38J5SKWGzQWkp1NRA27aJvbZVc/BkRbMS\nsGONqe+/j5wE/vtfB8uW2Rk7VodftWaxJIchSS+FUknmG87atm18d9pIy3b7BI9WSkbbfTJ2d+vd\nO/yyHh6PtYTH4sUOTQ6tXCzNSqXAOGPMt97F+G4heE1hpTJcrHMdfDd334gkVzNdD03zHKCyMr7V\nVmOVrs7iL77Q4a2tWSw//SkELo43HXggOcVRKjlinevg21rTt4Bec8nB1yGdl2fdwX/+OfuTgy/e\nlCm6k1xrFktyyDPGLPI98P9aqWwRa83BlxR85zbXGew/WimW81silclh6VLHjhFU9fVN78eoUbBp\nk3ZWtyax9DlsE5HxwAKsZFIJpG47I6XiVNGhTeBj4H2AM2J4Lt7N0n3bUu8D7tIyaq6eSO1FE0LO\n929WgmT1OST+mpH84Q9NK7bOmZPPCSfYef/9Gh57DAYMsDNwoO4P0VrEUnP4A9AbmAU8C3TzHlMq\nY7hLk9cNZq+uouRv4ZcS8w1ldTQ/XaHFPvkkiRdvxurV6Yut0qvZmoMxZiMwJgVlUarFaq6eSMnf\n7sJeXZWU6/uuG/wp3jeU9aWXrJljyWhWMkY7hlXqRUwOIjLTGHOWiHyPt6btT+c5qExSe9GEsM0+\nvk3Wr7++kH32cXPhhdGHZ378sZ1Bg0p3PPYQ2M4ePJHO1+dQWdnIvHn5uFzZ3yEdyS+/2AFtVmot\notUcLvX+f0wqCqJUMsXaId3cjnG+0Uw+vj6Ho45yMW9eflImwr3zTkp2823WFVdYC/TtsUeGZCuV\nVNF+60REJMr3v010YZRKltJS2B5mGMWXX9o58MCmtqAtW5pLDoHf99UcCgqaHueaN95o6neoq0tj\nQVRKRUsOC4Avgf9h7d/g/1fhwdrwR6msUFLi4aefQtvujz22lFWrtu9YVmPLFht2uyfiHtINDYGP\ng4eyJnvvhXQ477ySdBdBpUG05HAMcB5wLPAG8JQxZklKSqVUgoVrVvL1H2zb1rSsxpYtNjp29PDj\nj7EnB/+hrLmYHPydfXYJH35YzV13FbBgQR7z56do02yVchGTgzHmfeB977agg4CJIrIf8ALwtHcp\nDaWywi67wC+/BN7wAye8Wclh61Ybu+/u4ccfw1+noSHwGk6nDYfDg8NhPT8ZHdKZZM0aO3/4QxFz\n5ui63rkulqGsTuBV4FURGQj8E/gTsFuSy6ZUwvTo4WLZssKAY7W11o3cf1mNzZttdOzoBkLH91d0\naNM0Sc7ndDgN4H/WrlhsCXla7pnj93WHll0i2sRClRmaHUAtIvuKyE0ishwYB9wIdEp6yZRKoM6d\nPdTV2QLWPvLVHGpqmo5t3Wo1KwHY7R5cJbrGZDJEm1ioMkO0eQ5jgPO95zwF9DPGbE5VwZRKJJsN\nevZ0sWyZnY4drSFFvhVUa/yazTdvtnH44VZyaNfOw3dnX8c+j/8laZPrWjN9TzNbtJrDw8DuWBv8\nDANeEJF3fP9SUjqlEqhnTzdffNHUXBSu5rBli40997SGtrZrB+vOupRN36zHhofzz6vnxReqcdjd\n2PBgw8P0aTUM6N/I9Gk12PBgtzV9r2I3146vc/XfHrtbr3HshfVs3PBrTP9UdojW59AlZaVQKgV6\n9XLx2mtNv/JNNYem5LBtG/Tr5+L++2uZOrUgYN6Cx2ON8y8qaqptNDYGDmX135gnLzPmriVVuOHB\nKjdEG62ko5FUTunZ081f/hJac/DvkK6utrHLLh6GD3fy0EMFAWslbd9u47zzSthjD/eOhOJLDr79\nHPzl+w3oOfxwF0uW5O4idmvWaJLINfoTVa1G165u6upg5Urr1953g/f973Ra8xiKvatW2+2BC+n9\n+KP1PP8hsU6nNWku3KqsyVy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GugNni0h3YC/ge+9p2bHgi1I7oVMnz05tMxruRl5S4uHw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\nCqHJQSmlVAhNDkoppUL8Pzlt5uQccjZkAAAAAElFTkSuQmCC\n", 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s//SZaStbolLd0ZyNidDkt7hJQUQeUNXTRGQ2zn0J4e0AqGonmuHGpEqwvEub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\nMFCsqjsBE3BulItm/z4mpXw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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1845,7 +1824,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 32, "metadata": { "collapsed": false }, @@ -1877,16 +1856,16 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 33, "metadata": { "collapsed": false }, "outputs": [ { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1913,34 +1892,25 @@ "# Show the plot on screen\n", "plt.show()" ] - }, - { - "cell_type": "code", - "execution_count": null, - "metadata": { - "collapsed": true - }, - "outputs": [], - "source": [] } ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 34190371b..c39f21dfa 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -11,7 +11,7 @@ "* **Validation** of multi-group cross sections with **[OpenMOC](https://mit-crpg.github.io/OpenMOC/)**\n", "* Steady-state pin-by-pin **fission rates comparison** between OpenMC and [OpenMOC](https://mit-crpg.github.io/OpenMOC/)\n", "\n", - "**Note:** This Notebook was created using [OpenMOC](https://mit-crpg.github.io/OpenMOC/) to verify the multi-group cross-sections generated by OpenMC. In order to run this Notebook in its entirety, you must have [OpenMOC](https://mit-crpg.github.io/OpenMOC/) installed on your system, along with OpenCG to convert the OpenMC geometries into OpenMOC geometries. In addition, this Notebook illustrates the use of [Pandas](http://pandas.pydata.org/) `DataFrames` to containerize multi-group cross section data. We recommend using [Pandas](http://pandas.pydata.org/) >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of [Pandas](http://pandas.pydata.org/)." + "**Note:** This Notebook was created using [OpenMOC](https://mit-crpg.github.io/OpenMOC/) to verify the multi-group cross-sections generated by OpenMC. In order to run this Notebook in its entirety, you must have [OpenMOC](https://mit-crpg.github.io/OpenMOC/) installed on your system, along with OpenCG to convert the OpenMC geometries into OpenMOC geometries. In addition, this Notebook illustrates the use of [Pandas](http://pandas.pydata.org/) `DataFrames` to containerize multi-group cross section data." ] }, { @@ -32,7 +32,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", + "/home/romano/miniconda3/envs/default/lib/python3.5/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -721,12 +721,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:57:40\n", - " MPI Processes: 1\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 15:06:49\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -812,20 +811,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.3700E-01 seconds\n", - " Reading cross sections = 8.2000E-02 seconds\n", - " Total time in simulation = 4.7745E+01 seconds\n", - " Time in transport only = 4.7726E+01 seconds\n", - " Time in inactive batches = 3.8220E+00 seconds\n", - " Time in active batches = 4.3923E+01 seconds\n", + " Total time for initialization = 4.1500E-01 seconds\n", + " Reading cross sections = 1.1800E-01 seconds\n", + " Total time in simulation = 5.3686E+01 seconds\n", + " Time in transport only = 5.3657E+01 seconds\n", + " Time in inactive batches = 4.3970E+00 seconds\n", + " Time in active batches = 4.9289E+01 seconds\n", " Time synchronizing fission bank = 3.0000E-03 seconds\n", " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 4.8198E+01 seconds\n", - " Calculation Rate (inactive) = 6541.08 neutrons/second\n", - " Calculation Rate (active) = 2276.71 neutrons/second\n", + " Total time elapsed = 5.4118E+01 seconds\n", + " Calculation Rate (inactive) = 5685.70 neutrons/second\n", + " Calculation Rate (active) = 2028.85 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -879,25 +878,6 @@ "sp = openmc.StatePoint('statepoint.50.h5')" ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint." - ] - }, - { - "cell_type": "code", - "execution_count": 28, - "metadata": { - "collapsed": false - }, - "outputs": [], - "source": [ - "su = openmc.Summary('summary.h5')\n", - "sp.link_with_summary(su)" - ] - }, { "cell_type": "markdown", "metadata": {}, @@ -907,7 +887,7 @@ }, { "cell_type": "code", - "execution_count": 29, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -942,7 +922,7 @@ }, { "cell_type": "code", - "execution_count": 30, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -961,7 +941,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 30, "metadata": { "collapsed": false }, @@ -970,7 +950,8 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n" + "/home/romano/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", + " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n" ] }, { @@ -1051,7 +1032,7 @@ "2 10000 2 O-16 0.000000e+00 0.000000e+00" ] }, - "execution_count": 31, + "execution_count": 30, "metadata": {}, "output_type": "execute_result" } @@ -1070,7 +1051,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -1116,7 +1097,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 32, "metadata": { "collapsed": true }, @@ -1135,7 +1116,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 33, "metadata": { "collapsed": true }, @@ -1147,7 +1128,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { "collapsed": true }, @@ -1166,7 +1147,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 35, "metadata": { "collapsed": true }, @@ -1181,7 +1162,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -1237,7 +1218,7 @@ "2 10000 1 O-16 0.000000 0.000000" ] }, - "execution_count": 37, + "execution_count": 36, "metadata": {}, "output_type": "execute_result" } @@ -1266,7 +1247,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 37, "metadata": { "collapsed": false }, @@ -1285,7 +1266,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -1304,7 +1285,7 @@ }, { "cell_type": "code", - "execution_count": 40, + "execution_count": 39, "metadata": { "collapsed": false, "scrolled": true @@ -1318,12 +1299,12 @@ "[ NORMAL ] Computing the eigenvalue...\n", "[ NORMAL ] Iteration 0:\tk_eff = 0.854370\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.801922\tres = 1.521E-01\n", - "[ NORMAL ] Iteration 2:\tk_eff = 0.761746\tres = 6.349E-02\n", + "[ NORMAL ] Iteration 2:\tk_eff = 0.761745\tres = 6.349E-02\n", "[ NORMAL ] Iteration 3:\tk_eff = 0.732367\tres = 5.029E-02\n", "[ NORMAL ] Iteration 4:\tk_eff = 0.711075\tres = 3.869E-02\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.696557\tres = 2.912E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.687673\tres = 2.044E-02\n", - "[ NORMAL ] Iteration 7:\tk_eff = 0.683470\tres = 1.277E-02\n", + "[ NORMAL ] Iteration 7:\tk_eff = 0.683469\tres = 1.277E-02\n", "[ NORMAL ] Iteration 8:\tk_eff = 0.683129\tres = 6.141E-03\n", "[ NORMAL ] Iteration 9:\tk_eff = 0.685949\tres = 7.889E-04\n", "[ NORMAL ] Iteration 10:\tk_eff = 0.691329\tres = 4.181E-03\n", @@ -1336,11 +1317,11 @@ "[ NORMAL ] Iteration 17:\tk_eff = 0.765800\tres = 1.655E-02\n", "[ NORMAL ] Iteration 18:\tk_eff = 0.778371\tres = 1.660E-02\n", "[ NORMAL ] Iteration 19:\tk_eff = 0.790897\tres = 1.643E-02\n", - "[ NORMAL ] Iteration 20:\tk_eff = 0.803273\tres = 1.611E-02\n", - "[ NORMAL ] Iteration 21:\tk_eff = 0.815415\tres = 1.566E-02\n", + "[ NORMAL ] Iteration 20:\tk_eff = 0.803272\tres = 1.611E-02\n", + "[ NORMAL ] Iteration 21:\tk_eff = 0.815414\tres = 1.566E-02\n", "[ NORMAL ] Iteration 22:\tk_eff = 0.827256\tres = 1.513E-02\n", "[ NORMAL ] Iteration 23:\tk_eff = 0.838747\tres = 1.453E-02\n", - "[ NORMAL ] Iteration 24:\tk_eff = 0.849847\tres = 1.390E-02\n", + "[ NORMAL ] Iteration 24:\tk_eff = 0.849846\tres = 1.390E-02\n", "[ NORMAL ] Iteration 25:\tk_eff = 0.860527\tres = 1.324E-02\n", "[ NORMAL ] Iteration 26:\tk_eff = 0.870770\tres = 1.258E-02\n", "[ NORMAL ] Iteration 27:\tk_eff = 0.880562\tres = 1.191E-02\n", @@ -1362,8 +1343,8 @@ "[ NORMAL ] Iteration 43:\tk_eff = 0.981021\tres = 4.104E-03\n", "[ NORMAL ] Iteration 44:\tk_eff = 0.984493\tres = 3.814E-03\n", "[ NORMAL ] Iteration 45:\tk_eff = 0.987729\tres = 3.543E-03\n", - "[ NORMAL ] Iteration 46:\tk_eff = 0.990742\tres = 3.290E-03\n", - "[ NORMAL ] Iteration 47:\tk_eff = 0.993546\tres = 3.053E-03\n", + "[ NORMAL ] Iteration 46:\tk_eff = 0.990741\tres = 3.290E-03\n", + "[ NORMAL ] Iteration 47:\tk_eff = 0.993545\tres = 3.053E-03\n", "[ NORMAL ] Iteration 48:\tk_eff = 0.996153\tres = 2.833E-03\n", "[ NORMAL ] Iteration 49:\tk_eff = 0.998577\tres = 2.627E-03\n", "[ NORMAL ] Iteration 50:\tk_eff = 1.000829\tres = 2.436E-03\n", @@ -1377,63 +1358,63 @@ "[ NORMAL ] Iteration 58:\tk_eff = 1.013868\tres = 1.314E-03\n", "[ NORMAL ] Iteration 59:\tk_eff = 1.015006\tres = 1.215E-03\n", "[ NORMAL ] Iteration 60:\tk_eff = 1.016059\tres = 1.124E-03\n", - "[ NORMAL ] Iteration 61:\tk_eff = 1.017033\tres = 1.039E-03\n", + "[ NORMAL ] Iteration 61:\tk_eff = 1.017033\tres = 1.038E-03\n", "[ NORMAL ] Iteration 62:\tk_eff = 1.017933\tres = 9.596E-04\n", "[ NORMAL ] Iteration 63:\tk_eff = 1.018766\tres = 8.865E-04\n", "[ NORMAL ] Iteration 64:\tk_eff = 1.019535\tres = 8.188E-04\n", - "[ NORMAL ] Iteration 65:\tk_eff = 1.020246\tres = 7.562E-04\n", + "[ NORMAL ] Iteration 65:\tk_eff = 1.020246\tres = 7.561E-04\n", "[ NORMAL ] Iteration 66:\tk_eff = 1.020903\tres = 6.981E-04\n", - "[ NORMAL ] Iteration 67:\tk_eff = 1.021509\tres = 6.445E-04\n", + "[ NORMAL ] Iteration 67:\tk_eff = 1.021509\tres = 6.444E-04\n", "[ NORMAL ] Iteration 68:\tk_eff = 1.022069\tres = 5.948E-04\n", - "[ NORMAL ] Iteration 69:\tk_eff = 1.022586\tres = 5.489E-04\n", + "[ NORMAL ] Iteration 69:\tk_eff = 1.022586\tres = 5.488E-04\n", "[ NORMAL ] Iteration 70:\tk_eff = 1.023063\tres = 5.064E-04\n", "[ NORMAL ] Iteration 71:\tk_eff = 1.023503\tres = 4.671E-04\n", "[ NORMAL ] Iteration 72:\tk_eff = 1.023909\tres = 4.308E-04\n", "[ NORMAL ] Iteration 73:\tk_eff = 1.024284\tres = 3.973E-04\n", "[ NORMAL ] Iteration 74:\tk_eff = 1.024629\tres = 3.663E-04\n", - "[ NORMAL ] Iteration 75:\tk_eff = 1.024948\tres = 3.377E-04\n", + "[ NORMAL ] Iteration 75:\tk_eff = 1.024947\tres = 3.377E-04\n", "[ NORMAL ] Iteration 76:\tk_eff = 1.025241\tres = 3.113E-04\n", "[ NORMAL ] Iteration 77:\tk_eff = 1.025512\tres = 2.869E-04\n", "[ NORMAL ] Iteration 78:\tk_eff = 1.025761\tres = 2.644E-04\n", "[ NORMAL ] Iteration 79:\tk_eff = 1.025991\tres = 2.436E-04\n", "[ NORMAL ] Iteration 80:\tk_eff = 1.026203\tres = 2.244E-04\n", "[ NORMAL ] Iteration 81:\tk_eff = 1.026398\tres = 2.067E-04\n", - "[ NORMAL ] Iteration 82:\tk_eff = 1.026578\tres = 1.904E-04\n", - "[ NORMAL ] Iteration 83:\tk_eff = 1.026743\tres = 1.754E-04\n", + "[ NORMAL ] Iteration 82:\tk_eff = 1.026577\tres = 1.904E-04\n", + "[ NORMAL ] Iteration 83:\tk_eff = 1.026743\tres = 1.753E-04\n", "[ NORMAL ] Iteration 84:\tk_eff = 1.026895\tres = 1.615E-04\n", "[ NORMAL ] Iteration 85:\tk_eff = 1.027036\tres = 1.487E-04\n", "[ NORMAL ] Iteration 86:\tk_eff = 1.027165\tres = 1.369E-04\n", "[ NORMAL ] Iteration 87:\tk_eff = 1.027284\tres = 1.260E-04\n", "[ NORMAL ] Iteration 88:\tk_eff = 1.027393\tres = 1.160E-04\n", - "[ NORMAL ] Iteration 89:\tk_eff = 1.027494\tres = 1.068E-04\n", - "[ NORMAL ] Iteration 90:\tk_eff = 1.027587\tres = 9.825E-05\n", - "[ NORMAL ] Iteration 91:\tk_eff = 1.027672\tres = 9.041E-05\n", - "[ NORMAL ] Iteration 92:\tk_eff = 1.027751\tres = 8.319E-05\n", - "[ NORMAL ] Iteration 93:\tk_eff = 1.027823\tres = 7.654E-05\n", - "[ NORMAL ] Iteration 94:\tk_eff = 1.027889\tres = 7.042E-05\n", - "[ NORMAL ] Iteration 95:\tk_eff = 1.027950\tres = 6.478E-05\n", - "[ NORMAL ] Iteration 96:\tk_eff = 1.028007\tres = 5.959E-05\n", - "[ NORMAL ] Iteration 97:\tk_eff = 1.028058\tres = 5.481E-05\n", - "[ NORMAL ] Iteration 98:\tk_eff = 1.028106\tres = 5.041E-05\n", - "[ NORMAL ] Iteration 99:\tk_eff = 1.028150\tres = 4.636E-05\n", - "[ NORMAL ] Iteration 100:\tk_eff = 1.028190\tres = 4.263E-05\n", - "[ NORMAL ] Iteration 101:\tk_eff = 1.028227\tres = 3.920E-05\n", - "[ NORMAL ] Iteration 102:\tk_eff = 1.028261\tres = 3.604E-05\n", - "[ NORMAL ] Iteration 103:\tk_eff = 1.028292\tres = 3.314E-05\n", - "[ NORMAL ] Iteration 104:\tk_eff = 1.028321\tres = 3.047E-05\n", - "[ NORMAL ] Iteration 105:\tk_eff = 1.028347\tres = 2.801E-05\n", - "[ NORMAL ] Iteration 106:\tk_eff = 1.028371\tres = 2.575E-05\n", - "[ NORMAL ] Iteration 107:\tk_eff = 1.028394\tres = 2.367E-05\n", - "[ NORMAL ] Iteration 108:\tk_eff = 1.028414\tres = 2.175E-05\n", - "[ NORMAL ] Iteration 109:\tk_eff = 1.028433\tres = 1.999E-05\n", - "[ NORMAL ] Iteration 110:\tk_eff = 1.028450\tres = 1.838E-05\n", + "[ NORMAL ] Iteration 89:\tk_eff = 1.027493\tres = 1.067E-04\n", + "[ NORMAL ] Iteration 90:\tk_eff = 1.027586\tres = 9.824E-05\n", + "[ NORMAL ] Iteration 91:\tk_eff = 1.027671\tres = 9.043E-05\n", + "[ NORMAL ] Iteration 92:\tk_eff = 1.027750\tres = 8.318E-05\n", + "[ NORMAL ] Iteration 93:\tk_eff = 1.027822\tres = 7.654E-05\n", + "[ NORMAL ] Iteration 94:\tk_eff = 1.027889\tres = 7.041E-05\n", + "[ NORMAL ] Iteration 95:\tk_eff = 1.027950\tres = 6.481E-05\n", + "[ NORMAL ] Iteration 96:\tk_eff = 1.028006\tres = 5.960E-05\n", + "[ NORMAL ] Iteration 97:\tk_eff = 1.028058\tres = 5.480E-05\n", + "[ NORMAL ] Iteration 98:\tk_eff = 1.028105\tres = 5.043E-05\n", + "[ NORMAL ] Iteration 99:\tk_eff = 1.028149\tres = 4.634E-05\n", + "[ NORMAL ] Iteration 100:\tk_eff = 1.028189\tres = 4.266E-05\n", + "[ NORMAL ] Iteration 101:\tk_eff = 1.028226\tres = 3.920E-05\n", + "[ NORMAL ] Iteration 102:\tk_eff = 1.028260\tres = 3.604E-05\n", + "[ NORMAL ] Iteration 103:\tk_eff = 1.028291\tres = 3.316E-05\n", + "[ NORMAL ] Iteration 104:\tk_eff = 1.028320\tres = 3.047E-05\n", + "[ NORMAL ] Iteration 105:\tk_eff = 1.028347\tres = 2.800E-05\n", + "[ NORMAL ] Iteration 106:\tk_eff = 1.028371\tres = 2.576E-05\n", + "[ NORMAL ] Iteration 107:\tk_eff = 1.028393\tres = 2.367E-05\n", + "[ NORMAL ] Iteration 108:\tk_eff = 1.028414\tres = 2.176E-05\n", + "[ NORMAL ] Iteration 109:\tk_eff = 1.028433\tres = 2.003E-05\n", + "[ NORMAL ] Iteration 110:\tk_eff = 1.028450\tres = 1.836E-05\n", "[ NORMAL ] Iteration 111:\tk_eff = 1.028466\tres = 1.689E-05\n", - "[ NORMAL ] Iteration 112:\tk_eff = 1.028481\tres = 1.552E-05\n", - "[ NORMAL ] Iteration 113:\tk_eff = 1.028494\tres = 1.426E-05\n", - "[ NORMAL ] Iteration 114:\tk_eff = 1.028507\tres = 1.310E-05\n", - "[ NORMAL ] Iteration 115:\tk_eff = 1.028518\tres = 1.204E-05\n", - "[ NORMAL ] Iteration 116:\tk_eff = 1.028528\tres = 1.106E-05\n", - "[ NORMAL ] Iteration 117:\tk_eff = 1.028538\tres = 1.017E-05\n" + "[ NORMAL ] Iteration 112:\tk_eff = 1.028481\tres = 1.553E-05\n", + "[ NORMAL ] Iteration 113:\tk_eff = 1.028494\tres = 1.427E-05\n", + "[ NORMAL ] Iteration 114:\tk_eff = 1.028507\tres = 1.309E-05\n", + "[ NORMAL ] Iteration 115:\tk_eff = 1.028518\tres = 1.202E-05\n", + "[ NORMAL ] Iteration 116:\tk_eff = 1.028528\tres = 1.107E-05\n", + "[ NORMAL ] Iteration 117:\tk_eff = 1.028538\tres = 1.015E-05\n" ] } ], @@ -1456,7 +1437,7 @@ }, { "cell_type": "code", - "execution_count": 41, + "execution_count": 40, "metadata": { "collapsed": false }, @@ -1509,7 +1490,7 @@ }, { "cell_type": "code", - "execution_count": 42, + "execution_count": 41, "metadata": { "collapsed": false }, @@ -1535,7 +1516,7 @@ }, { "cell_type": "code", - "execution_count": 43, + "execution_count": 42, "metadata": { "collapsed": false }, @@ -1567,7 +1548,7 @@ }, { "cell_type": "code", - "execution_count": 44, + "execution_count": 43, "metadata": { "collapsed": false }, @@ -1575,18 +1556,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 44, + "execution_count": 43, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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Mpk37fDP7hZn9q5nt0TKLhJh45NuibRnpglGfBy52dzezvwM+A7yvmfCCxQPH\nvVVN6JsDGgNtsr48LbMtsLLOz0rpqqbVSZHGyEBD49OJ83tH9FRwZ7mhL9C+HiJlMGAVO60PouJ+\nLnymlFHRCPvgVljcqmupZli+fX7huK90rrQuWiWR9tjIulmRBaOqynm0lB5qoaLhsC0gM1JdZfeK\n6JoRkIkEw0i3T3mn9fsrZCZX5D0KLOk/v2hR0/JHFLTdvfjofpmsD6Yp1x09cDzijsgXAnYdmJbZ\nsjgtM6XCC8odkZ2R5dkiHZGJXqZDI3qa0GBjOaJUEfHI8r2rwI4MlNNk1caGjsjAl57dG9A1DIbr\n258rHNexIxLq1xEJ9eqIhBF0RM6dy0Hd3ZXnos0jRqGdz8z2KZx7B9D8a0GI9ka+LWpF8k3bzLqA\nU4BZZvYEcBFwqpmdQPb+tgz44BjaKMSYIN8WdSQZtN29syL7qjGwRYhxRb4t6sj47FyzU0njTqXz\nLwuUEehpsYfSMru8PS3z7psb05Oeh85y70JgksmOB9IycxI9JKFdfSoaK20SWPHuvjRQzqsDMpE2\n5EjPWVWn8Toae2givUcTTLHbYnspXXaZkdKqdub9K/JmNskfikinZ6QNOVJOVYCaESy/SKRTuFX1\nXG6vnlyRl+ruquqo7EfT2IUQokYoaAshRI1Q0BZCiBqhoC2EEDVi3IP2g5FOqjbjwUiPSZvxYGAy\nUrvx4Ja0TDvz2EQbMAKemGgDRkDdbC7POh0t4x60F9cwaC+uYdBeHJnb22YsVtAed+oWAKF+Ni9J\niwwLNY8IIUSNGJ9x2i+bN3D82BJ42WGN5w8IlBFZXCGyTschAZnjSukHlsBxJZsj5QSYlBpAekSg\nkKrFtDYugd8p2BxZVyRyHyKLZRwUkKlaC2X5EjiiYPNQg1X7uf2+gNDYMX3egG9PXrKE6YcN2B9Z\nECkyFD1SDZF1M6rKmbJkCbsddljFmeZExjxHbB5pOSOxObL0Tnn6SKtkJi9Zwk4le1Nr/+50xBHQ\nZO2R5M41o8XMxlaB+K1npDvXjBb5thhrqnx7zIO2EEKI1qE2bSGEqBEK2kIIUSPGNWib2ZvM7CEz\n+7WZfWw8dY8UM1tmZg+Y2f1mVt7Upi0wsyvNbI2Z/bKQN9PMbjKzh83sxnbaNquJvReZ2Qozuy//\ne9NE2jgc5NdjQ938GsbHt8ctaJvZJLKNPs4AjgHeaWZHjZf+UdAHnOLuL3f3+RNtTBOqdhX/OHCL\nux8J3AobYXIlAAABsElEQVRcOO5WNedFswu6/HpMqZtfwzj49ni+ac8HHnH3x919O3At8NZx1D9S\njDZvRmqyq/hbgavz46uBt42rUUPwItsFXX49RtTNr2F8fHs8b9r+NK6ivILhL+U7EThws5ndY2bv\nn2hjhsFsd18D4O5PApGVuSeaOu6CLr8eX+ro19BC327rb9o24WR3nwe8Gfiwmb12og0aIe0+tvPz\nwEvd/QTgSbJd0MXYIb8eP1rq2+MZtFfSOFfugDyvrXH31fn/p4HryX4O14E1ZjYHfrNZbZP9z9sD\nd3/aByYNfBl41UTaMwzk1+NLrfwaWu/b4xm07wEON7ODzWwacC7w/XHUP2zMbBcz2zU/ngG8kfbd\nnbthV3Gyuj0vP34PcMN4G5TgxbILuvx6bKmbX8MY+/b4rD0CuHuvmZ0P3ET2ZXGluy8eL/0jZA5w\nfT5deQrwDXe/aYJtGkSTXcUvA75jZu8FHgfOmTgLG3kx7YIuvx476ubXMD6+rWnsQghRI9QRKYQQ\nNUJBWwghaoSCthBC1AgFbSGEqBEK2kIIUSMUtIUQokYoaAshRI1Q0BZCiBrx314M3U2ye2u1AAAA\nAElFTkSuQmCC\n", "text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1604,34 +1585,25 @@ "plt.imshow(openmoc_fission_rates, interpolation='none', cmap='jet')\n", "plt.title('OpenMOC Fission Rates')" ] - }, - { - "cell_type": "code", - "execution_count": null, - "metadata": { - "collapsed": true - }, - "outputs": [], - "source": [] } ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index d5e8b9861..ea71055a7 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -20,7 +20,7 @@ "%matplotlib inline\n", "import glob\n", "from IPython.display import Image\n", - "import matplotlib.pylab as pylab\n", + "import matplotlib.pyplot as plt\n", "import scipy.stats\n", "import numpy as np\n", "\n", @@ -370,7 +370,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -551,12 +551,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:40:02\n", - " MPI Processes: 1\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 14:39:34\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -619,20 +618,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.7900E-01 seconds\n", - " Reading cross sections = 8.6000E-02 seconds\n", - " Total time in simulation = 8.7310E+00 seconds\n", - " Time in transport only = 8.7200E+00 seconds\n", - " Time in inactive batches = 1.3230E+00 seconds\n", - " Time in active batches = 7.4080E+00 seconds\n", - " Time synchronizing fission bank = 2.0000E-03 seconds\n", - " Sampling source sites = 1.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Total time for initialization = 4.6600E-01 seconds\n", + " Reading cross sections = 1.1100E-01 seconds\n", + " Total time in simulation = 1.1106E+01 seconds\n", + " Time in transport only = 1.1089E+01 seconds\n", + " Time in inactive batches = 1.7090E+00 seconds\n", + " Time in active batches = 9.3970E+00 seconds\n", + " Time synchronizing fission bank = 4.0000E-03 seconds\n", + " Sampling source sites = 3.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 9.1240E+00 seconds\n", - " Calculation Rate (inactive) = 9448.22 neutrons/second\n", - " Calculation Rate (active) = 5062.10 neutrons/second\n", + " Total time elapsed = 1.1590E+01 seconds\n", + " Calculation Rate (inactive) = 7314.22 neutrons/second\n", + " Calculation Rate (active) = 3990.64 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -686,20 +685,6 @@ "sp = openmc.StatePoint(statepoints[-1])" ] }, - { - "cell_type": "code", - "execution_count": 22, - "metadata": { - "collapsed": false, - "scrolled": true - }, - "outputs": [], - "source": [ - "# Load the summary file and link with statepoint\n", - "su = openmc.Summary('summary.h5')\n", - "sp.link_with_summary(su)" - ] - }, { "cell_type": "markdown", "metadata": {}, @@ -709,7 +694,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 22, "metadata": { "collapsed": false }, @@ -725,7 +710,7 @@ " \t\tmesh\t[1]\n", " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'fission', u'nu-fission']\n", + "\tScores =\t['fission', 'nu-fission']\n", "\tEstimator =\ttracklength\n", "\n" ] @@ -748,7 +733,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 23, "metadata": { "collapsed": false }, @@ -757,13 +742,13 @@ "name": "stdout", "output_type": "stream", "text": [ - "[[[ 0.1508711 ]]\n", + "[[[ 0.1501735 ]]\n", "\n", - " [[ 0.05389822]]\n", + " [[ 0.05936257]]\n", "\n", - " [[ 0.19633 ]]\n", + " [[ 0.21402727]]\n", "\n", - " [[ 0.12963172]]]\n" + " [[ 0.13436703]]]\n" ] } ], @@ -778,7 +763,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 24, "metadata": { "collapsed": false }, @@ -819,8 +804,8 @@ " 0.00e+00\n", " 6.25e-07\n", " fission\n", - " 2.34e-04\n", - " 3.54e-05\n", + " 2.20e-04\n", + " 3.31e-05\n", " \n", " \n", " 1\n", @@ -830,8 +815,8 @@ " 0.00e+00\n", " 6.25e-07\n", " nu-fission\n", - " 5.71e-04\n", - " 8.62e-05\n", + " 5.37e-04\n", + " 8.06e-05\n", " \n", " \n", " 2\n", @@ -841,8 +826,8 @@ " 6.25e-07\n", " 2.00e+01\n", " fission\n", - " 7.03e-05\n", - " 7.05e-06\n", + " 7.43e-05\n", + " 7.91e-06\n", " \n", " \n", " 3\n", @@ -852,8 +837,8 @@ " 6.25e-07\n", " 2.00e+01\n", " nu-fission\n", - " 1.87e-04\n", - " 1.76e-05\n", + " 1.97e-04\n", + " 1.96e-05\n", " \n", " \n", " 4\n", @@ -863,8 +848,8 @@ " 0.00e+00\n", " 6.25e-07\n", " fission\n", - " 3.67e-04\n", - " 3.61e-05\n", + " 3.52e-04\n", + " 3.39e-05\n", " \n", " \n", " 5\n", @@ -874,8 +859,8 @@ " 0.00e+00\n", " 6.25e-07\n", " nu-fission\n", - " 8.94e-04\n", - " 8.80e-05\n", + " 8.57e-04\n", + " 8.26e-05\n", " \n", " \n", " 6\n", @@ -885,8 +870,8 @@ " 6.25e-07\n", " 2.00e+01\n", " fission\n", - " 1.04e-04\n", - " 5.36e-06\n", + " 1.02e-04\n", + " 6.16e-06\n", " \n", " \n", " 7\n", @@ -896,8 +881,8 @@ " 6.25e-07\n", " 2.00e+01\n", " nu-fission\n", - " 2.76e-04\n", - " 1.40e-05\n", + " 2.70e-04\n", + " 1.61e-05\n", " \n", " \n", " 8\n", @@ -907,8 +892,8 @@ " 0.00e+00\n", " 6.25e-07\n", " fission\n", - " 6.04e-04\n", - " 5.57e-05\n", + " 6.09e-04\n", + " 6.55e-05\n", " \n", " \n", " 9\n", @@ -918,8 +903,8 @@ " 0.00e+00\n", " 6.25e-07\n", " nu-fission\n", - " 1.47e-03\n", - " 1.36e-04\n", + " 1.48e-03\n", + " 1.60e-04\n", " \n", " \n", " 10\n", @@ -929,8 +914,8 @@ " 6.25e-07\n", " 2.00e+01\n", " fission\n", - " 1.41e-04\n", - " 6.69e-06\n", + " 1.38e-04\n", + " 6.74e-06\n", " \n", " \n", " 11\n", @@ -940,8 +925,8 @@ " 6.25e-07\n", " 2.00e+01\n", " nu-fission\n", - " 3.72e-04\n", - " 1.82e-05\n", + " 3.65e-04\n", + " 1.88e-05\n", " \n", " \n", " 12\n", @@ -951,8 +936,8 @@ " 0.00e+00\n", " 6.25e-07\n", " fission\n", - " 6.45e-04\n", - " 4.59e-05\n", + " 6.23e-04\n", + " 5.16e-05\n", " \n", " \n", " 13\n", @@ -962,8 +947,8 @@ " 0.00e+00\n", " 6.25e-07\n", " nu-fission\n", - " 1.57e-03\n", - " 1.12e-04\n", + " 1.52e-03\n", + " 1.26e-04\n", " \n", " \n", " 14\n", @@ -973,8 +958,8 @@ " 6.25e-07\n", " 2.00e+01\n", " fission\n", - " 1.82e-04\n", - " 9.37e-06\n", + " 1.74e-04\n", + " 9.99e-06\n", " \n", " \n", " 15\n", @@ -984,8 +969,8 @@ " 6.25e-07\n", " 2.00e+01\n", " nu-fission\n", - " 4.76e-04\n", - " 2.47e-05\n", + " 4.58e-04\n", + " 2.68e-05\n", " \n", " \n", " 16\n", @@ -995,8 +980,8 @@ " 0.00e+00\n", " 6.25e-07\n", " fission\n", - " 7.28e-04\n", - " 7.49e-05\n", + " 6.94e-04\n", + " 8.68e-05\n", " \n", " \n", " 17\n", @@ -1006,8 +991,8 @@ " 0.00e+00\n", " 6.25e-07\n", " nu-fission\n", - " 1.77e-03\n", - " 1.83e-04\n", + " 1.69e-03\n", + " 2.12e-04\n", " \n", " \n", " 18\n", @@ -1017,8 +1002,8 @@ " 6.25e-07\n", " 2.00e+01\n", " fission\n", - " 1.81e-04\n", - " 1.04e-05\n", + " 1.75e-04\n", + " 1.10e-05\n", " \n", " \n", " 19\n", @@ -1028,8 +1013,8 @@ " 6.25e-07\n", " 2.00e+01\n", " nu-fission\n", - " 4.72e-04\n", - " 2.67e-05\n", + " 4.55e-04\n", + " 2.80e-05\n", " \n", " \n", "\n", @@ -1038,52 +1023,52 @@ "text/plain": [ " mesh 1 energy low [MeV] energy high [MeV] score mean \\\n", " x y z \n", - "0 1 1 1 0.00e+00 6.25e-07 fission 2.34e-04 \n", - "1 1 1 1 0.00e+00 6.25e-07 nu-fission 5.71e-04 \n", - "2 1 1 1 6.25e-07 2.00e+01 fission 7.03e-05 \n", - "3 1 1 1 6.25e-07 2.00e+01 nu-fission 1.87e-04 \n", - "4 1 2 1 0.00e+00 6.25e-07 fission 3.67e-04 \n", - "5 1 2 1 0.00e+00 6.25e-07 nu-fission 8.94e-04 \n", - "6 1 2 1 6.25e-07 2.00e+01 fission 1.04e-04 \n", - "7 1 2 1 6.25e-07 2.00e+01 nu-fission 2.76e-04 \n", - "8 1 3 1 0.00e+00 6.25e-07 fission 6.04e-04 \n", - "9 1 3 1 0.00e+00 6.25e-07 nu-fission 1.47e-03 \n", - "10 1 3 1 6.25e-07 2.00e+01 fission 1.41e-04 \n", - "11 1 3 1 6.25e-07 2.00e+01 nu-fission 3.72e-04 \n", - "12 1 4 1 0.00e+00 6.25e-07 fission 6.45e-04 \n", - "13 1 4 1 0.00e+00 6.25e-07 nu-fission 1.57e-03 \n", - "14 1 4 1 6.25e-07 2.00e+01 fission 1.82e-04 \n", - "15 1 4 1 6.25e-07 2.00e+01 nu-fission 4.76e-04 \n", - "16 1 5 1 0.00e+00 6.25e-07 fission 7.28e-04 \n", - "17 1 5 1 0.00e+00 6.25e-07 nu-fission 1.77e-03 \n", - "18 1 5 1 6.25e-07 2.00e+01 fission 1.81e-04 \n", - "19 1 5 1 6.25e-07 2.00e+01 nu-fission 4.72e-04 \n", + "0 1 1 1 0.00e+00 6.25e-07 fission 2.20e-04 \n", + "1 1 1 1 0.00e+00 6.25e-07 nu-fission 5.37e-04 \n", + "2 1 1 1 6.25e-07 2.00e+01 fission 7.43e-05 \n", + "3 1 1 1 6.25e-07 2.00e+01 nu-fission 1.97e-04 \n", + "4 1 2 1 0.00e+00 6.25e-07 fission 3.52e-04 \n", + "5 1 2 1 0.00e+00 6.25e-07 nu-fission 8.57e-04 \n", + "6 1 2 1 6.25e-07 2.00e+01 fission 1.02e-04 \n", + "7 1 2 1 6.25e-07 2.00e+01 nu-fission 2.70e-04 \n", + "8 1 3 1 0.00e+00 6.25e-07 fission 6.09e-04 \n", + "9 1 3 1 0.00e+00 6.25e-07 nu-fission 1.48e-03 \n", + "10 1 3 1 6.25e-07 2.00e+01 fission 1.38e-04 \n", + "11 1 3 1 6.25e-07 2.00e+01 nu-fission 3.65e-04 \n", + "12 1 4 1 0.00e+00 6.25e-07 fission 6.23e-04 \n", + "13 1 4 1 0.00e+00 6.25e-07 nu-fission 1.52e-03 \n", + "14 1 4 1 6.25e-07 2.00e+01 fission 1.74e-04 \n", + "15 1 4 1 6.25e-07 2.00e+01 nu-fission 4.58e-04 \n", + "16 1 5 1 0.00e+00 6.25e-07 fission 6.94e-04 \n", + "17 1 5 1 0.00e+00 6.25e-07 nu-fission 1.69e-03 \n", + "18 1 5 1 6.25e-07 2.00e+01 fission 1.75e-04 \n", + "19 1 5 1 6.25e-07 2.00e+01 nu-fission 4.55e-04 \n", "\n", " std. dev. \n", " \n", - "0 3.54e-05 \n", - "1 8.62e-05 \n", - "2 7.05e-06 \n", - "3 1.76e-05 \n", - "4 3.61e-05 \n", - "5 8.80e-05 \n", - "6 5.36e-06 \n", - "7 1.40e-05 \n", - "8 5.57e-05 \n", - "9 1.36e-04 \n", - "10 6.69e-06 \n", - "11 1.82e-05 \n", - "12 4.59e-05 \n", - "13 1.12e-04 \n", - "14 9.37e-06 \n", - "15 2.47e-05 \n", - "16 7.49e-05 \n", - "17 1.83e-04 \n", - "18 1.04e-05 \n", - "19 2.67e-05 " + "0 3.31e-05 \n", + "1 8.06e-05 \n", + "2 7.91e-06 \n", + "3 1.96e-05 \n", + "4 3.39e-05 \n", + "5 8.26e-05 \n", + "6 6.16e-06 \n", + "7 1.61e-05 \n", + "8 6.55e-05 \n", + "9 1.60e-04 \n", + "10 6.74e-06 \n", + "11 1.88e-05 \n", + "12 5.16e-05 \n", + "13 1.26e-04 \n", + "14 9.99e-06 \n", + "15 2.68e-05 \n", + "16 8.68e-05 \n", + "17 2.12e-04 \n", + "18 1.10e-05 \n", + "19 2.80e-05 " ] }, - "execution_count": 25, + "execution_count": 24, "metadata": {}, "output_type": "execute_result" } @@ -1102,16 +1087,16 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 25, "metadata": { "collapsed": false }, "outputs": [ { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1126,7 +1111,7 @@ }, { "cell_type": "code", - "execution_count": 27, + "execution_count": 26, "metadata": { "collapsed": false }, @@ -1134,18 +1119,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 27, + "execution_count": 26, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1160,11 +1145,11 @@ "# Extract mean and reshape as 2D NumPy arrays\n", "mean = fiss['mean'].reshape((17,17))\n", "\n", - "pylab.imshow(mean, interpolation='nearest')\n", - "pylab.title('fission rate')\n", - "pylab.xlabel('x')\n", - "pylab.ylabel('y')\n", - "pylab.colorbar()" + "plt.imshow(mean, interpolation='nearest')\n", + "plt.title('fission rate')\n", + "plt.xlabel('x')\n", + "plt.ylabel('y')\n", + "plt.colorbar()" ] }, { @@ -1176,7 +1161,7 @@ }, { "cell_type": "code", - "execution_count": 28, + "execution_count": 27, "metadata": { "collapsed": false }, @@ -1191,7 +1176,7 @@ "\tFilters =\t\n", " \t\tcell\t[10000]\n", "\tNuclides =\tU-235 U-238 \n", - "\tScores =\t[u'scatter-Y0,0', u'scatter-Y1,-1', u'scatter-Y1,0', u'scatter-Y1,1', u'scatter-Y2,-2', u'scatter-Y2,-1', u'scatter-Y2,0', u'scatter-Y2,1', u'scatter-Y2,2']\n", + "\tScores =\t['scatter-Y0,0', 'scatter-Y1,-1', 'scatter-Y1,0', 'scatter-Y1,1', 'scatter-Y2,-2', 'scatter-Y2,-1', 'scatter-Y2,0', 'scatter-Y2,1', 'scatter-Y2,2']\n", "\tEstimator =\tanalog\n", "\n" ] @@ -1207,7 +1192,7 @@ }, { "cell_type": "code", - "execution_count": 29, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -1233,144 +1218,144 @@ " 10000\n", " U-235\n", " scatter-Y0,0\n", - " 3.86e-02\n", - " 1.11e-03\n", + " 3.84e-02\n", + " 1.32e-03\n", " \n", " \n", " 1\n", " 10000\n", " U-235\n", " scatter-Y1,-1\n", - " 2.75e-04\n", - " 2.96e-04\n", + " 3.61e-04\n", + " 3.13e-04\n", " \n", " \n", " 2\n", " 10000\n", " U-235\n", " scatter-Y1,0\n", - " -5.55e-05\n", - " 4.33e-04\n", + " -2.38e-04\n", + " 4.69e-04\n", " \n", " \n", " 3\n", " 10000\n", " U-235\n", " scatter-Y1,1\n", - " -4.22e-04\n", - " 3.51e-04\n", + " -5.08e-04\n", + " 3.83e-04\n", " \n", " \n", " 4\n", " 10000\n", " U-235\n", " scatter-Y2,-2\n", - " 5.88e-05\n", - " 2.04e-04\n", + " 6.68e-05\n", + " 2.46e-04\n", " \n", " \n", " 5\n", " 10000\n", " U-235\n", " scatter-Y2,-1\n", - " 1.00e-04\n", - " 2.49e-04\n", + " 6.47e-06\n", + " 2.84e-04\n", " \n", " \n", " 6\n", " 10000\n", " U-235\n", " scatter-Y2,0\n", - " -8.09e-05\n", - " 1.59e-04\n", + " -1.41e-04\n", + " 1.75e-04\n", " \n", " \n", " 7\n", " 10000\n", " U-235\n", " scatter-Y2,1\n", - " 1.93e-04\n", - " 2.14e-04\n", + " 1.61e-04\n", + " 2.33e-04\n", " \n", " \n", " 8\n", " 10000\n", " U-235\n", " scatter-Y2,2\n", - " 1.12e-04\n", - " 1.86e-04\n", + " -1.80e-05\n", + " 1.97e-04\n", " \n", " \n", " 9\n", " 10000\n", " U-238\n", " scatter-Y0,0\n", - " 2.34e+00\n", - " 1.34e-02\n", + " 2.33e+00\n", + " 1.35e-02\n", " \n", " \n", " 10\n", " 10000\n", " U-238\n", " scatter-Y1,-1\n", - " 2.32e-02\n", - " 2.97e-03\n", + " 2.53e-02\n", + " 3.23e-03\n", " \n", " \n", " 11\n", " 10000\n", " U-238\n", " scatter-Y1,0\n", - " 7.50e-04\n", - " 2.55e-03\n", + " 7.10e-04\n", + " 2.92e-03\n", " \n", " \n", " 12\n", " 10000\n", " U-238\n", " scatter-Y1,1\n", - " -2.73e-02\n", - " 3.28e-03\n", + " -2.49e-02\n", + " 3.52e-03\n", " \n", " \n", " 13\n", " 10000\n", " U-238\n", " scatter-Y2,-2\n", - " -2.36e-03\n", - " 1.21e-03\n", + " -1.43e-03\n", + " 1.17e-03\n", " \n", " \n", " 14\n", " 10000\n", " U-238\n", " scatter-Y2,-1\n", - " -1.80e-04\n", - " 1.49e-03\n", + " 6.84e-04\n", + " 1.63e-03\n", " \n", " \n", " 15\n", " 10000\n", " U-238\n", " scatter-Y2,0\n", - " 3.23e-03\n", - " 2.25e-03\n", + " 2.85e-03\n", + " 2.63e-03\n", " \n", " \n", " 16\n", " 10000\n", " U-238\n", " scatter-Y2,1\n", - " 3.75e-03\n", - " 1.97e-03\n", + " 3.97e-03\n", + " 2.24e-03\n", " \n", " \n", " 17\n", " 10000\n", " U-238\n", " scatter-Y2,2\n", - " 2.07e-03\n", - " 1.60e-03\n", + " 2.26e-03\n", + " 1.85e-03\n", " \n", " \n", "\n", @@ -1378,27 +1363,27 @@ ], "text/plain": [ " cell nuclide score mean std. dev.\n", - "0 10000 U-235 scatter-Y0,0 3.86e-02 1.11e-03\n", - "1 10000 U-235 scatter-Y1,-1 2.75e-04 2.96e-04\n", - "2 10000 U-235 scatter-Y1,0 -5.55e-05 4.33e-04\n", - "3 10000 U-235 scatter-Y1,1 -4.22e-04 3.51e-04\n", - "4 10000 U-235 scatter-Y2,-2 5.88e-05 2.04e-04\n", - "5 10000 U-235 scatter-Y2,-1 1.00e-04 2.49e-04\n", - "6 10000 U-235 scatter-Y2,0 -8.09e-05 1.59e-04\n", - "7 10000 U-235 scatter-Y2,1 1.93e-04 2.14e-04\n", - "8 10000 U-235 scatter-Y2,2 1.12e-04 1.86e-04\n", - "9 10000 U-238 scatter-Y0,0 2.34e+00 1.34e-02\n", - "10 10000 U-238 scatter-Y1,-1 2.32e-02 2.97e-03\n", - "11 10000 U-238 scatter-Y1,0 7.50e-04 2.55e-03\n", - "12 10000 U-238 scatter-Y1,1 -2.73e-02 3.28e-03\n", - "13 10000 U-238 scatter-Y2,-2 -2.36e-03 1.21e-03\n", - "14 10000 U-238 scatter-Y2,-1 -1.80e-04 1.49e-03\n", - "15 10000 U-238 scatter-Y2,0 3.23e-03 2.25e-03\n", - "16 10000 U-238 scatter-Y2,1 3.75e-03 1.97e-03\n", - "17 10000 U-238 scatter-Y2,2 2.07e-03 1.60e-03" + "0 10000 U-235 scatter-Y0,0 3.84e-02 1.32e-03\n", + "1 10000 U-235 scatter-Y1,-1 3.61e-04 3.13e-04\n", + "2 10000 U-235 scatter-Y1,0 -2.38e-04 4.69e-04\n", + "3 10000 U-235 scatter-Y1,1 -5.08e-04 3.83e-04\n", + "4 10000 U-235 scatter-Y2,-2 6.68e-05 2.46e-04\n", + "5 10000 U-235 scatter-Y2,-1 6.47e-06 2.84e-04\n", + "6 10000 U-235 scatter-Y2,0 -1.41e-04 1.75e-04\n", + "7 10000 U-235 scatter-Y2,1 1.61e-04 2.33e-04\n", + "8 10000 U-235 scatter-Y2,2 -1.80e-05 1.97e-04\n", + "9 10000 U-238 scatter-Y0,0 2.33e+00 1.35e-02\n", + "10 10000 U-238 scatter-Y1,-1 2.53e-02 3.23e-03\n", + "11 10000 U-238 scatter-Y1,0 7.10e-04 2.92e-03\n", + "12 10000 U-238 scatter-Y1,1 -2.49e-02 3.52e-03\n", + "13 10000 U-238 scatter-Y2,-2 -1.43e-03 1.17e-03\n", + "14 10000 U-238 scatter-Y2,-1 6.84e-04 1.63e-03\n", + "15 10000 U-238 scatter-Y2,0 2.85e-03 2.63e-03\n", + "16 10000 U-238 scatter-Y2,1 3.97e-03 2.24e-03\n", + "17 10000 U-238 scatter-Y2,2 2.26e-03 1.85e-03" ] }, - "execution_count": 29, + "execution_count": 28, "metadata": {}, "output_type": "execute_result" } @@ -1420,7 +1405,7 @@ }, { "cell_type": "code", - "execution_count": 30, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -1429,8 +1414,8 @@ "name": "stdout", "output_type": "stream", "text": [ - "[[[ 0.00159927 0.01341406]\n", - " [ 0.00018637 0.00111048]]]\n" + "[[[ 0.00185463 0.01350521]\n", + " [ 0.00019723 0.00131654]]]\n" ] } ], @@ -1451,7 +1436,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 30, "metadata": { "collapsed": false }, @@ -1466,7 +1451,7 @@ "\tFilters =\t\n", " \t\tdistribcell\t[10002]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'absorption', u'scatter']\n", + "\tScores =\t['absorption', 'scatter']\n", "\tEstimator =\ttracklength\n", "\n" ] @@ -1489,7 +1474,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -1498,7 +1483,7 @@ "name": "stdout", "output_type": "stream", "text": [ - "[[[ 0.05767856]]]\n" + "[[[ 0.05468423]]]\n" ] } ], @@ -1519,7 +1504,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 32, "metadata": { "collapsed": false }, @@ -1543,141 +1528,141 @@ " 558\n", " 279\n", " absorption\n", - " 8.19e-05\n", - " 7.82e-06\n", + " 8.72e-05\n", + " 8.13e-06\n", " \n", " \n", " 559\n", " 279\n", " scatter\n", - " 1.33e-02\n", - " 6.19e-04\n", + " 1.37e-02\n", + " 6.98e-04\n", " \n", " \n", " 560\n", " 280\n", " absorption\n", - " 1.00e-04\n", - " 7.93e-06\n", + " 1.03e-04\n", + " 9.17e-06\n", " \n", " \n", " 561\n", " 280\n", " scatter\n", - " 1.40e-02\n", - " 5.61e-04\n", + " 1.41e-02\n", + " 6.26e-04\n", " \n", " \n", " 562\n", " 281\n", " absorption\n", - " 9.52e-05\n", - " 7.08e-06\n", + " 9.41e-05\n", + " 8.40e-06\n", " \n", " \n", " 563\n", " 281\n", " scatter\n", - " 1.51e-02\n", - " 6.50e-04\n", + " 1.50e-02\n", + " 6.92e-04\n", " \n", " \n", " 564\n", " 282\n", " absorption\n", - " 9.85e-05\n", - " 9.47e-06\n", + " 9.56e-05\n", + " 1.03e-05\n", " \n", " \n", " 565\n", " 282\n", " scatter\n", - " 1.53e-02\n", - " 4.63e-04\n", + " 1.52e-02\n", + " 5.37e-04\n", " \n", " \n", " 566\n", " 283\n", " absorption\n", - " 1.08e-04\n", - " 1.34e-05\n", + " 1.06e-04\n", + " 1.49e-05\n", " \n", " \n", " 567\n", " 283\n", " scatter\n", - " 1.65e-02\n", - " 7.04e-04\n", + " 1.64e-02\n", + " 8.14e-04\n", " \n", " \n", " 568\n", " 284\n", " absorption\n", - " 1.13e-04\n", - " 7.91e-06\n", + " 1.16e-04\n", + " 9.02e-06\n", " \n", " \n", " 569\n", " 284\n", " scatter\n", - " 1.67e-02\n", - " 5.51e-04\n", + " 1.64e-02\n", + " 6.00e-04\n", " \n", " \n", " 570\n", " 285\n", " absorption\n", - " 1.23e-04\n", - " 9.53e-06\n", + " 1.25e-04\n", + " 1.12e-05\n", " \n", " \n", " 571\n", " 285\n", " scatter\n", - " 1.88e-02\n", - " 7.25e-04\n", + " 1.87e-02\n", + " 8.26e-04\n", " \n", " \n", " 572\n", " 286\n", " absorption\n", - " 1.44e-04\n", - " 1.34e-05\n", + " 1.47e-04\n", + " 1.49e-05\n", " \n", " \n", " 573\n", " 286\n", " scatter\n", - " 1.90e-02\n", - " 7.07e-04\n", + " 1.94e-02\n", + " 7.71e-04\n", " \n", " \n", " 574\n", " 287\n", " absorption\n", - " 1.26e-04\n", - " 8.66e-06\n", + " 1.31e-04\n", + " 9.84e-06\n", " \n", " \n", " 575\n", " 287\n", " scatter\n", " 1.97e-02\n", - " 7.23e-04\n", + " 7.93e-04\n", " \n", " \n", " 576\n", " 288\n", " absorption\n", - " 1.25e-04\n", - " 9.59e-06\n", + " 1.23e-04\n", + " 1.07e-05\n", " \n", " \n", " 577\n", " 288\n", " scatter\n", - " 2.01e-02\n", - " 6.75e-04\n", + " 1.97e-02\n", + " 7.34e-04\n", " \n", " \n", "\n", @@ -1685,29 +1670,29 @@ ], "text/plain": [ " distribcell score mean std. dev.\n", - "558 279 absorption 8.19e-05 7.82e-06\n", - "559 279 scatter 1.33e-02 6.19e-04\n", - "560 280 absorption 1.00e-04 7.93e-06\n", - "561 280 scatter 1.40e-02 5.61e-04\n", - "562 281 absorption 9.52e-05 7.08e-06\n", - "563 281 scatter 1.51e-02 6.50e-04\n", - "564 282 absorption 9.85e-05 9.47e-06\n", - "565 282 scatter 1.53e-02 4.63e-04\n", - "566 283 absorption 1.08e-04 1.34e-05\n", - "567 283 scatter 1.65e-02 7.04e-04\n", - "568 284 absorption 1.13e-04 7.91e-06\n", - "569 284 scatter 1.67e-02 5.51e-04\n", - "570 285 absorption 1.23e-04 9.53e-06\n", - "571 285 scatter 1.88e-02 7.25e-04\n", - "572 286 absorption 1.44e-04 1.34e-05\n", - "573 286 scatter 1.90e-02 7.07e-04\n", - "574 287 absorption 1.26e-04 8.66e-06\n", - "575 287 scatter 1.97e-02 7.23e-04\n", - "576 288 absorption 1.25e-04 9.59e-06\n", - "577 288 scatter 2.01e-02 6.75e-04" + "558 279 absorption 8.72e-05 8.13e-06\n", + "559 279 scatter 1.37e-02 6.98e-04\n", + "560 280 absorption 1.03e-04 9.17e-06\n", + "561 280 scatter 1.41e-02 6.26e-04\n", + "562 281 absorption 9.41e-05 8.40e-06\n", + "563 281 scatter 1.50e-02 6.92e-04\n", + "564 282 absorption 9.56e-05 1.03e-05\n", + "565 282 scatter 1.52e-02 5.37e-04\n", + "566 283 absorption 1.06e-04 1.49e-05\n", + "567 283 scatter 1.64e-02 8.14e-04\n", + "568 284 absorption 1.16e-04 9.02e-06\n", + "569 284 scatter 1.64e-02 6.00e-04\n", + "570 285 absorption 1.25e-04 1.12e-05\n", + "571 285 scatter 1.87e-02 8.26e-04\n", + "572 286 absorption 1.47e-04 1.49e-05\n", + "573 286 scatter 1.94e-02 7.71e-04\n", + "574 287 absorption 1.31e-04 9.84e-06\n", + "575 287 scatter 1.97e-02 7.93e-04\n", + "576 288 absorption 1.23e-04 1.07e-05\n", + "577 288 scatter 1.97e-02 7.34e-04" ] }, - "execution_count": 33, + "execution_count": 32, "metadata": {}, "output_type": "execute_result" } @@ -1729,7 +1714,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 33, "metadata": { "collapsed": false }, @@ -1791,8 +1776,8 @@ " 10000\n", " 279\n", " absorption\n", - " 8.19e-05\n", - " 7.82e-06\n", + " 8.72e-05\n", + " 8.13e-06\n", " \n", " \n", " 559\n", @@ -1806,8 +1791,8 @@ " 10000\n", " 279\n", " scatter\n", - " 1.33e-02\n", - " 6.19e-04\n", + " 1.37e-02\n", + " 6.98e-04\n", " \n", " \n", " 560\n", @@ -1821,8 +1806,8 @@ " 10000\n", " 280\n", " absorption\n", - " 1.00e-04\n", - " 7.93e-06\n", + " 1.03e-04\n", + " 9.17e-06\n", " \n", " \n", " 561\n", @@ -1836,8 +1821,8 @@ " 10000\n", " 280\n", " scatter\n", - " 1.40e-02\n", - " 5.61e-04\n", + " 1.41e-02\n", + " 6.26e-04\n", " \n", " \n", " 562\n", @@ -1851,8 +1836,8 @@ " 10000\n", " 281\n", " absorption\n", - " 9.52e-05\n", - " 7.08e-06\n", + " 9.41e-05\n", + " 8.40e-06\n", " \n", " \n", " 563\n", @@ -1866,8 +1851,8 @@ " 10000\n", " 281\n", " scatter\n", - " 1.51e-02\n", - " 6.50e-04\n", + " 1.50e-02\n", + " 6.92e-04\n", " \n", " \n", " 564\n", @@ -1881,8 +1866,8 @@ " 10000\n", " 282\n", " absorption\n", - " 9.85e-05\n", - " 9.47e-06\n", + " 9.56e-05\n", + " 1.03e-05\n", " \n", " \n", " 565\n", @@ -1896,8 +1881,8 @@ " 10000\n", " 282\n", " scatter\n", - " 1.53e-02\n", - " 4.63e-04\n", + " 1.52e-02\n", + " 5.37e-04\n", " \n", " \n", " 566\n", @@ -1911,8 +1896,8 @@ " 10000\n", " 283\n", " absorption\n", - " 1.08e-04\n", - " 1.34e-05\n", + " 1.06e-04\n", + " 1.49e-05\n", " \n", " \n", " 567\n", @@ -1926,8 +1911,8 @@ " 10000\n", " 283\n", " scatter\n", - " 1.65e-02\n", - " 7.04e-04\n", + " 1.64e-02\n", + " 8.14e-04\n", " \n", " \n", " 568\n", @@ -1941,8 +1926,8 @@ " 10000\n", " 284\n", " absorption\n", - " 1.13e-04\n", - " 7.91e-06\n", + " 1.16e-04\n", + " 9.02e-06\n", " \n", " \n", " 569\n", @@ -1956,8 +1941,8 @@ " 10000\n", " 284\n", " scatter\n", - " 1.67e-02\n", - " 5.51e-04\n", + " 1.64e-02\n", + " 6.00e-04\n", " \n", " \n", " 570\n", @@ -1971,8 +1956,8 @@ " 10000\n", " 285\n", " absorption\n", - " 1.23e-04\n", - " 9.53e-06\n", + " 1.25e-04\n", + " 1.12e-05\n", " \n", " \n", " 571\n", @@ -1986,8 +1971,8 @@ " 10000\n", " 285\n", " scatter\n", - " 1.88e-02\n", - " 7.25e-04\n", + " 1.87e-02\n", + " 8.26e-04\n", " \n", " \n", " 572\n", @@ -2001,8 +1986,8 @@ " 10000\n", " 286\n", " absorption\n", - " 1.44e-04\n", - " 1.34e-05\n", + " 1.47e-04\n", + " 1.49e-05\n", " \n", " \n", " 573\n", @@ -2016,8 +2001,8 @@ " 10000\n", " 286\n", " scatter\n", - " 1.90e-02\n", - " 7.07e-04\n", + " 1.94e-02\n", + " 7.71e-04\n", " \n", " \n", " 574\n", @@ -2031,8 +2016,8 @@ " 10000\n", " 287\n", " absorption\n", - " 1.26e-04\n", - " 8.66e-06\n", + " 1.31e-04\n", + " 9.84e-06\n", " \n", " \n", " 575\n", @@ -2047,7 +2032,7 @@ " 287\n", " scatter\n", " 1.97e-02\n", - " 7.23e-04\n", + " 7.93e-04\n", " \n", " \n", " 576\n", @@ -2061,8 +2046,8 @@ " 10000\n", " 288\n", " absorption\n", - " 1.25e-04\n", - " 9.59e-06\n", + " 1.23e-04\n", + " 1.07e-05\n", " \n", " \n", " 577\n", @@ -2076,8 +2061,8 @@ " 10000\n", " 288\n", " scatter\n", - " 2.01e-02\n", - " 6.75e-04\n", + " 1.97e-02\n", + " 7.34e-04\n", " \n", " \n", "\n", @@ -2111,36 +2096,36 @@ " mean std. dev. \n", " \n", " \n", - "558 8.19e-05 7.82e-06 \n", - "559 1.33e-02 6.19e-04 \n", - "560 1.00e-04 7.93e-06 \n", - "561 1.40e-02 5.61e-04 \n", - "562 9.52e-05 7.08e-06 \n", - "563 1.51e-02 6.50e-04 \n", - "564 9.85e-05 9.47e-06 \n", - "565 1.53e-02 4.63e-04 \n", - "566 1.08e-04 1.34e-05 \n", - "567 1.65e-02 7.04e-04 \n", - "568 1.13e-04 7.91e-06 \n", - "569 1.67e-02 5.51e-04 \n", - "570 1.23e-04 9.53e-06 \n", - "571 1.88e-02 7.25e-04 \n", - "572 1.44e-04 1.34e-05 \n", - "573 1.90e-02 7.07e-04 \n", - "574 1.26e-04 8.66e-06 \n", - "575 1.97e-02 7.23e-04 \n", - "576 1.25e-04 9.59e-06 \n", - "577 2.01e-02 6.75e-04 " + "558 8.72e-05 8.13e-06 \n", + "559 1.37e-02 6.98e-04 \n", + "560 1.03e-04 9.17e-06 \n", + "561 1.41e-02 6.26e-04 \n", + "562 9.41e-05 8.40e-06 \n", + "563 1.50e-02 6.92e-04 \n", + "564 9.56e-05 1.03e-05 \n", + "565 1.52e-02 5.37e-04 \n", + "566 1.06e-04 1.49e-05 \n", + "567 1.64e-02 8.14e-04 \n", + "568 1.16e-04 9.02e-06 \n", + "569 1.64e-02 6.00e-04 \n", + "570 1.25e-04 1.12e-05 \n", + "571 1.87e-02 8.26e-04 \n", + "572 1.47e-04 1.49e-05 \n", + "573 1.94e-02 7.71e-04 \n", + "574 1.31e-04 9.84e-06 \n", + "575 1.97e-02 7.93e-04 \n", + "576 1.23e-04 1.07e-05 \n", + "577 1.97e-02 7.34e-04 " ] }, - "execution_count": 34, + "execution_count": 33, "metadata": {}, "output_type": "execute_result" } ], "source": [ "# Get a pandas dataframe for the distribcell tally data\n", - "df = tally.get_pandas_dataframe(summary=su, nuclides=False)\n", + "df = tally.get_pandas_dataframe(summary=sp.summary, nuclides=False)\n", "\n", "# Print the last twenty rows in the dataframe\n", "df.tail(20)" @@ -2148,7 +2133,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { "collapsed": false }, @@ -2183,38 +2168,38 @@ " \n", " \n", " mean\n", - " 4.19e-04\n", - " 2.24e-05\n", + " 4.16e-04\n", + " 2.42e-05\n", " \n", " \n", " std\n", - " 2.42e-04\n", - " 9.14e-06\n", + " 2.39e-04\n", + " 1.03e-05\n", " \n", " \n", " min\n", " 1.90e-05\n", - " 3.44e-06\n", + " 3.80e-06\n", " \n", " \n", " 25%\n", - " 2.02e-04\n", - " 1.56e-05\n", + " 1.99e-04\n", + " 1.61e-05\n", " \n", " \n", " 50%\n", - " 4.05e-04\n", - " 2.20e-05\n", + " 4.09e-04\n", + " 2.37e-05\n", " \n", " \n", " 75%\n", - " 6.07e-04\n", - " 2.89e-05\n", + " 6.00e-04\n", + " 3.08e-05\n", " \n", " \n", " max\n", - " 9.19e-04\n", - " 4.95e-05\n", + " 9.07e-04\n", + " 5.38e-05\n", " \n", " \n", "\n", @@ -2225,16 +2210,16 @@ " \n", " \n", "count 2.89e+02 2.89e+02\n", - "mean 4.19e-04 2.24e-05\n", - "std 2.42e-04 9.14e-06\n", - "min 1.90e-05 3.44e-06\n", - "25% 2.02e-04 1.56e-05\n", - "50% 4.05e-04 2.20e-05\n", - "75% 6.07e-04 2.89e-05\n", - "max 9.19e-04 4.95e-05" + "mean 4.16e-04 2.42e-05\n", + "std 2.39e-04 1.03e-05\n", + "min 1.90e-05 3.80e-06\n", + "25% 1.99e-04 1.61e-05\n", + "50% 4.09e-04 2.37e-05\n", + "75% 6.00e-04 3.08e-05\n", + "max 9.07e-04 5.38e-05" ] }, - "execution_count": 35, + "execution_count": 34, "metadata": {}, "output_type": "execute_result" } @@ -2257,7 +2242,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -2266,7 +2251,7 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 0.303583331507\n" + "Mann-Whitney Test p-value: 0.7234916721800682\n" ] } ], @@ -2295,7 +2280,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -2304,7 +2289,7 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 6.038663783e-42\n" + "Mann-Whitney Test p-value: 3.5054120724573393e-41\n" ] } ], @@ -2331,7 +2316,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 37, "metadata": { "collapsed": false }, @@ -2340,7 +2325,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:4: SettingWithCopyWarning: \n", + "/home/romano/miniconda3/envs/default/lib/python3.5/site-packages/ipykernel/__main__.py:4: SettingWithCopyWarning: \n", "A value is trying to be set on a copy of a slice from a DataFrame.\n", "Try using .loc[row_indexer,col_indexer] = value instead\n", "\n", @@ -2350,18 +2335,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 38, + "execution_count": 37, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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MTGiGAH7z1Nx9921cf/3ClHDa9u3bLcxmGMagkveqMyM3JM9TEw+ndXQkhtOam5t9l7e1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\nyRsDKQZIfYpODDv5Ee+Ily6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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2380,7 +2365,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -2388,18 +2373,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 39, + "execution_count": 38, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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DlnoznkkeyJPJ/qpSks3oorJstUPi00rHX03uFWEkUtbX3oa7Sn7FgYX/j5ML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\nlcvmVCblU7lsLlvKpCE+qXx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WDt9JxAMVCEm4Wetn0a1FN98xJBo/NYbvgPYTfScRD1QgJOFmrZvFSS10BXWl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\nEpEKhIiIRPT/Abz6PSTJ+oGTAAAAAElFTkSuQmCC\n", "text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2410,29 +2395,29 @@ "# Plot a histogram and kernel density estimate for the scattering rates\n", "scatter['mean'].plot(kind='hist', bins=25)\n", "scatter['mean'].plot(kind='kde')\n", - "pylab.title('Scattering Rates')\n", - "pylab.xlabel('Mean')\n", - "pylab.legend(['KDE', 'Histogram'])" + "plt.title('Scattering Rates')\n", + "plt.xlabel('Mean')\n", + "plt.legend(['KDE', 'Histogram'])" ] } ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/post-processing.ipynb b/docs/source/pythonapi/examples/post-processing.ipynb index 36cf63c6a..de92c2bcb 100644 --- a/docs/source/pythonapi/examples/post-processing.ipynb +++ b/docs/source/pythonapi/examples/post-processing.ipynb @@ -339,7 +339,7 @@ "outputs": [ { "data": { - "image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAAAFzUkdC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\nVDExOjMyOjU1LTA0OjAwoL4U5gAAAABJRU5ErkJggg==\n", + "image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\n1kHjAQAAAABJRU5ErkJggg==\n", "text/plain": [ "" ] @@ -445,12 +445,11 @@ " 888\n", " 888\n", "\n", - " Copyright: 2011-2015 Massachusetts Institute of Technology\n", - " License: http://mit-crpg.github.io/openmc/license.html\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: eeb5091ca3a34cc85df73a3318cae2b6c7097413\n", - " Date/Time: 2016-04-13 11:32:56\n", - " MPI Processes: 1\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 14:41:55\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -586,20 +585,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.8100E-01 seconds\n", - " Reading cross sections = 8.6000E-02 seconds\n", - " Total time in simulation = 2.4400E+02 seconds\n", - " Time in transport only = 2.4395E+02 seconds\n", - " Time in inactive batches = 8.3260E+00 seconds\n", - " Time in active batches = 2.3567E+02 seconds\n", - " Time synchronizing fission bank = 1.6000E-02 seconds\n", - " Sampling source sites = 6.0000E-03 seconds\n", - " SEND/RECV source sites = 7.0000E-03 seconds\n", + " Total time for initialization = 4.4900E-01 seconds\n", + " Reading cross sections = 1.2100E-01 seconds\n", + " Total time in simulation = 3.4132E+02 seconds\n", + " Time in transport only = 3.4128E+02 seconds\n", + " Time in inactive batches = 1.0748E+01 seconds\n", + " Time in active batches = 3.3057E+02 seconds\n", + " Time synchronizing fission bank = 1.1000E-02 seconds\n", + " Sampling source sites = 1.1000E-02 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", " Time accumulating tallies = 1.9000E-02 seconds\n", - " Total time for finalization = 1.7400E-01 seconds\n", - " Total time elapsed = 2.4458E+02 seconds\n", - " Calculation Rate (inactive) = 6005.28 neutrons/second\n", - " Calculation Rate (active) = 1909.46 neutrons/second\n", + " Total time for finalization = 1.5600E-01 seconds\n", + " Total time elapsed = 3.4196E+02 seconds\n", + " Calculation Rate (inactive) = 4652.03 neutrons/second\n", + " Calculation Rate (active) = 1361.27 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -674,11 +673,11 @@ "text": [ "Tally\n", "\tID =\t10000\n", - "\tName =\t\n", + "\tName =\tflux\n", "\tFilters =\t\n", " \t\tmesh\t[10000]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'flux', u'fission']\n", + "\tScores =\t['flux', 'fission']\n", "\tEstimator =\ttracklength\n", "\n" ] @@ -809,11 +808,11 @@ "text": [ "Tally\n", "\tID =\t10001\n", - "\tName =\t\n", + "\tName =\tflux\n", "\tFilters =\t\n", " \t\tmesh\t[10000]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'flux']\n", + "\tScores =\t['flux']\n", "\tEstimator =\ttracklength\n", "\n" ] @@ -856,7 +855,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 24, @@ -865,9 +864,9 @@ }, { "data": { - "image/png": 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dHYwxnwF+tv9cfcZSuEhS5aY53cGpqRLyYEtZLtFQm9jTLhqLe0EU5dVUATOh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\n0aUjYeXpp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5wWkCkSo++wGPu8scNqZo1ELYKYlKIcad965Tdkbw+Ft87h/9CVtjs+QPn6N+K4qRVFAm\nm/i0FsyJ2HHodTzU5Aiiz8QGpjhgwnFIYLnOXnGO0oMYnaU6Ln+HtOOYwOlHZDey9NEIUSWilpkP\nbpEjSVv3ElAaFAZx3jNfoOH0Iwg2k2aGbGealualbgeIC0UmOERt6+y+tUhfcMJVHZwSVlqmh8af\ndt6gVozQ3AsjL/XoW05saZ/DtRnMhoJ66T7FSpJ8J0k5FmHWtc1p5RF+GoDAkrhBX9PYai9h1DQS\n7gJetUGOFAny9NEQRAFhysJYc9D6ZxGEawben6/i0rpc0O4Sk0rkjTjWd5u0idLBje5W4LSN+N8P\nyPgnYA++mP5DDKfIt3idebaYY4eg2EBK2eiCzLSyiywYFIw4D3pnccQ6hOsGlbUo35t/je30HFVC\n7FozKBND4v+kyEXtLl/77SdRwSMjT48nEtptw4M/XkYQYKBq9BQ3RGz8y1Xmxjcp+pI0KwFoc3Lq\nRwcK0B146O574DsgvzpAnhti2DJWWYScAC7QvRKmF5LyEZv6Ipv1JYJyE6svU6lGKezP0LT8aGqf\nmFjELXfQnU7yQhL8kLh8TM44Tykfw3aAbYioPYNJO0PGmqQ0SKI3HRiSiuWTELHR6BOQasyGtujU\nfBSqadx6l4hQQpZ0rJCE7NIJUUVBP5l1URARgzaSy6TXc1LthykjoGj6ycwNqc2MbwvTKeCngYFM\nq+/jsD3FUFbxB+p4ZhsIURFNH3CwNcP+cJpW34esWgh9E1kw8MSaDD0yOSOJq9ekYoYRBJuEkCfN\nMT4aHJNGRScp5MjLcVqOAE2CPH7vNKJmcjA5hTfeIOoq4bT73K/1sA4lhsdO5MkeVlzHcksMbA1B\nsUknDzlwCmRJUyGM19tkcXoN+fSAaidCsR+jbEYYmjJlKcIy6xhDhcIwiUPr45GHuGnTw4WIRUQo\nk/TkUDAolxOI8knf3UBGzziwazLCWQvdVp5E+Y6MPFWeSGg7F7qMn9pFWLapxOL0nS7sZRNPukna\nOsKp96EO7NmwbJ/s1aYAzwknJwL/b9BTCvVkiNzjScw9GUo2BOBm6xq7nQk+7f02jXaYZjvMV579\nHXayC7y9dx7upPHPVkg/t8dL9ttM+fYRZy3+r/Lfo0yEmhjE62iTHD/GTti0D4N4Bm1OsUYlE6e5\nFQYHqJ4hLk5+undwU7HDJCiQE0tIiklaOCZlH2Eg87F5lbbl4RlrkwOmyJSmKL6fZvn6A0ITVdbq\nK+iGA5faYWir1AgQcNa5PvsuEiYiFjmS3Gg/z3dan8X/6SLTrk3m2EEMW+yuz3Pz3RfABY6ZLt7n\nKrQyYVS7T2A+S/t6iVI3xr3OeZzeHufin/BfKf87XcHFBovc5Bqz7DJr7+ChQ9J/hKPb47d/41dp\nCCEcP9vn5ZffYtq5y6K5yXs3X4U1G86DcUfD2HTSWYG3XWlSqUNe8X2ThuWnYy2Qs5Msedc55XuE\ngs4D71numhf5Hf2XmDQPOC/dx0Ob+73L/F71b7Mcf0BYLpFhgiZ+PEqbF5V3SXOMJ9BieFmlQJym\n7UfEonErSm5jgnLK4juDzzyJ8h0Zeao8kdC2IwL9tpP6exFiWoGV66s8cK5wvDvGn934EsWDOOxZ\nCB+YXPknN+GMwK3D69gPBGgAYxD3F3AbLUrtNM7zbZRTQ5rfDmM+Vmh7gqytrFAtRhnsqWwH5sn1\nU0iDHIsrnyBN6FRtP28PXiYo1AmodZy+LmmOaOFlmj2mhT225Hk2DlcwqjKtKS8DWYUB8ADGXEec\nX7hNmQgRyoSpcse+xGPnMkZMZludI0cc2xKYEvfZrzT5+Heep4MbR7jP2efv8HPR3+Oc/oB+18Nt\n7wXu+c+xK04jYGMjUiVMmApxCmj0WfQ+IuooklXjnGKNV/geBRKEUjUGrzjYy8/TKvto/vsI4xcO\niEwWaQt9Lrrfw9YEjkkxlBQ0ucc7vISbLgYyYSr0cPKge46PV5+jbEQZ2irdUx5QwPDIPLKXwTAZ\nSg6aF304Fnr4X6jQKIQYDN0nrawmVPNh3vvGqzTf7SHUTtMduHg46aK4mGZsbo+2001AquEV2pwW\n17jAPSbIUHLFmJB3EFSTCGUuc4sWPjy0mWUHNx22egv8QfkrNKoBDFOGMFRcEayIxGDbQ2Is9/91\nmeLIyP9vPZHQ1i2F9rYPuysQixZZGl9jtzvJwf4M5T+KgdkBvQWKE7e/hXumw/yLG+SaKVqbfrBg\nsO9EUizsqggREJw2dMAxHKDYBkeFCfptJ6g2JTGK6u4zEdwjOhlDD0tYNpSIUidAggJmUcFsShxa\nHuJjRaLBIlPSPnktTd0Z4kCYwutvci59h3o9iCLr1OthGsMQAVcTwWVxMJyk6gjiiTVIO44QMCkJ\nMeaEbdpCmYwVZFB1ojn7pCczOMQ+Vl9A03ooooHDHBKjSJwCykDnZvE6bY8XNThknEPmHNuIDovv\n8ipe2sQpEKRO2+fhgecMXrWOiIWj2SflOiLgrtIRbFxqB9G2UMwIiqjjEAfUCKKjIGIzQKNoxqnq\nYQpWnIYZQDcVLEtG9BhI6SF9TaNCmCMxzeCMgkPs4j9XpfeJh0HDCXELr7uFmLPJPJrCPo6AGoWg\nRf+eRmPLS+85B3ZQwHDICOMtNGcfp91jR58lM5xAMGwElZP3wIApVpHRaRAAbCr5CGtvnqE3dEMY\nuGATTRaZ8O1T0qIonsGTKN+RkafKEwntQV6j/kGUuS89IpXK4LK7WEMRIyPAu31gH65p2L+2wO70\nLHOxDT77ytd4a+oLrH/PD78BW3+4DLM29rjIUFJP5nQPIDJZwb9YI3NjFiMs4rlcZeiROe+/T2z5\nPY5C17CQOCt8wmPHMgYKAbvOw48uUniYBB3cP9vFvgRBanjONsiace5qF/hs+pt8IfU17j1/kduV\na3x48CJ2FZ4Zex91ZkC760GSh0wm9vllvoqJxHeE1zjNGtlIhdgvHFG6mUayLTShz58IX6TsjNBK\neWkUIoRLNb6U/o88I36I0VK58dFLHM1N4gm2+Cm+ziIbDHDwp3yeHWZZY4Ur3MJPg4IQwz3WIJ4+\nJvZMEY/YxkBmgINHnKJleSkM4ySUPHNigykOGOAgT4IdZjkajNGw/YQvVxCMIbWDIPqqG/m0jnul\nRlI9JiDW6eKCJQOFLipDxMcWNC2EmQGpsT20sM6jg/PoKjBlw2cM+D8NBv9WYHdjAaIiYtyg+Qs+\nYmNFwnaFP+58mf3aLEJLZml6lZoS4EOe5df41/Rw8lV+hRl2aTwOYPxTYM4+Wdn6ksnp0/cZ9xzw\njv0yHVF7EuU7MvJUeSKhrWhD3Fcb5G+nESahciGM5u4ROlun8isxGI4TPVNm9uX3OG6Os761QnUi\nRPGtGPzxEA47uN7QCf5Ui4SnQM0VoG4HEGZsDFOhsh4jPFOk03TT/TjAZmIFOWkj8JBsaRyP3Mbt\n79I79lEYJKg6EzhXOkzM7tK0vHQmXdQJMMkB045dLFtgIDjYEWbJmin2h1PksinMQxFh3KDjd9IQ\nfCTdWebEbZaEdXw0aeHFS4sME/TELufk+9xW3LQsL1vMUd2P0TwIoh8p6E0HrnCf3BsJjpRxEAV0\nt8KSusF1PmKbObKksBHQOZkt8i4vcJeL7BVnyG1MInxko0V71L8S4IyyilWTKO4lqX60iK5J9NMy\nZ3wPuK58hInMNnN0cfEpvoeq6nQlF0dymqIUp5iMkf2vx+noHoYP3YTnq8QDBSTbZFzLMEQlSola\nK0ZjNYidd5CfmURJD1GudzF3dKyQAOsyiWdzeM80yOTnGXhdmEmZ7raPhw8ukq1OkY9MYKChDnTG\nY4cs+B4TpEaeJDmSDHBw9/AqtWoYc8lB4AsV1Nf6tKIeVEcf0YBeycuMd5vSkyjgkZGnyBMJbcEE\n2akj923qlRCNvA8t1EVJGHBexhl24JkH12QLadugq3sp2DF6dQ16QMJCnDVQloa4PE3cUoO0eIA6\nN6S2FaNWDKGmu7iEDnpJQ9QtDFPGtDX8RhNN6NHFhUMfIDRFcrUxTs3exx1uIhHBTQsJkyY+4nIB\nNx0qhDksTJCtj9Fw+fEaHSaduzSjLlzeNg6GqLaBNLCx+xK6U6Uru2jgp4uLqlki1pPx+RrI4hBZ\nMEAXMCoK/YcuKIv0xzUOXxvHTx1NHaKm+qT9h6Q55jaXsRBwWn3qnRDNlp+j/iSORI9qP0qrFIJ9\naA+HNLtuIoUqlESa5SH2dhwpMMCZaiDoMBA02ooHU5SIWiVe1N8nIpXpOFzc5jK7zOD092i95kXM\nm3iO+yiWgYMBIaGKQ+7TaAWp5sJYioQQMpH7BuFuhbBUQlwY8jjRpOkXYEdCugLKixbCR6C5uzji\nfQYdB8XdBPlHabSXujgCfZBAFE6mUfZtJx/3r3Gsj1Mzw7S7fuywyOLnN0i/foByvs++PoVuOsj3\nU0i6hcMYtUdGfvI8kdAeVh30PvDywme+R6md4O6Ny3ifq2K0VMScSezlLNasxc3ONcamj0ioR6jS\ngPXXXPTSXigEaWs2/Y0g1cUgn/J8j2viTQLUKU9H2Jmc45Z8mdTsMaemHqOIAxTRYF0scTb+DY6E\nNOvCElOTW7ikDjfvv4AjPcBNhz4ap3iEiw63ucQ1bnKaR1QIU7sVp7KWwnpeYGn6Divn7nNPvsCc\nuM2ssct71Vc5aE+zal5kenyPlsfNPS4QpkLWyHG/8llW0g9Ycd0lKeR5PLPMprDM0fEMZlakX9bI\nmBOImARdNaIrWTTx5AsjRxI3bZx6n/3MPIXHKdTDPte//A6K32R/dhESYKkS/baLu79/DYoiNhnQ\nQbMHJL053u2/zAfdF1kKr3FWfMAV8zaXmw+QtQElb5BFNrAQ6eDGqfYIjVWYT25zJI9RJ8BZHrBM\ni/uZi/zxH/wCxrMgv9rDG2jy0/J/4Kp8k5oc5F9oaZpOoA653Dj5RBpzRSIdOiAeOqZgJ6gVIwzv\nuogtZxlMyVQ6Ebb9MxyTpGO7KVeSdKp+jJ7E8tQDzrx6n3MvfsK445ChqHLD8Qwf5V7ksDtJOr1H\nhtSTKN+RkafKEwntM7P3OLr2Gs2olzH/PhPaAbeki5SSMRyf6dBoBbEzNlZapGYHkS2DcamGbBk4\nwx1i53JUM1G8pRavnXqT69KHBKjxDi/Tkr10cDNEJUsKHYW4VCAuFLB1kTsfXsX2wMLZTTYPlznY\nnIV98J5qMcUeC2zSR2OPGfIkebf0Cnca1+mbGmLC5Hr8XYZpFTtg84l5nqPHU/SDbsrjEcK+ImPO\nDGP2IWn1iLX6GYr5MZpmGKFxi9OBh3i0Nm3ZSwaV4wcTdEse4s8f0l1yoyoDpjwHLLGBX6yjiwr7\ngyn2etOoziE9ycW+PEU6ccCK8oBossjmB4tkytPQtxGf11FTPdzeFq1siOEnGvgEwp8q4BzvUr0b\np33oJaRUGf/MIXht1sVFem43kmzQx0GNAEVimILEFPuEpCopsmxUTpOVZAqhOLvMsG4sM+w4YGhB\nWaC75qd0OsbBxCRZUrQPbagBQbA0CZfeYy65jsvbwlbAS5P+kptez0u1HiVazjORuEv+OE2hNYZu\nKdhRIDqEjsKMa4fzjvssODbYZ5q14zPc+e5VjtoTiFGLmdgeHZfG/pMo4JGRp8gTCe3xVAZWDtCk\nHl6jhcfuIBwKSH4Tz7Ua/QdejIYKAWh0gggi+L1NokKJULyKc6WFrBtEmhXOKZ/gznc4bo3zceoZ\n/M4aSTlHkhyHlXEe1Vawx0Scrh49y8nG4Vl8wSYTZ/bI1ccod6ME3FUccg/F1nHaPQpCnKyeotqO\nkCnNYTZVnHKHq+Mfciq+io7Cqn6WtdJZOg/8mDMy7skmpzyrzLDLBBni5HnUOI3eVul2vXgaTvzH\nTdpRF7ZXIKRUMZsysmlw6tRDMtI4A8tBRC0xziEhqhRIsN+b4ag5wZL8GMWrY3lhNrzFYniDeLLA\nvY8vk7+fhqGNeE1HcQ9QJR3RYYFqgWWipdrIQZ36zTG8jRaxeAHVGpLvpNga+jj2ponIZXw0ARji\noI2HJFl8tNAthWY5QFd1kwsl6eKi63YSnCrTcXoYVhz0P1bZkJdp92XyRZnGTuFkGuCzgA5KcUh8\nKotbazPGKruEAAAgAElEQVTAcdKbn9AQXAKubI/gsE5QqVHuJxmWnXTaHpxWC2e8ixwd4nK0MS2J\nvJVkU1xgtXuGta2zKLJOOpDBazcJy6OO9shPnicS2k3By6fktwlQ58HaBf7ozV+ka7oIXy0w9eV9\n9PMK5UKcg/U57AMoGy4asRhfWfkq0XSe78qvMnN2k5hVZN8xydfe+hnWVs/S+mUXPz3z+7zue4sK\nIb59/w3ev/kS6i/rDCYd1KUAg3kHOVeCD4VnqUaCBEIVFgJrGC6RVfssR/oYMbmA3ZRofxJi6FDx\nhFtMj2+Q0I4JUsVFl532Iu1cAHtXYta/zRt8gwU2iVBBo4+FiCPUI+zJUc0naDV83PiNF7B+yub5\nC+/yX4T+NcI12LOmecXxXb4zfI0Na5GO7cYQZFQGhKng7vTpHvl5mL/I/Mxjzp2/wzR7BKkxVFWs\nC9+/rec2SE4DXXdQLAexLksI5y2E8pDmggfyIlZR5PRznzB5ZZf7nvMcb04iluC1C3/GsucRF7mH\ngs6f8nnucoExjmjgZ9U+S7UWwqc1qBJiiXXSk1nUXxqw1j1NcSsJA4X7dy/z8K0Q5h9/k4HWh88A\nCrAHwx2V7OkU5333WGKdO1zC4Rmw7HzIXHKHjD3BB+azTM4eoHl6PNo4R/8DD954i6Wfe8S+NMWa\neZp6z8+MYw9nrIfwJZup0A6T0R3yrjgLbDyJ8h0Zeao8kdDeXVvA3HiW0ESR7ribmVc28dotjLRI\nR3Tj0rp4ww0iVo7zwU9IWHkEt40aGbDdmSf78STNqQB6UsEjtGmKfirNKHzHpvOyl+ZlLwIgCDYD\nw8n28RJHvQka+SLai10GAweHN6bp5dw44gPMcZGj9yfpWm7MZ+FZ4UOmnBnWps9yqIzTdHtwOdvk\nSJLTEyi2wV57BtG08b5QgnGTLCksJHw0EQ2Lx5kz7KgzBNI1rIhEN10nvHzEqemHXHHeBGyizgLH\n7TRvr79OJ+ImHixgChJ9NPpoDFAxHCJasM0p32Nmw5tEKFMgzq41Q50g7QUnycAB0XNF7Embuhzk\nkBlIC/jVBgHrkHnPTRyxId1XvchTQ5o+D7NsEwuXMZwqqjpgjxmKdoyqHWZLmMMWQGWAmzaLrJNX\nJpiv7vK3P/gP3Fq6SC0c4JT/IX5HnfxMktLnEhS7SVqraRBfAPUWUkLHtdJiGNQYHjrIvj2BPadw\nPDuJ7BuQUPIExSoNxUeukaJeiiIJIpJoEFs8xgjI+Fx1PFIbQ5CRBQNBtZmXthAQuM2zKM4hCW+O\nRTaIUeQ3nkQBj4w8RZ5IaGfX4lR2rjATW2dp/BHXxj7CK7TYFWa4wTOIWLg8HSKePOe5xbS9T8dy\n82HrOR7nTmMfStghESMuo6NgxUVIAFmBWi1Ehgk0BthhAXVywFF1ArFroXQ/ZC5QpVPxUtgbg6rF\nUFaotcPkVicwRZH480cnJ+jct0jM5HjICnk7gdvqsG4tsW4sUe8FYSAT8pRJrRwgugy2WCBLmiRZ\nwlaVG43rdDQXaeEAv7dBPl4k8HqZBfExMbHAFnP0DBedjpeH1fPM+DZJykcMUWnjoY0HFZ2Is0g/\nqjKm7uPVmgxwUCDOsZ2mIMTQEl3GU0XG7CMqZoR+RwPZxB1vE9FKuHabJMnj8zURnzVZtVdoWlHO\nCKsYUYUmJ19wx6So2wE+Nq7hFjvMy5tYSAQoExPLPA6cZbK9zwvH73N78gJVPYSn3yGl5dCCA4yh\nQsMO0LJicOEKlLYRnBaqv48pytimhGe3S9ft4TDpJG4f4xHaDHBS9oYZGg5CvTp1I4Q32GBmahPX\nVJewXSFtH59Mc5RcNCQ/M+xiCgoxqUBYqJDmmGe4QaMTeBLlOzLyVHkioU2ugrPX45p5g09b3+KK\neZuKHMYrtCgSY4hKBzcKBodMsGvMcLd/kfrdGIFBg1c+/U2WfY9QlCH3uUBnzn2y9rYCjXEfR4zh\npIe61GU29pidtSUc/h7uqRxj3jAFMw0rIDmG9HCyv7OIHlDRfB0QoEyUPWbYZIEKYeJWkV8c/i4f\nydf4hvVF3su/QshbYmHsMVPqLiWi7DNNCy/nuc8X5a+hL6lkhRQ+Gvho8j2ryKPWHE23j5haIEGe\nR60zFEjgPVtF0QYYSFiIJ4ss0eIMq0w799hmnreOPk/P6yCUKjLJPuPiIVGxSJQyMgZdXOy3pjjs\nj4NksZBaw+XosmaMk6t9gYDQYDm8SsmMYVgyLdVHXQhQJkKA+kkv3spwp3OZMfWI5+UPuMtFFHQu\nS7eZntiC5JCPjfPEXVkOm+P87s7fJTqbxcoKHP7WDMbrAtL0EPNnNPhDMHIK9e9GsZIiqfQxv3rl\nX+H1NTlkgjfXv8TD4nm8Votnrr/H9dAH4PqQt62XUSSdi9zlZf6cBXsTt9FmQ1piQ1pghzkMZES3\nybNLf86MvMM8WzTw8/X9LwPfeSIlPDLytHgioe2atZle3mTKtYdH6NAWvciCQYwii2ywzhIGMipD\njhijLXqoKiHSY8ecsh9xNfQxPdnBvjnN494yDa8X50wTt9ZBcQ3poxGkjm44KJsx9IjEZChLQDmk\n3nmZHk6WxleJq1mGpsphewrzvIRHa5EWMhjIHDLOJguUiVAWIrwjv8ixmEaXZGzNpjnwka+kCUfL\nONSTy8wT5Bkng0MccMX5MQXidHCjMsQvtEg7jqk0otiSTDxY5LOttwjqdaywybGcokIYGwEPbSRM\nhqhYoohDHZAIZjEcIkmOeYl3cAh9KkQY4KCJjwEOJh37eKUWLTxccX5MTCoiSnmync/RM1wEgzUu\niVU6gpsNFunaLizhpCe+YS8iChZjjiPS0jEKOtPsIWGwK8xgOCQMh0SRKAEanNYeosc1YlqOUijC\n8fVxrkzeJRYvcnBlhsrjbZyXHrHbnMfsKvQaTh4vLTPv38DTbDGoOmj2g/QcLh69c4bqTBjfxRrT\n9i4IkLOT+O0GcbtAT3SerEVOg0vcoYeTvqSx7HxEDycPWUFlQCUUfBLlOzLyVHkioa3NK8RPZ9Ho\nUyVEU/AhDm26outkVgUSQ1QUWydvJWj1fIgNWBpb44rrJjPscIsr7FozFAZxBqKC111nwbuBV2rh\nYEiAOnpLI1uaBL+OU+ziqvXZKE0ieCwuJG4yxzY2AqnAMcMxFY0+UYrYCGTMCTYHSzQVL6JsUJFP\nljTt2xrp4AF62YlZVegFXUTUEhNkWGCDEFWOGD9ZlY42+0zRwoMkGcw5t2lXghi2iiMw4NPmdzhj\nrFIgxAc8y2NOYSESpoKHFjmSNPBTV/xEYzmcdBnjmLN8goLBAZMcMk4HNy6hyyXXbRpWgIfGGSKd\nKmODLFOtQ4bFCmUhQnrqiFllh5od5Detv88QFbfZYdh2sCUHMDSJ55wfkBKymEhMkCFnJ7nLRZr4\ncAld2ngJUmPMfYjX3SREhT3nDHe+eJEL0h0m7ENExUKZzhF5cZ3uhpvyZozmoZ+3l16hrbmZEXZR\n5QHOUBvbK1J8O0FD8OO61OAl4R2GqNyzL1AiSl5IcCBNUiSGjMEMu2SYwEYgToE1TrPJPF1cSEnz\nSZTvyMhT5YmEdq/vZI9pAtSZIINmDPhe7nV0h0wyeUidADYCFiLNro/6wzDmmw4cP6PjvNCjgZ8o\nJS5Kdwn46tzLXIWOwM/O/z5DSaVI7OSmtrp+cld3ZNZ3zyK9e53+2SSJxWMsRPIkWGSDN3gTE4ku\nLiqE2GeKzc4i2/tLCAmDQKSCINjUCOKR2vxD7/9CxFlhYDnIORLYCLjpEKFCgTjbzHGaNUyk7x+x\nz5PlPjPouGNNOrjYEWZ5J/kc2/YUWSmJRo8kOcpESHOMlyZv8nkOGaeFlyEKXlo0/t/PRqBIHAEb\nLy0m2ecMq6z1z/LvK3+X/XsLOPYHtN7/Bv3hWcZmMwTMBtPsEadASsySJUWjGaD+bhRrHEJnirjE\nLlGhSIQymyzyiX2Oh/YKAbFBjCI9nPTQKBHlEacIUkMWTM7Iq+SEFOv1UzxYvwzNLA63h88uf507\nmWvc2bxCYzXChrVMd9xJ6soBXqGKLqlcS9+kpXl4zBJdXCdH0mjcFS6ywSIf21dZFh4zQYZt5ujg\nQsLEQ5tz3MdNmz/ip7EQn0T5jow8VZ7MFZFFB9WDGJV4BIc2QBWH2G5oy2429QXaGT+GriAGLAQH\nxCN5/GfaELQ5ZJwCcVp4KfVjHOanafW9eJxNbEGgiY89a5rN4QKmU+CZ9PsU1Dh+s4E5tkchUqLd\ndrHzYJHYZB7bI9DR3RhdFVky8PiayIJBSskyH9jg2ByjXo2QsUUU9wCvq8WRPMaYfMQi63hoUiBB\nFxc6CjWC7DOFgz7T1QzP5G8THK+jc8gFQcbvOLnpQJkIA03F2exxfnuVkL8GIZuMawxEmyIxqgTx\n0CZBnjp+ZEyc9PBwMpPlEafQ6DHLDos06ePEkgQmXPtYaQlDlWHfgnmDXlxlT5oiSRancPIFUdKj\n9Gwn3nQDb6hBWswwKRwwY+4Stqrcly7QFVx4aBOhiIzBIeO4OVmMykeTDh7aXS+NUojx0D6yZNB0\nuREELwUrTtBdQ13qMenaQUqZGCjs12dJ+Y7wKk0sQyLbSNOx3AjYxCiiI5MVUrTwkm+kuJe5QrUV\nY8eTw3uqwRX5Y071H5OqFtn0zlHTQpQaSfrW6B6RTy+Jk9tUhb7/cH1/m8nJzWEr33/0OFn9beSv\n6j8b2oIgjAFfBeKcfLr/yrbt/1UQhCDwe8AksA/8vG3bjb/sb4htm27GhxGQ6WsObElgLrrOnjnN\n/e4FuvcDGF0HzFlML2wyM7/F7Pw2LbxsMY+FSMmKkO+mOD6cRo73CcRKHMiTJ9Ph7BnKwwjnvJ9w\nJXqTj4zrzCT3sDZv8mh6k7Xdc2yvL2GGRQquKN8avk6rGiFElcviDU5Za6SkLOfHbzMsq2w3lsib\nLpJSBpxwg2eICictERddbKBOgAB1hqgMUagTwNHc4sr2PRY8GzQNkVkkwlSIUOYuF1EZEulUeGHj\nBuK4TUtz49Pq3BfPscMcOipzbLHM+kkbCR+WLRI2qhwbYxyZ4wS1ChPyyUqJNSuEIup82vNNyucj\n1CQ/O9U8vZdy2JZIRp5gwsqQIE9MKOIx2ijKkOmLu0Sk8sl2CsSsEmGjii6qKKLOpHBAiAqKZdC3\nnDjEAW6xyxzbHDBJoZ9k62iJlJzFH2wgJQb0RZlcI0Vb9hKcrjGxuItXarFfnuOwNkXAVcUv1xEM\nm3v/D3tvHmTZddd5fu7+9n3Jl/lyz8raV5WqSlVSubTYsmSMbQR2Y8DN4pkGJobuYZpmhoiJiY6O\nmAloGIaO6YZpwt24bWhw2yDZ2LJka7NUpa021Zr7vrx8+77eZf54eZVPNXZgkCkkm1/Ejffeueec\ne/PGL7/nd7+/5Wwdp+OQifk3GJDXEUSLeSawEGhVHJgzKtc3jnI9fBh/Msdh71WG2qt4My2yUpRp\nYS+FzRg1PO9K+X8Quv2jKwKoTkSXhOJv46GCU28i1UzMOhhthQ4iFm6gH4sQFgqgY1FEoInIBhoV\nJLWD4ALTLdKQHVTx0C6rmDUL2nXA+gf+W99b8v1Y2jrw65ZlXRUEwQNcEgThWeAXgG9blvU7giD8\nJvC/Av/Ld5tg7PgcG3EDr1JhiBWiZMkRZr05SC3rxbwpQxkEINKfZSy8wAFucpP9ZImSJ0Sq0UdZ\n8KPtrzDpmGHEsUhWjOClwgfEl3C56viFEh1dJZUaxOtoEBVMdmlztEc01mODtPwKUanAXudtXpce\nIJPu49X5s1zL30MwlGPg3BL9/lWini06lkJGDFPXXXxY/iYCFs/wKFkiqLQJkcdPiUFWsRCYZJpG\n3MUfnvosH8t9jVpB4A/5ZfZz6+0i/8uMkA1FqZ71kHbEaDgcjEtzZIhSwYOTOhrdHXL2c5NZdvGK\n/gB/svFZNjaT1Epe7j12kT3RKcJkmaiu4C3XaJdV/jD5WWb8E9RxM+hcZ4gV7hXe5FTzIg6zyboz\nyR51iqSyhkesUsLPIqN0UKhLbgbEdXJiCAAXdcr4Odq+xieqX+MV70nmtRGq+PFTZtI3hetAjcXK\nGNmtKA3NhZlVqb0apFnzURyMURjLczhyibA/jeUxCasZKqaXtBAnPrFGteInu5SAfpGWR2aZYaJk\nGI/MMnF2lm/VP8hUYR+FN2Lc2HcIuV9nc7yfVXWQrVocPSOjJWo0353+v2vd/tEUEVBg/DTec15G\n/skcP6Z8jROrlwg/V6L2kkVmWmAJmTZOLBx0UNAR0LEw0RFp4KHBAUEnOm6hPSBQfMTNxeQxvtH5\nCLN/vo/CS1W49Spdy/wf/Re2/I2gbVlWCkhtf68KgnAbSAIfAz6w3e3zwIt8D8U2wgKBUJ6NxiAO\nq4XmbjPBPCUpwOvaSRoeCZ+WZ3R0npA7SxMHywwzyCrj7QU6VQffFh/itmM3HkeFgFhAFnSKBOhn\ngwlhjrLsA6BliXi0CpLSQRcUJqQ5dI9M26MyyiJeKnQEhaA/S23FTe75KOXdXjohgaCYZkBZx0md\nIgEcRo2gVWA3U3ibdeq6h4CzhG+9QmJ9i9BAnpZvgyHHOoJqUHL4MJRlgtUiTsFBjDQFAjRx4KWM\nmxqa1iIVi3GxdZym4WBCniUiZEniQUHHRxmFDgJWd3MAoUXUkUbxd6hJbhqKg4IVooPKkjxM3JFh\nzJhnTJ6nhcwy11Dlceq4KOLnfPsMakcn4CgSkIo0cGIh4KWCk66/oJNXSeTSnEy+Ts4dxkCigZN+\ncR2/UgDRImdGmDMmkHQDRND9IprVINFaZ5d2i9uuHBW3STun4bLq+NQSitAhomTwU8RPCdlcZZc4\nx4y4m1rbQyPvYT2aJEyaI+ZV8qtRdEFl3+ANJsxpRI9BRk8QcWTxyyUqHi8eKrhbVaRAm87Wu2P3\nfhC6/aMhCgxGkY/0safyKveqlzCfhUytirDmou/SOuPSNeKZRfxrdVx1C4mufdzZ/rTorpD69ncB\n0OjubeGrgbIOXHcwsKmwR3fhW1uAWoM4t1AetVgbGOa5yyNY2QSsZbdn/tGUv5XWC4IwAhwBXgPi\nlmVtQVf5BUGIfa9xeYIMuHLMbO2hZARQ3C0e4nnaDoVIJENmr8KgY5kP3f91VhncjoMe4Zf4HA+2\nXyKYrdKJytTdju4/LTUMJCS6W1X1s8EaSVpoIEE0tIEm1KniYYBuokaaGPfxKg3TybPGh/AESsTY\npPRmCO1cHffxEm6q25EcVUwkBqU1RqxFkqwxVlslWKuQi3tRFg08F5oop3TMEYFa0Mk1aS8D0joP\nWS/QCbjQnBIfMF7mRfEcy8IIAYoc4zIDrNNEY6sZp6a7can1baBuYyDipYKIyQJj5AkRlrLsj9yk\nGnGzKI7yZutexLbBbnWaq44jxB1pnoh+mTHmmbBmuG1dY9m6hwvCacBiWj+Ao9Pin1u/h9us0bY0\nFKtDQkzhFcvMMUHfaoaT1y4x8sEFFt0jzFkTdCwZj1xm3j9Ehggbej9vdQ7TaSooZoeAXGKXOsu4\ne55BZYVKzGTzQIaqGSTZt8REeLq7SNFEtdpIHYsJcY4+YZP/q/4b1GoetE6TeXMML0UetZ7ljxd/\nlXlhF55kmbi4hTdQYfFQmX3SDe7hEkm6+4nmxRDOoTKtb0X/jmr/g9PtH04RAAXZaaK5ddSSiTUW\nRv7UQU6v5fhXvpt0nm1yc+WrpFeAr3VHzdFlrTvsALTNVmvbs9quYxvE5yxgpXtYX2/S5DpjXGcS\nGAAOA55PODh/32O8/h/OodwKQyZDywutmozeEIH2XXgm7x0RLOv744u2Xx9fBP6NZVlPCYKQtywr\n1HM+Z1lW+LuMs7TD+zDjI6hqi+R+N8cONRhihWWGeNk8i16VSQrrHPNeJE+YOk5AwEUNt1HHpTfY\nkmIU5AAmIn1sEWMLLxUaOKnjQsSiSIB1fYCZ0l5QLdRrL3DfGTAR2NzeUCBfC7NSGCUYymIUJFJv\nJJEPtRgbnOXDyjdpCN1oBid1JExcZp1hcxlvoQ51kdW+BO2OilLtMKCkaDgcpLUwitjBZ1Zw6zWe\nFR7l1QtgHTmD4m6hqF3m20mDEDlGWGZWn6BIkDFpAafQoIGDOXYxwDoJNplmNwptPEaNmfJeWrKG\n5GyRXu8nrqQ42neJq6VjBMUij/q+wZYQQ7Na1M7fYPRMjA2hnxWGqeheJNNkUF4lrqcJtEpILZNl\nZ5INd4IQecauLjN8Y5XswwFuJfZy2TxGqREgJmxxyPUWM0yyZg2St0I4zAbGpkzhjShqrI0/WWRw\ncInSa7eInpyg0AzhVcsEtQIaTYoESbX7KGxGkJ1t/JECXqOKrOtYhkjLoaLIbbxWhVI1iCFION01\n0maMQiNMLe/jseBfM+Jd5AYHuPGKQm4qg+Zp0mi4aH77GSzLEt7VP8G70G3Y09MS3T7uhqwCg39P\ncyvAEInjNSbPLDH25BytbIu1sBOzvcwRqQnrFh26pIVFF6xluqBs9rSbdMHasf2919Lujf2x+3bo\nbsuqbB8yoA4I1NxeLmY9nDQVxJiDW4/vYvrlYbYuObefxd+n5f33+ax7JbN92DL1XXX7+7K0BUGQ\ngS8DX7As66nt5i1BEOKWZW0JgtAHpL/XeNcT/4zmR3+JAxMXmfRMMcwyKoeQ9N1I+gOILRm/PMOI\nW2YvDZo42CRBGwUJAx9lDpmrOKwma2ISr6DRR5fueL1zkjfbJ/C3K/g1CVMNkMsdpmAGqQkytY8O\nMa7OcURLM8Ue6vnD1JfuxRvfRDY6uO8LoA3XGImFeFR9nYwQpWMpHLSuUxE80PJxbMOk1o6yoSZI\n9PtoOxRcRpNjlSJl2cOMp58IWby6hdnxc0F+DFnIMPT4CYZ984iObqbnfv0Wh2plDuRavBwKMh3Y\nRR8e4mxhIaJxAKF+kFYJCqmjeMQaHk8aQ92Hy9uk371KeCFESB0kOuwjnD9BVMgwFsrgF8I4rCbr\nVpVzn/aSFUJc4CAubEt+jDPVLIfr61R1Fzc9CeZ9MgN0GNxtEdnjZunDceg/yJL5QWJVkyFxhX0e\nkzz3U2cYPxJ+ipQvB8lOn0I/3iRwepYzE1/nhlxi5NMH8VAjr4/RNlT2KFPcru5noXA/1XIUggZS\nf5qTwnOoVZ2NYhJPpETdcrFZSiI3dfqcGcbiM7xunqRSHced1tgfXWYyILPM40j7TkM2QeLoDLmt\nOM397+6f6d3qNnzqXV3/3cnBH+BcMhCm/3CF4T15nC94SPob7BlucdiZo1XLMVOD63SXKY0u6Erb\nnyJdILbFNgXN7XOu7TaDHetb6OlrUyn2YQOTDgjrFlAGyvy0CqI7wqWRYW6/JbES81F9cJjFW2E2\nrnvpRqToP8DnYssP8ll/v/Kvv2vr90uP/CfglmVZf9DT9lXg54HfBv4p8NR3GQdAKRXALzRwt2tU\nOl4uK8dIEyOrRyhVAzRKPkynguJu8QjfRrNarDCEizpuatRxsducZshc4VXxPhasMbaIU8XDC60H\n+Xr5owglmT3Bm+zve4uJ+BQL2UluFiI8k3+MR/zP8oD2Mg2cpNQBHIEm+UYU1dXAfzqDR6giYnGN\nQ4iYxNkiaa2xRpJy3Y9y22JhZIxLY4cYY2GbomkgWBYOq0nYyiFikpeDFKQgUTLsUW7xyegU/ayz\naSV4ko/zwc63eTj7Eo6rbdYOJSkE/MTZYoB1NKtNy3LwdPnH+M78Q/CKgKUIKONtJs7cYiwwxxDL\nOHY3qeJhnSQDkRW8VLjJftzUKAk+rohHkYUxDEtikwQHuEG/sEEZH4Jo0lZl0oEg/dYq4/UZKpIP\n44jI5rEwGSJgwZiwwBnveVxCnTWSWAg4zAZeo4qqt2kJLsQBg8DBHBN7p3iI57hq9DPT3s3HlKeY\naU9ypXOUiJwlnU2wtjmMa18Jp7+GJrZoobGQm+TVqQf45NEvIlgCr83eD1mBw5ErnI68QtTK0HC7\n0CZaSEaHSseHKQkIMjQkJ7P1SYw15ftU378/3f6hEFVElJyorUEOP7zI47+4QHTxRerPZcg8B/N0\ngcJLF6QluqBtbrd72AFbnR2rW9qe3raqbYBnu18v322Du7p92G5HjS75YW6Pn2sDV7IErjzLR3kW\n+VSUlf/9LE/9xySFm4O0HHVMvdat+/5DKt9PyN8Z4GeA64IgXKH7jH+LrkJ/SRCEXwSWgU9+rzl2\n77nFGX+VV//iNPqYyoFHrxIjTVJaY7dzmj/Vfo51eQATkRYae5ji18x/h4xOU3CwJcRBtNgU+2ih\ncbxzibiRpq3JzDp2sSldZMy7RETJ4qJKGxWHt0UzMkt/9BU6isyf8E85ylU+6PgmJ+JvcN06wKI0\nypYVpaAHKeFHVjp4qeCiRk4M46SOT6ugDHYYCS5ibe8U7qBJXEyx5Q6hGS36GmkuaUeRJZ1dzBK0\nCliWgcgBBippJq1Fhj0rXFKOM983zsdPPUnR76WBkw4Kr3GKhc4EC/ndtCSVXXtv0ow5KWbDtJpO\n3HJ3h50ZJnHQxECmjosEG5iIzDHBHqaIkCVIgRJ+FvRxbtf3knOESWpr1HHRr2c4XLpF/0oW4Q0T\nacrAc6TNm0eP8a09D3GlepQtKY7oMhkRlphgjkFWeYCXubx1nGff+gjCeQtJ0Rn4iSX8I3kMRF7j\nFOsL0Hh2N6+fO8WWFkeQLDaFBMR1BnxLFCUv3k43tT9FnE1vnHZS4jucxVItXBMlWlU3i8UxPj/z\nWfK5EE1NRd1T58+nfwa1ppM94KfgD+JxF5gMTpOKDbD+LpT/B6Hb73+R8PzUIMOnVT7+b/+E6Fdn\n0d/KkpstYdIFUJv2gB2L2gZRiXcyyr1AbPBO8LapEZsyEbfbugz6DrViLwawQ6XQ89u+jzJgTJfQ\n/8dXeWJ5lnOjk3zhf/5JFl5uUP+vK/ywxn9/P9Ej59l57nfKI9/PRTzhMj6tQHEuRGNBIFp3Mnw6\nzTPWE5sAACAASURBVP7oTe5RL3FZOkZblDAQWWQUo6PQX99kl3MaVWmTJsqG2I+MjpsabuoIWFzT\nD1GWfIw6F7qOTVSW9RHSuT5E1SKprfBo55ukzRiXlcM0cOCXi4TkDOPM0qorLG+OoCsybacDj1zF\nJTQQBCjh73J1qoWQkPCUK+yaWiDVl8BwC6SVKHPqBJ5OnX49RYYY8VaaeDVL/+wWb8w7Gdvw0pfJ\n4FTrWJMGM9IkK+4hvu7+MGniaDRxUSdPiFv6fhZzu/HIZaL+TUIjGdRgm2reh6J16KDQxEEDJzHS\n7OU2PspkiDLLLoIUtt9M6jhpoAgdVKGNiImMQYg8pgRFzYsmt1BrOkIaqpaDrBRhVRgiLcQoCz7c\n1PCZZfrZwEWdiJilKbq5pJxi9dYQHUEl8vEU9aqHtdYwVT1AunWbVifC1ewx6hEHOKEoBKgKHoym\nTOemAzMmwQisXxwinYpjWiLrRweQPDpCWYC6QLkQ4GY5AAYIYR2pz43fqONRavjFMg5/E69Y4ajr\nMlPx9rsC7R+Ebr9/JU7II3Fm32sIfXmcNZG95gXkuU2yc11wFOlaujJd4LS2v6u805rupUZsgL+T\nLunlug12AN/ucyfH3bs4iOzcjz2PBVSBdqFN57kN4sIGwZEsB2ujjMc76EfLXJg5SaFmAFs/kCf2\nXpG7khFZs1zcFPdTd7pYf1oh+2d7+fk/S0EcNsR+QuTps7bYJMHrwgn+uvUx0ukk/338/2FAW+Fp\nPkyOCH1Wik/yJTaUPpbFE/xR45fxKyXul17hGJdZYIzzrft57tZjDIcWGDX/nE9ufIecI4jDUyNN\njBWGaeJgF7NEy3nq1wMYcQn6ZMLubh2UJt0A/w36ySlhvNEKJ69f5ui16/Q/nOPy8EG+o9zPRY7j\nUFqMyQt4qDJSW8G72IL/BKGZCg8cfx1rQyAVjzI1uZv7hAuEyfFb/B8c5i3u41XibOGnjNppIxZM\n8qUobYeDQ8cvEogWaUYdXU+7JaNZLSxBYJ9wi1/ic6yT5GUe4CU+wDzj2wD9CsPWCh6pRsybZkhY\nYdyaZ4B1JJfBvDNJLJYhVK0gRWDuQ8OUoh762MTnK5EjTNPSOKJf5Yh5FYCCEqQV1yjGfXz1yZ/k\n1o1DrD4/DiNW9525BoJvE/Eehdtrh3BSITSYpm65yOT7WLs+Bl+Byqkmm4EWK38wTu2mDwZNpN8y\nsaISzTd9ULEgb8GWAPstrLiEkXNxbtcLHA+9xgyTFAmgCm0OcAOjT+KVu6HAP2wigGAdYLxP4vc+\n+9usP7fAq7/XJe7ddDcg6qUtYAdwle0+9konsUNn2KC6fQkkdqxrhR2w7Y24tgH5u9nE9hw2uNsL\nhk3FNNiJ4L5lAYsbHP2Nf8uZT0Do07v42X//33Gp1gZh64cqP+eugHZ6qw/R34/2ySrjD+QZaGap\n7w1yhaNc4xBFAhStAEvGMPdKbxJ2nKeQCON0VFFp81k+R5YwK+YQf9n+BC1do21paFobj9wF4z/i\nl2niQNckfmHfH1PXnFy53s/1AYGy6GWLOCd4EwGTafYQIUvd7yJyZINiNUyhE+R1TiHRQaVDjDRr\nJEnRh4CJe3+d4ECWdlxlzjnKBgM4aRJni6BZ4Fv5xygbYU6MvMH0ZydZ/VIOq5ziiwf/CZcGD9MW\nZc5wHpUO9/MyAYq4qDHGAiX8NF0O9u++ya76AnFri+cdZ/FTZJQFFhlj6vI+li6M8fGPfpn9I7dI\nE3s7PBJgD1MEKXCe/Tw0lWd3c57n9jsZVpfZU56m73YWedVAKJo4tBaqoWN5BPqELSp40OnWKu+g\nABYtWSNXiJHYSNMacpL2x7jNXkr7/F2v0hC4J8qIfp1qLoD1kox5XoNhAR2FUjbI9IqbEe8iB498\niWw4wpYrznptiOZ+R7ceelKgrTthQUBYNhk+Mw9OgaXpcRIHVjkweI2HHc+x5Briv9U+xdrqMO5o\nmUgkTQ03U9n9d0N9f7gkHoFzJ3nixst8ZPkbTP3HLYrpLhDLdMFVoEt52LHUvRazbV3faWmL27/t\nUD4bhG2vg749p043kkRhJzzQtrLtRCk7xpuesTZNYtMo1h3t9jVFYPoN8C1s8quZ/41vHHicr+x7\nHF58HdK5v/tzew/JXQFtExEccOjQVRyHmghYtHDToIOfEkEKbHYSZOt9hN15dqtTVBQfywyzSR97\nuI2ARY4ITctByQpgCBIOuYkhSaSJk9muCucRq4heg4rgZcPq5xXvCAhQxYOPMl7KVPDRQcHtrHHS\neYFUJolidKjhRqJDa1sdFqrjrHSG8fvyTMcn8cVLJNhERCdEnhhpNFo0DCczW3tRtQ6L40PcCu9h\n+eIqb8QH+EboMd5w3oOnXcalNNgr3eY0FzCQibRzJMppllxFPK4KzmiD/e1rjBvzrCsxqnUvzaab\npHeduuml1vEzanUThFYZYp0B2qiMsMQgq0gYNNFwmg18Zjcc0qtXibZz1HQ3fqOCt1VDrhqIfjC8\nAqFWsRsGqBist5KIoklUTCPNW5g1mYbmpISfKh5MREJHsgTiJca8S6wG46QicSxVpN42MDdlGAW9\nI2PkHVSfEYgNiEiHDSTBoN3RqHR8uI/VkYUyUtig371Bp6CwkezHMVKj7VShAWODc9yTeJ2DXGGd\nPtKdGFtWH1ELfBTpoBCyCndDfX9oxHHYi2/SQcyzwj3iS+yqPsfMxS6Y2lVceq1lW2yAtYHZBvY7\naRAbaHt/q9v92+xY78p2ey/VIbBjWcvs0CjGd5nfvj/behd6xphAbh1q61X2822Oih6mvUNkz2qU\nZtw0rtX+to/tPSd3BbQjsTSDrPJJvsQqgzzPQ7ioM84853iRLWLUWl7qmQBt2UlHVWihMsc4DVxY\niOQJYYkCH3Y+QwuNFH3cZD9pYkgY3MerWAisG0n+OPurVGUnov4FvmGeIialibPFGkkiZPFQZZYJ\nVFp8hv/CajhJBR9uoUYHhRYadVyspMaYL05w376XmXeNU8PNZ/g8B7nBAN1Ss1Ps5gXzIWqbLrY8\ncS5M3EeKBHM+lT84+wiv3TzN6twg4lALn7+C11nhE/wlDZzINfDdblAaCjM7vAsTCadSR1B07uNV\nnso9wZc3P82v7/ltzh57geThFfxykSwR1hkgTwgPVR7mORQ6tFEYYhNzj8k8Q0yLu7m/+jpIEi+d\nOMPEyVkO1m7iXWgiti1E2cJbamKpCsvBYf6i8LOgWpzSznP6Ly8RCBTZ+GcRUmIME5G93CZyIsuu\n1AK/cvVz/Bv9N/mK+nEc0TpbnhYND6CC1VSwZtvwhUVuB+JMHz2OVRcw94jIZzoMnF7GGyzjoMEn\nhL+iZAX4b2d+kkw7QjkXBAUOiNcZZpk3uReNFgfdbyHv7uAWavSxyWHeIhzJ8/TdUOAfEgn94gAH\n9hV55Bf/Bf71FNN0AcAOx7MdigJdULXjpjV2wFfd/m0Dqg3CdjTIncnm2vb8NXYAuBfwze3r2jy3\nHZ9tbLfb17d/t3mnU1Rmx3EpsxOt3QbeAnw3/pqfK1/ipc/9K25cS7DyP839HZ/ee0fuCmgX8yGK\nBHidkzRxIGFQxcMmCRYY7ZYe1SWoQ8xIM84CdZzsb8ywZiV53nmWldowAaPIce+bzFXv5Vr7CO5A\nCSsjUy970Iba+JwlRMlkKTRKWwhjSCZuoYqIQQk/AhYaLbDg4cZ3ELBIOcOMiQtotKnhpoqHLeIs\nMkoolsbnL9CnbjLEMrvMWfqaOTblODPqJCImbVQm5RlS+y4RUTL4hAoDrJMRy0SkQa4HjhDR0xzy\nXcGvFCkS4ApHaeFAdhnUdznJu/3ESTPAOkGhgIFMHynOBl/AoTUwHQJ1yYVDbPDN9qOIgkVC3WST\nBDIdJHQeKL5KG5WnrD6mJD9hcjzMc9QdGrfF3dxTu0bR4eElz1k6IyqWIaIKHWJSmi1HlJBV4DfM\n30UwDQRHG+HxNs8bD/LnmZ/mVOA8k/I0x9uXmVPH0EMK1w7toRz04BdKhIUctUQJ/UiNTsNJyJPF\ndbDI1i8m6LR9mJYCz4EwoCMmW7TcKq2tKMaiyua+fjohCcsSGBZXiISvMKitk/cFmTb38HHjSV6U\nzlERvfRJmxznIpPM0ETDJTbuhvq+7yV6wOSeXzZJrH+T+DdnULMZMPW3AdQ+nOxY1bBDcdgg0WHH\nsnXSTYKx+P97cm36xAZmnXdGktjUhthzPdvRCDuLhsiO9Wxz6S52FgbX9meTnagTe/GwD8vUcaYz\nHPjdLxI5upvNfzfMlf9XIHvzXeVj/YPKXQFtvaWSbcRY0YZxiA3c1BAxaeIgY0XJW2FWrUHAxE8J\nF3VS9HHGfIOAVeJP+RQ5M4LTbCJaJql0P0ulMe51nyegF2m1nMSsNBEyBMQiZY+X6eZeVtsCfcYW\nHrFKw3QSK2UZYJOWR+VQ9TZFIcAV50H8lBFpUCCIlzLJzir1mocxdRHZ1aEhOXFTQ7AsslaUjBWj\nSAA3NfyUiMtbdAYU3NTotzYY0te4pguESBEPbBKysjzm/AYZIUoVDzc5QKyTwS3UeDN+D3khRJgc\nu5iliYMiAcr4GBMWiAoZZpmgjUqQPIYpoRlNBlvrrDiH2RLj1Cw3HzJeIEYGhxVgnb1YCJziNRaV\nUa6zn73NWabakyyIwyQCGzjEJi6zjqtVpS0pOGjwuPEMpgm3lXHSRyIsl4apbflR3B28cgWPVWWQ\nVTacCc4PnqKDTJI1NJrISgdBtBCWQG7qOPo7+B+VqKYlmlNs/xdbiJJBQChQa/jZzCZYaQ0TJMuE\nMItLruN3lgkqBZblJE7qBCiCxdulYR000ZHJEMMwvlfgxz+KLdH9JrtP1zg2lCL09BtoT8+97VS0\nY6dty9eOCoEdC9YG9F7H5J1heALvBG47k9EWG+xtKsVgB7RtC/nOc3ab/QZwZ9alSJcb710YzJ55\n7fsTAaneJPn060TkPAMnLOqnYwi4yNx8f9Zjvyug7fOVyOb6OBa9TEDL00FBo7XNCbf5lvEIl8Xj\nCH4DWWmzzgBf4OdQnW1kdKq4CXsy9LNOQ3DRXlBR19pEx9KE+zPIfQYH5Otvp7WPM8/TlY+ymHcw\n1lwirmxSNnwcmb7BJLPoewUcRZ11Ocl8eJy64EJH5hqH+Am+wkP1F3ls9kUIG6RjEZ5zneOqcIRX\nxPs54rxKTEiToLsjuGe71nSUTDd+29rCX62jtkK0BZVR7zx9pPgYT3GZY7zFYRYZ5Wz9VRJ6ij8I\n/AqK1GGMBVzbhaoWGGOTBKc33uDexStUj3uphRwEKLLXMUWikGZwM8X84DjXXAe51jrEJ7x/xRl5\nkSPCFUrcyyIjfJSvscIQ1+QDfD74GVKlBLFCht8M/5/sEmfw62USmRxXnIdY9Scx2hINSWONQTbo\nZ5QVPi9+hqzgY1Ya43nngxwQrlPBy4ucYw9TJNjkLQ7RSjlpv+CCWYGsI05jl4uxJ6bJ1WOsNUbh\nAFh+GWVe4Lj3MlvBPpZ272LVM8gAq3yaP2OKPVzqHOdL5U9y1HeFoFbgVfk+SvjxUAXg6zxOkQBB\nimQ7YeD/vhsq/L6Ve37F5OjAJoFfexpps/K29dyiC3C2Y683ntqmG2yQtgHXPm+DsO2stMHUBhMb\nTO3IDhvwe4HeBmfYsbbtBcRuV7fnqgH1nnuWt9vhnRa7vaDIPZ82qEuA/OwC2q0s537vMTwHR3nm\n1/4RtL+n7NamaPkvUZR8rNWS5CtRZEPHna/hy5RpHXCQ9K9RkqvMqWO4tiM2roqHUdCJkkUTmsh0\nWGGIYiRAy9JYkwdJSOskpE1c1Ah2mW+KBIi7N4j5TXxakyB5fFKZuaFRKFnsn7+NuAW6X6I24qaJ\nRoIUH+dJGjh50zrB4/q3ceXrZKwY15OHWNDGaAkaV4UjHOcie9u3ia/kcGk1KnEXb8gncIoNwkKO\njDNEVXETQOSMeJ4+UrTQmGY3GyQ4wlVKDg85cy9eoVttz0eZGGk8VIm2MkQ3C4xUV5ECJhk5gkyH\nfjYJ6gU21CR/HHuMS5UTbJWSNAQXIjJBR5mY1aSGzgpDvMG9tNFICmsUhAAOVwOX2iQtRploLJAo\nZ3AXWuzKL+DLVfA7CtTcfWh6m5OrlwiZeQpRL3ktSENw4hJqvGScY40keTHEhtCPaJjMt8epGzmQ\nRPBC3551wkcy5K0oRW8Qhix4CdyBMv6xHJer91I0Q1gq1EQ3eYJkiHb32JRdeD0VinKAS/l7uXz7\nJCWvn4bfAT6D4lII6uA9VqNR8N4N9X1fiuuwh8gv9BHbeAbvN99E3qhgto23LWzbgu4VG5xtWqIX\naHst8V6npL2lgZ3WbvWMtWmM3ozI3rju3uSd3uvb2yX0XtteFNSeOWzgvzOz0o4ysReotwG8ZSCt\nlfF87g3CB2WSv/8ouf+8QeNa9W/xZP/h5a6Attpp4/VusUk/G/UBMq0Eom7S2VDp3FS4Z/hVYrEt\nJFVnqrQPQbdoKi5uOA/iUuuEyZHsrOOwWqwpA1TCXkxNpK2otFFpopEhipcKYXK0cBB3bZLw6gRV\nkSBFNKFFI+6iKPowCiJtS0a2OozXF/E6SsTlFPu4xbX2EXJGhJQnhlNvsKXHKePDQkCjhYGEu1qn\nr5DBKCqkfXHWzT4uW8e6FIcwQ9nhJ6uCaYXwG6XuxsHSIBtCghru7uYJBQW9LnMwfBPDKeJWKyh0\niJLuUj31EqIKqXAMXVUQMbrJNaaTdTXBRdcRShs+tFYHRa1AR6Ameqig0cRJEyerDOGhgma18FkV\n6h03dAQ2tQRzxgSqbpKQNnG3aow1apRDHloOjf7mJocWbiO4TJZG+jF1EdoiTcXBG+2TZKwY+5w3\nyNUilDs+dFlGcAJRA0oizvEa7oNl1kqDCCGLwEiOSt2HJjZwJStsbiYQLYsJ5zQRKUPN8HCxcy+r\nQpK2qHHAeQNJMMi3I9zKH6ZW8KBrMjh0lIxOTE7TZ6SotAN3Q33ffxKP4N2tsu9wkfBvz6B+c+7t\nCI7eUDzbyr4TvO/kunv72JEathVrp673jrMtXthZBGx6o/e70DOPPca2mu22XkvadoLaYoP0nc5P\nOxmo1zH6Nl/eMlC+Nkdcj3DoX57k8qSfRkp7X4UD3hXQvrB2hj724adIzLOJx1nCZTXIZOMsdyZo\nWE4kOliWwK3bh6jkA5ghkfBEikR0jVEWebTybYJ6id8P/w80NQdus8Z+8QZbxDjP/WSIcZLXOcZl\nnDQYYIMEJgkEYtsJLH2NHE5XncpRBxXTS6ie5Z+v/yHTfWOk/BEWGONo+RqOVpvL4wcpi17aosop\n+VU2SVDBy26muXfpMrGZPG+cOMaF2CkuyvfQFBzsYYpZdpEnxCpVVjnMk/WPEyLPh7zPEqSAhMEF\nTvPE81/l/pkL8JjA1Pg4y5EkqwwSoIhbrXF7PEqOMGXRz5g0T54gL/AgsqrjpczHeIpE3wZr5iAt\nwUHLEviOeB/PCFE8DBMjzTDLrDDIdesgl/V7yC/G8eRrJI+t8Zfuj/FFh5ufi3yBcWsegJvyfgba\nmzxQfA1to43hg4nmPFJJoC77+U70A6xWR0iYKX7c8VW+vPLT5Bp93L/veV6KbbEx2cKYdrBe76eg\ne3AEKyTEFB6zxtXj92KMSiBb7E1cZ5IZ9ghTtEWFq42jPFl4Al2UOOC6zof8z7KX22xE+/nDh36F\n+Tf3ULgahVkF/2NZxh6c4ZTrVVqWyo27ocDvJxEFOHeSsHuJUz//L3Bk8ijshPS1tj9VuhZtb9y1\n7RA06dIPNpdtA629MZhE1ynY4p18tC32HL0p8DaA2k7JO9PYbbH7ONgpIiX2zGVHtdxJ2Ui8k1e3\nnZ29C0mH7luBDIy9dJWJ2+tsnPt9UmcH4cvf+Juf7XtE7gpo7wvfZA8SAhaWKNDQnVyfOkrhjQhc\nFmg+7CBAgaSwhjags8kAa5sjFAJhOi2FairIVPQtor4M88U9CIpJxJmiLamUzAAFM0hZ8vGWcJg1\nkoywhJMGAVaZ5SQ13NxrXcTdqrMu9vO07xGyRIjIWc4Jr/Bt6yE2G30cdVyh5vIjaia6Q2BanCRF\nH8OsEGeLSabRaJOPBnhTPMrXg48hqgYfMb+Op9hEkEwqPi8+ykTJEeMmw9oyhiWRIYqORBk/qwxS\n2u/B6jMR+00qTg9rJDGQCJMlJmZQtTYqLTxUaKGywhBXhKNMMkOEbHcbMzmLhxpDLLO/dZs1I0mG\nKCIuBlklSoYiAYSWQHErQlN1IA7oXLGOUNPdGKLE8+qDpIQ4A6zjoka4kMe11YQYlMMe1pQ+Zj27\n2RD7eZDnOel6k6BVZExYYE/kFpW6l9ulQ4jCJgdGr2E9KtFKqLRVGVE2qdT9dEwnD37k22h9dQTB\nYFhZIckaQbPIc9UPcaV+nIrhJe5M4dK6yVIu6mxUkqRn+9F8TUKJNMWnIshndGoOF8/VHmbh+q67\nob7vI4kjWrv59NzLHBK+g7iSQrbMt4GzN77aSddqtdt6eWfbUu21rnudgL2bG/TGatv97HP0zNvL\neRs95+0xYs+43vvpnee71SyR2UkAsoHbTuSxMzV7E3vevud6E2llk09e+iLj5lm+wkPATd4PKe93\nBbQnI1OM4aGJAxmdtq5xYelBipshlO21X0LHK1QQhixaTY3114ZpaG5afgelfJjzgdMklA3MskTY\nm8XrKLFRGKCs+lGc3Vy+hdYYF9snOOF6jVFpkQ5b3GYvDZwc4S10JFJWHy9ZH+gW/1dTuMNVXq7d\nT6YTJaAVURQdUTbxCBVS9LHBAA5aDLJKknW2iJOJh6nH3cwyzgn9TX6q/RWcjQ6L6jCvcww/ZeKk\nOSm8hqJ1KBt+5lq7KCgBVLFNhCxyokPTryC6TSqyhwIBBKztED4TGR0JHdkysDoiomChSN04ZbdQ\nw0WdMHlkOhzhKnEjR0X3E24WGGstMGoukiim2PR1a7a46k18oTLucJFWW6VjyBiCzBXrKCX87Lam\nOShcRzQMsnoQ90iNctjHojrCC+pZFDp8mKeJdzI4rCYNHExEp9ls9HE1ey9eocrJ2Gu4YzXWGWCd\nAXRk1sojlCthnjjxF2juBin63na6Fggy3drNhjGAS60TdacRFYu3mkdYkYfJVmNsLg0ROryFZ6JE\nI+yGEmRux7lWOYL+puNv0LwfLQl6RMajCh9f/mtGai/wirVjndqgbSfHqD3fbUC0K/TZ1EUvaNq8\nsk0z2PHQvf2+G1feC9q99IhtLdvjennt3rHc0be3GJW9YKg999Ib9dIbvmhLb3x4x9Q5ff1J+txV\nFkdPs5iWKLwPcm/uCmhniTLPo/SRoo8UmtjGjImoP9bE258nEMujIzPDJA2cFAthrEsCpAS0w3Ui\nj2xymaMk6zF+NvSfWVaGuJ4/zFsvHie2a5Ndh2cIkyWdTpBKDdLYc41p724uIxBhgDhbVAQPVb+G\nixLHuEzailHCz6ywC7ezRgUvLwjn+OXS50i21/md2K8TlrPcwyUELMp4WWCUIkFGWWQ305Txsau2\niK/QIBsKUHM58FCjgRMRkwPcYJ1+/M0KZ9OvcSsyScXjYtRcpP/pNMGbFXjAInyoyMDwBgk2ELHI\nEOVbPEILB0PGKp/J/VdOyRd53P91ZuRJVKG7R+UkM1Rxs84AKUc//kKFT21+hR/P/jVqrUX4uTKv\n33cf9YMujoxdZEhaZlhewiNVuM5BLgnHqeLhin6U2/peqqqHbDjCgjfNIekauizTRkWl3eXlGWT4\n4iaJTpbiI25UpU1C22Ay/kWWtbc4yxz7uMVLnOM8Z3BTo111sZoeoZL0scQQN9lPkjWKBLgsHGMw\nuITbLLMmJFGlFqlaP+upEZzBMoYmoe+WKTgDOIMyod9JUfuqn9y/jqOLMoTfn97/vx8RuX/v6/zO\nz/4ui59PceNKF7Q0dpJjbHrDzQ6w2lTFnXVGbEeencxiW6x2n95IkzY7+6zblIl9vhcke61hG+B7\nrWs3OxRGb187WoWee7Ct9V4NMNlJhbfv374Xo+fTpkoMYBro2/0af/rzP8e//PwDfP3SMO9cOt57\ncldAW8Kgjcoio2SJ4JIbdAYFxDWdzjUn3hNVNFeDkuWn1PJDyGLfj73Fen2IQKDAo/5vMGtMYpgy\nbVUhvZ5gZXGUYjNEdPt1Zl6foOnUiMZSLIkjeMwKXvMyH2l8k6iYZlUbRJE75AnStByYgkjeDPGa\nfoqIlGNQWu3GRzs8VGU3E+Is+zu3mDDnWVUGMEUREwkRkyoeinqIE/lLBI0SaW+YmkNDkjvdkL92\nlau6wIucI0IGh9zmkvcootKmP7fJxLUlnK0O9TEXc4OjGF6BydIMQ9fWESWLXCRLcTBAzekmYmWJ\n6lkaopN5a5z+pS0capNmv4PBzAZS3aJlqFiqgCha6F4Bv1bCX60gS3C8fQWxaTHvHEYQLbKtCDfT\nh/C6yzwUep4lRkiLMeqyi2VhCFMRqSkuynhJ5/q4tHIvhVEfg4EVXDS4nZzkhrGPrBjEQCIuplhW\nhzFFET9l3NQJkSdMrlsiN1hHbTZ47a3TFPUAKUecZ8YeYzi0SFJbZVaepIYLFzVMROqWi7Lu365J\nYWE1wSXUcfmqGEGJ9pBKZ1OFMCjDTTp/dDc0+D0umojziRHkeIHyy3OU0tCwdixNG6B761nbFnGv\n9dwbFXLn5ga9c0jsAOedaei9NUB6HZY2DPZW+bsTcO23AdvC7q3PfWdVQLHnsMfb7Xa/XprGnreX\np7dDA5uZKtWXZ5HPfhTH5AjNLy9B570L3HcFtEVMHGaT2cYkTqlBTNtCSTSRlzq03nDSN7mFq69K\njghqu407XuPIp66izOh49SoHpBsIqsWakGSWXcxkd5NNxwlEioR9WRSrw7wxTr9/gz3hW9zW9xI0\n84yyyE+2pmgJGq9Ip9gQ+8mJYUqCHx9lGjhJ63H2mtOMNJeo1LzggJrLwTnhRQ6VbxBrZlFi/4Se\neQAAIABJREFUbdbEAYoE8NDdybxghDiRu4roNkkngjRx0N5+UQvoJQzDwwVOc5w3kTSTi9pxDnAD\nz2aN9i0nzSEP63sSXBg5Qb+6zp7UDP1TaQxZQmkbnImfp+50IgsmkqwzoxzkOeFhfj79Z7icTWYS\nowyUr5HIbCG0AA+sR/tYCyfIekp4azUYMDmqXaOvnuI7rTNc0o5wpX2Miytn+GjfX/GB0PM4aRCT\n0lQlDysMkaIPn1WmZAWYLu3jpaWH8cbyBAIFBCym9kyySpI0Mc7yMgOsc52DSC0LV6VBw+1EFdv4\nKbLECFbERJLavHnlJO1VJygWz7sf5iHPt/gp7ctc5yBlfPgoYyLiFBu4HRVktYXYMlHbFklpDUVs\nsFQYxxwWUcNNpKSBP5rr7sr7Iy0ykuxk9KwTd1nh0u93W20OGnaoD9gBULGnjw2svQBpi+3E6+W1\nbd7Y4J0A3Tt3b52S3lBAvWdsL11iH/YGC62e+3bwTgu99/57rfg7a6HcmY1py50LRHUVrqyC53dV\nRibdzDzpxuw0ep7ae0vuCmhvkMBquqhcD3Ew+Ao/NvkkXxGeoLnXSTvU4szAy8h0mGWCe9yXCGzv\n3t039Aw5M8J/4TPdolPACkPUdjkYG7rNB8TvMO6cQxdE5tVxjnCVj/EUb0mHCQoFUkwTFApoegdv\npcoF970U1QABCvwEX0ET2xS1ACdzlxleWMV8TULZ24a9FpV+B5HbRZQNHf+HSpwPnOYm+/lxnqKE\njwvi/XzJ9TM84vgWP8OfcJl7mGeMCl4mHbMUlGuc4TyLjL69y84l7iGdiFN/wsWyNsSSc4SCHKCJ\niidUwfPjFf4/8t48uLL7uvP7/O7y9n3Dw8PeQG9A781ms7mKFCnRlEWVl0i2RhM7YyeeJFPlymQ8\ni1OZqqTiymScSjw1k7imKmPHsccqWWNZlCyRFLWQbJLNZu8b0Nj3hwe8fd/ukj9eX+I2SNmyZTfp\n0qlC4eHid3/3d1E/fO+53/M958yIw0w7Jxn2rgDQlZ0QFayKAQpyhGtTR1AkjRVphIHBTcKBPO6s\nhhGAasBDVsTJOJxE/QUi8SrFqA9NFzzz7ptc7zvF1egZGm0PRT3MCqNs0U+UPBMsUCaISpcwRc61\nL/Jw9ArRJ3MU/GEkdM7zBKP0miN4aBAnyxjLHGaGi5l1jlyG0sNe3N4mblrU8VExg9RdXowzgGzA\nokAWOl3ZQZkA4ywRoEoLJ0m26bgdRPtzbClJFHeXw8dn6XNlKBXCzL99BNdYk/DJPGFngWFlla8/\niA38sbYozuYgv/y//wGT2oX76otbgTfYBTg7VQAfLKlqJa7o7KaC24HQAmKLBrE8V6tEq1XHxA7C\nCruqDSe9ZJm91IZldomh9SbwYaVbLXAXQNW2Lu6t2apnYgG6VTtFoleH2+LkrWM68KXf/UNOyIv8\nj+3/nBbrfFyDkg+mNGs5SXt2lEbZx3ptlGv1hxia2MATaJD3RCmokV53dVMnd7WPvJnAdbLOYecM\nSrfLYvEgR3032O+eRUZnx5eg43Og0kalQ4QKz4nvcoA5EuxwSlylhYsF4WPD6aJ/a5v4TB79rIKS\n0jhgznOkOYOJ4Jr7GPF6jqFqGhTIe4IUPUFqwksz7sFUZMqOAH6q7DMXGTVXKYsQHclBLLSNrgim\nmbynDlFwiA5pOUVGypAhyQqjpEnRwMMnMuc5VbtBv7KNsmTgN+qUH/LhcHeoOgKU+/z4l2qMLy7j\nOtLA1Wzh2WnjDdWZDRoU/WFW/CNEKBCgwo47gV+qMyBnwGkiO3uAG16t45ztIm6D/AkNz0CdaK3K\nsfhNzjjf4z35MTxSL0XcQKKGDw8NwhQZ0dZ4uHuFfjIYHsGAss5GJ0WmnWRVHWFcLDImVnDQYai+\nSZ+Ro+F1UfIEWYjEGK6uokoawm2QIo1LNImZOa7XziDiTYKxInlXlGynj1uuo6Srw4SkIg/736ON\ni9XNUXLvJIg+kic0WsShtnrhYNcmxcEYmWQcNdjmBNeI8ndHW/u3ZQPHq5x4eom+b84irabf95Yt\nILaKQNmlfRZYWrI4y0u2l1y1g6Tdi7V+tnvQFlVizWUPXtppFXvNkb3yP+thYj9XtZ1vHdtLzVgP\nC3uhKXvjBMV2jl0fbt2/XcctL2+SmJjlE7++ws3vNUjf5GNpDwS02zUXjRU/7lCThfJ+NjYH+VLy\n9xkNLLOt9IoztXESNktcv7GfbaMPMdXB66rj0jqoZZMxdYWH3e/ho8YS+1hlpFeHmxBJM8Nn+SYK\nGm3hYJg1NruD5DtR1lQFswSxyyWKB4OIlMEwq6RaGYpEKLij1DUPbZcKU5DdFyUdTdAxnRQPhKgL\nL07aDLLBFLcZMtdZZByfqHJUvYWQTd7icbzU389otNY2zSQVAmgoNHFzducSL2a+heGRkN6dod1R\n2R6PMKfsZ0ftZQSOrW4weWee9bEkwUKFwZkd6IeZkUmED7ptBx7RpM+RodH2kjH7CAcKSDUDb6fO\ncHed/mUN5xUNrpp4JpoYfQJJGDzsuUg95GTTP8ygvMmBzgLr8gg7UoJ10dOIH9AXONhZZMsTY0tN\n0jKdrHWH2WCQqJLHLZoMGpu4um2GK2lcRotZz37m4yrhiQkOrczjEl1Ud5dDzGAKwY7Wx9LWYZz9\nDSZOzXJr+xTVbpC75mHmSkc4Lt1g3P2n3BTHSK8PsPzSfh4deJ3IUIFMp5+D6izDoRWePPs9LnCO\nvB4l1d7Co/ykF4xyMjaZ47O/uoh2I8/G4i6QWUBrmaUcsQO3XcUB93u51s97Ad0CVSf3e/IWkWAB\npAXs1jWsgKLl4VqyQSuI6WK3trYF4hYnb5fqWeBuB22rPredr1Zt3xV63rj1gPiw0q8SsGGAPpTn\nM//VecrpMdI3Q+yGNj8+9kBA+1zsHaYeq7KuDjOvTbCqDXM1coJ9LLGPJVy0CFEiLmUZ/ql1LmkP\nc1U/wbwxwahrlZ9JfQUcBm/xONv0ESNHkgx+qgyzSj9bDJo9RUJeRFHZ4fDGLKfmNY6WVBYOT/BS\n/EWuJE/ioY6bForfRGAQpkB5wMtCfBjdlDE9Jik9Q7hZ4VXHc9x2HmGEVaa4zRjLlKQgZQLUmj7+\n9PIvIIV1EkfTPMbbRCkgoZMiTYwcQ6zTzxYJdoiSY7J/nk5Epej1EVAauDId+mYLrOkdskNxppnk\n0IlZTkzcwB+u4HHX6DpAycNIe43nuy/zyJ0ryC6NjUNJDk7Pk2zs4E004BtgNtvEdUHpsQEKI0FG\nP7mG4tUR6yCWITBQYdy9wKcnvsUj5UscXblLMrHNZe8prqin8VFlSR1hSR4jIyXIkGSLfuouL5Pc\n4aelb7GPJUL1MqMbaXxqnS1/r0SuzhKxeg55Rid+MMvBvjkUNCoEKDtDiEMaQV+RCXkeR6wLwsBL\nnU3GuNk5xv9a/E1qkhdjVGL4f1ggM5hgvTxEYb4PY1Rmo28OPzXqeNmsDvLHN3+Zc4M/yX1rFOAo\n/u9fZnjpPKW58vsUBOx6kfYgnr2QkwVUFqXQ5oPND6wsSrifQ4Zd+sTOYduTXezesMVvWzLDOruA\na63V3tDADrqwW6LVqiroYjdt3gp+WmuxvHfLg7a+O/igXNCeBm/RQMrVHJH/4nWcS0fpdWC/vvcP\n/5HbAwHtcXWBZ8I7XFIeIixyHOY2HZw0Ol5utE/00pYVnayI0xhw4dUrJDrbuESbrqxS9XjJNFM0\nW27inm2QTHLNGGtbY6ypY6z6x3nC+zq6IlMiiJc4w6U0wZ0KxcZ+SkNBPMEaI6zgo0ZEFMiqUZy0\nOchdGh4vC54xHHTYoQ9vs8nz2e+TDG+TdGYIUEFHYUck2CbJsjlGVsQRQQOPt4aHBh0caCiEjSqD\nO1tk0xkev9FCHu7iDdeIs4Nfq9EynGwG+qlO1PBFm3SaDgrOMLopM2Ks0g46uBo+QYwc42IJf3QF\nNEi6tnjEfJeD0golOUCaBCHKBOQKukuiOuRDayvoW3X0uMAwBGSgLAcoRCPkjsYoJgIU5BBDgVVi\nxjYIA4fSpi2cbNOHhM5aOcZs/jBKf4eK6merPYDhAFMVaMh4200cHY28J0zJ5Sft6ScnogT06ySl\nOm8NnKMd7L0ku2iRJUZZDTCYXMOlNqgKP5JTo5804/oSN8QZduQEK8oo7SU3PkeN0JEVcpsJSrNR\nmpf9zPZPUj/gY+TkEm2nE0OXWasO4qn+3aoZ8TdpksNg4jMVBko5Gj/Ivg9ae5NTLLC0e6MWRWEH\n4b3NdO2dYqzPlgdv94btgUu7wsPenMDufdtpEJnd8qr2twK7WsXuXdtridirBlrHrPH2mifW7+yU\nkL0crP1dzQC0Yhvp3R2Gn8lyIFBh6RUT7WPmbD+YKn9GmQGtyrw0TlTO0W9myNDHDzqf5LuVT+NT\nahiK4ALniLODWzQZUDYJaDVabRdvG49RrMXpJ8OnXS+TlyJMN49wZfYcDZ+X1OAmhhv6xBYCEx0F\nT7eN1iox3z5AV5N5XH6Luu7FQYeIXOAKpzGQeNR4hzelJ1gVIwSo8DqfQOmYPJq/xKhzGSXcoo2z\n1+Hc2EemnWROHKLkCPHIsXeJiywSxvtBvKBRZt/mGpsbmzxzcZm7vnGy4QgrjOItaigtnWy0j2I4\njBQzKBFkgyGcRpvn9Ve4IR3nTelJnLQxTIWU2MEbaRFxFHCLKt5Yh6rsxal1EDETTZJo9its/3yE\nlnBR+fIOireLZ7mF+p5J4VyY6RMHuDM6RVkOIDDpZws9BJlQlDQplhhjnSEkDNbzo9yaPsVB/y0M\nn0y1HMQRaFKWgtxRpniscYkuTq4PHUGWuve62niJ6nn6XTr/7ux/g0+qMs4iDjqUCFOUIxwIzlDF\nzzpDdFGZYIEj3CapZNiR47j8NfLzLnTDQXfUQX02SPNiAC7Djj5A95gT76EqilMjLBXJu/uZZvJB\nbN+Ppakug8d+6QYTS3Ns/mDXk+yyW1TJCsBZnqlsG2N5v3a9s10u12E3uGenEOB+wLYDsV01Yk+H\nt7xrC1gtswcT7cHRvYk3lldtUTqWdwz3vzlYa/kwUMc2znq7sOazzmvdu+8mMPnZu0gjLjbOu//u\ngrYQQgIuAxumab4ohAgDXwFGgBXg86Zplj/s3Glpkj9zHMIr1SkR4l0eYUHfT1gt8t9G/w2r6sj7\nKgYTQbaaJLMxiLyuY2RkGnkPqSfXiR7d4R350R5d4buNeVqgKzJuV5M7yiRZYgyyQYAqxgSIYzrn\n6hcpbIUppXyMbW7gk2oYKZ2EtIPa0fFVuih+g6IrzAyTrDJK0FPm7v5x3K4GOjJV/OSJslQe583v\nfxLXUINHzrxLiBIOeh3PlxnjNkd4U36S+Yk3Ke5/lePPa6jRNh1UXudpQrEmx7K3OX31JjfGJ7mW\nOs4Mh4iR54CYo6b4GBQbPMdrdHCQV6N8xfh5PpP/DrK7S9qdYHxjjVizyMnobZRkm2rAQ1NyEC8U\nMZGQTIPwUgXfTgvpEYNUcwf/+TpT6jxb43E2hvpZZow8UWLkUdE4xF0kDG5yDFd/g5/yv8RU6Daa\nLLMQnWBHTZCS0nyKV1n3JckQwy8qFAizxjDz7Ge/8BKUVnmG7/UoFbw0cfeCkTRZZ5gIBUZZJU2K\nHDHelJ7k2cgrjIgFXuM5qENjxcd6dR9tj7u3s/p6uy7UKfKo+Q5OWqy6RtgYHsThl6j+mP8AP86+\n/uhMRW1IPPXb75Cq3eU299fHtjIe7RRDk17qurLndx3beXZFCbZz7cE/u31Y3RG7nM4KaFrUiwXE\nVl0TK3XdTm/Ya6LYu9dYnLmd37aua3/DsAKT1oPAfh/sGQ+7csKW7bgJnPr9q8Q8TV6qforGB/Iq\nP1r7q3javw5MA4F7P/9z4Lumaf5rIcQ/A/7FvWMfsG0pSVaPM79xkK5bpRF1MVc9zCF5hkHfOpcr\nD7MpDeEMNPFTwyV3MJwO0vlBKhsh0EARXQxZcLc4heZW6XenkRK94klxPcdAM41fqeJ1VfFSR613\nkSoG/Y0dCAryBPF366hShy0RQ0GjJdxckh+iLIJIGNTxUC6FaWpeZsKH2C/P4aNKF5Vb7WNMt6fw\neyscck8zKW6xRT8mAgcdgpSp4aUowoiggerp4pI7OEQLB10MJDp+hZruYbsdp6m48XXrHKwv4nC1\naDldvGI8j0u08Mk1nLRwGBpuvUrN5cFltvCUWsjCwC3aqM0ul9Tj1Nwe+sgwIG3jMho4TAWHaiAF\nNQiC+7Um6nobz9MN5tUx0q0Bhrc28fkbVKIBQpQYIE1bOEkzgN+7win3VUYba1R0Px5PgzpeouQZ\nIE3JEQJMwhTpohKixAireLpNAtk6Jyu3CCUq5PoiRCjgb9UY6ahoHpWMkqRCgCoBJEq4RZOwK88E\nJk3dxfLEftKuAfJqFFMR4DEhasCOoFn2sDI7jiPepur2MRpZJugp8eaPs/t/zH39kdlQHLz9tBbn\n6eZz72utLbrDrqbYm/5tmT313MqchPuDkhZvDffz1gr3e+d765TYrwEfLEZlD2jar2mBq6VC+WH1\nT/Zee68ixKJlWrb1Wr8zbF92GsWx53fadI52pIZ59jDcWYECHxv7kUBbCDEIvAD8FvCP7x3+HPDU\nvc9/ALzOD9ncdbyE2mW+eutLJPvSnAufh5xCwRVn1TPC3NYk22qCVGCFcRaI+XJ0J2b4wZ1PUQ0E\nkEc09LhMreVnZ3OAVp+bDfcAChoJfYex1gpfzP0nhK/LuqsfAHVeR74u6H5KoeNTMYSE4RGU5SCz\n0kEkDDKOJC9FHmKcRcKUiJFD7EgU6n0s+CcYFqvsM5fwSg2yzQQz5hT/8Jn/i9OOy/jNKufNJ3q0\niNTlMDP0s0WWOE9wnoXGAofuaOwcC+J3Vzhm3sTtqrLSn+L7/c/QxzYna9c5np7hRmyKl6PP8R87\nfw9V7jLOIvulOT7d+T5Ptd9mMT6EURFMbK0hYgY6Eu2uk++pn6SKl+d5hZCvjEtv4NG7mAMq7Y6M\nUjEwr0J7WSH7KyF+0Pck04Up/s3Vf0pjzMFydIgJfQEhTBzyAAeYY8Jc5CnjDfyFNsvKKJueFIeZ\nwUWLOl72sYSPWq/HJRpBs8wBfYH55g7+5Tb+G+u4zzbJJ4J4qRGq1zEqKpuOFEvKPm5wnCxxznGB\n01zhKqdQTI1fFF/mvScf5iqnuC2mKN7oo1HzQrKLGFXYmU/ylbe+BP2CxL4MTx99hcNi+scC7R93\nX39UJp/sh1SDK2/foJ4BP7tALe/5ssqx2oN+dk7Z0mU72fU24X6VBuymw1uUhl07bQ9AWmZ5z9bc\nlpnsFm+y0yd2usbeod2iMqzUeqv6n2V23tykp8G2wN+uDbffu11uaN2rY8/vZjW42xdE/pUziN95\nB/PvGmgD/yfwG0DQdqzPNM1tANM0M0KIxA87eY0hXnU9xPjpu4y6VnDrTeSczppvmNf6PkU2Gyfk\nLDM5MU2SbWR0yoTQp0xSoys8GnsHLSxRdfhwDbc45brMAJtc5zjLd/bz58s/y519pzjqv8Ywi9zm\nCJNHZ2g9/k1+d/JzSH6dKXGbXDiEJhRkdBaYYJFx0qQ4y0X62aJAhJ/q/yZBvcJBZYYDq4vEKyVc\nB9qc8l7GdJmMKwuodNG7Cs+lXyfj6mM+OUYHlTg7jLH0fnYfOpimRLRZ5Mncu9QjTmZ8B7jBcQbZ\nwFNvMTUzT+VQkFbcxTnnBWY3JpkrHGHkwBotp0pFcpHQsmSdcd4YPkdKTmMgsWX0U3IFAZMaPrqS\nCm2BUgPPa1rvnfQsiGFwdTX6cgV+IfBVSsqrJJI7NIIOHHqTUKlO1+nC769xhRSRdhl/tY3SMGh4\nPGwywBwH0FCQMNCR8dAgRbpXFqq8xcG5ZXaqVYgAp+C7/c9y0TzNr4j/h6yvjw3XMCG1iIc6OWIE\nKFMgzEu8SIEo5XaIl+qfo6wE8TlqPOk6z9LoBDtago5bwf94HW3EwfLMfrSOg3ImxNvK09x89zTw\n23+tjf83sa8/Kvtk4jXGRt7m6M0NYFftYYGqXTJnrylteZ7YxlkUiUVNwK53btEsVuDyL0rstuaz\nxloA2d0zxgoUWoFFa06Lh7dnXFqUiPUmYQG0tUaxZ04rbd16KNgfJtYDwZ4Zal3HUqZYa/TeO34k\nOM1jp/4Rvx1scYtH/4K7f7D2l4K2EOIzwLZpmteFEJ/4C4bujTO8b5u//XW2/+hdQs4S64eiBMaH\nKOX+nLrk4+brOu131zAdVe5eWWPV7PUblLyr+DozqHRpOtLkRIyCEaZjOFmQFslLJVZoszG7Qy6d\nYHHCYD1a4qAnS4ZpMuTorqsEvrOC36xSM5dx11rUhI91f5MGC+Qos0KBb9AkTpc276Ggs4POAvBa\nNoG36SVxbZuM4yo1MrxMGzc6zk6X7raXjqtFO75AjigKOhHyzKCyes1PvQLyUhdFKaF0DKo+DxvO\nTdKcp8sOVFcprWrMre1w98Ytqiwj56/SVzeoX5/jGqtk2h2EapJTG2SUOn00kQ2Dsilx2VxAEzI1\nqcYl00VIC3L7Sp3uhkFTc7GZGyCZ2yGmF+DlFq3YLC2nyp2KSs3ppuMSDOZNms4K6fASWQxudgr8\nftuJ1lZYUGUu+IsUyxISBtFQDp9RJWRWKBtF1pQq7lYL57bKxdsJrvpSACzf1am6b/N10SEjIqzg\n4xhL3C1Pk6724Q+XabqK5OUSTdxUukEK7QhRKY+s7NBQM9SMCZpEUSWNkNhErWu0NsbJ3snT2lhh\nw21Adm+Y6Ue3v4l93bOv2D7H7339bZqEdmmR5twN5lcNKuwG6+xdYCxAbrPLd9vpCrtm2xpvr5lo\nl+rZKZMb7AK4HcTt2ZF7i1FZX9YDo8sHHwB764jsLU4lgFt80KO31mXJ9vbWRLEeXna6x851271r\nay5Br72Zc3mHid/5Ft2lIXrs2V+yFX5sy977+ovtR/G0HwNeFEK8QC+W4RdC/CGQEUL0maa5LYRI\nAjs/bALjM/8EHv85gg/PU3Z4mK0mCUWKOItOKjdi8MdQ9kP5S0AHRhJLPHnyNU5K13HRYpqzFDhF\nqTtBuRoE9xYhd6+zeed6H9JaEPVkjVi8j0mXyjnKSPRzk3H+8ReXGDQ2cHbauK/qXHeM8ocPvchz\nvEUJhd/nOe7yBVrmCr/EH7DBIHfFIeaZYNMYIGbm+OfSv+Kw6DJv7uMNnsLHOkOdVf7v5V9nwLvO\nC0Mv8T0+SdV04WeNLkUEbxD4xSCfSL9DxMyzlhrAKzWomS1O0uAAacbYwGHAFRHEJQ5yXjzOF/g6\nXzL/CAMZ93oXZ1onfTjOTjBC1XSyD42wVkRvV/hV41+yoQww5v5TAlSJkaPiuM1TX+ywYE7wp/wz\nfi3/e3y++jUAcmEvW6E4awwzywG0uo9PTf8xSrjD5rgDL/PoyNTEBHmibPIoOe3zZL4zQkpO89Cn\nvs4Xm1/hVOsGsgZz/jFuuQ/3KI3fh1de/CcAfMHzFf6B68/wMcBLfI6MeIL/jH9L7fxZam/+17Qe\nbrJv/G1e8H6bVUbJEaMjHHyG60TJsWyOkW5+lqw5woBnmc+LP2GMDd5lkFdv/QI38idxHamgrbvo\nnPL9CFv4b2df9+wLf93r/zVMAB723+xyhGsMmL3FWV6ym90KfhZ42akSyxN1s1tP2y7Hs3o7YpvD\n4H4wdQCfZRf8rC+LQ7erSuwetQX+Vm1r68Fhz4i0ANkC7L1JPyo9LsvioK0ApU4PZFt8kDu31mQl\n8ti799ivZ5/LAMqAexOO/p7BV4kAp9ltMfyg7H/60KN/KWibpvmbwG8CCCGeAv570zT/vhDiXwO/\nDPxvwC8BL/2wOSYG7hI+fpm6z01c1BiVl1GULtVgkMzRBoVfjyOcJsGpPI8ZbzPmWsItaiwwQZZY\nr3cgXpytLsaGE39fnYPuWWLkiI/kcMS6LETGCasFkmQwkHDRIkCFImFMIfAoDfqHs6TkdV7km0wz\nyRwHCFNknEVoSPz79D/ikfjbHAjNkaYfRWh0hUqGJBIGm+1B5lammNZP4BV1Mmv9mP0mF4bOoSNT\n17xcbJ9l1LVCmRVe5SyxcIF9LLItkiTJENIrPNa4RMYVY1Y9yIS0wKi5gmn2dNAhUaJAlLBepBr2\nsuXxo3ugQIRlY4yR4iYuQ6fjkjjjuMx+ZY5j3CSVy9I1Vd40olxmAEery2/kfgfV3eHd+Cli5JAc\neq+SHh6cdHA4i2zti9F2OMnpEU4VblFUPcyHJ+gnwxgrTIlpGvEwWRHnDe0p3GqLqhHgydY7/MB4\nmmsc5Si3eEJZ4qRvBwWNLbmfr3d+hp1sio5X4WB4lhAlJg7O8kzkVTZS/WguldvaUWbuHkV3SKQO\nrvMtPkNXVyl1gyyn9xMxizy17w3aspNNBjjGTcpDYZyJJqbfoH90+69de+RvYl8/cHN4YN+jZOpF\nfOsvEeB+igDuB1CLp7XGcG9cwDbeOmZplu31t635pA+Zw5ICmnwQbC0e2WRXRmeZJbmz0yD2krBW\n2VS7/M/F7luEdY5d9WJx4Mq9z9b1P4yGsdZv3Y9d7WJ54k12pZGLQD0yBInHYekCdBp81Pbj6LT/\nFfAnQoh/AKwCn/9hA0PBAu5YnWw2RtzZYDS6gsCk5K5hOAX1p7x0Sw6ktIFjqIUj0ELQA6occQxk\n+tgmKCp0ZRcBqUJSz/Bk6y00WSEd6MflaNKRHOyQQEMhSh4DiXn24xM1BuRNArEaoW6JE5VbvO5+\nmjV1mBRphlinYfpYMA4hmwYJdjjJNUY6G2iGyqpzhKAo4zJbaLrC6uYY7bwbFPAmK6SNFHpLRdMU\nHKKNjxpZzcHl2lkec71NQs0go1PHi7vdZjS7QbvtpCT8KAETR6CLy9vCRw231kbXVFalEcqeIHW/\nlwi9euMqGltmChMJj1zjpLiGJmSGxDpuU2PVGGGZPkLs55A5x7Pay9xSD7PpS+KijoIYx/q2AAAg\nAElEQVRGFxU3TYKU6SoqW9E+BCayZlAx/Gyag8xxkO495e8xcRMt6WKdIar4uSsfJKVucdJxg7wc\npmM4OKjNkxNrnHTWKRNgujPFO5XH2UiPcTBxh6lwr4hDJJFnKnqTUilIfj1Os+pju9JPJJLHT5US\nIdJ6iqXWPoaMLR6SL3OWixSI0MHRa/wQyhInQwMPLvlv5R/oR97XD9okr4T/E370NTeF9V2O2k4t\n6PQAy14DxDJLd22Blb06Htyfii5s59vn3luKdW8Q0q5WsQcq7ePtHLU92cZeCdB+TWsddoWI1Une\nuia2MdZ17KqZvSoSc89nuyLF+rvo9EQj8oiD0MN+KhkJw/4E+ojsrwTapmm+Abxx73MBePZHOa+B\nm3Rjgvy7/biTHeRHdVz3cvpbuEi7UlSXfWT+0xBf//s/y9BDKzzku4yEwTBr+KiSYouO14HzUBtF\ndHG2O5zdvsa/b/xD/g/pv8M9UsbvLhMQFXzUGGeROiu8wVPEyfIo7zCgbhJqlAlmGuQH4tSCPp7k\nTZy06PNmODgxTVPyoKDxS/x/xKpl1psj/FbyNzgm3eCk6ypXDp2ivBBg+60heAFcsRY+o87N7GkG\n1XVe7H+JUVb4047JrY39lFIRlGCXUZZZZJxmy8fQ+jYHri9ilkGaNLh88gSXxs8ww2H2NdcJNht8\nI/wiWSnaK1TFEkOscUZa4wfRZ5A5wkmucax5G6feouT2MxOb5B0e47pQCZBi2LlOq18CxcBJmxAl\nKgRo4WKE1Xsp5Ck2STHGCvvkJW4mjnJLHGOWg9zlIOMs8Yi4wKGBGVYY47J4CAcdCo4QmUiEfWKe\nEW2Fs42rvKPFucQZ3uYxbtROs7o9jpGRcXg6OGmTI4aMTqRbpDwbZfn2BPKmxuAXlhk5uHhPwVPg\nrn6Yu/XDfDr1bX7a8032iUXaOMmQZJpJMvRRJsAOfdxsHfsrbve/2X39oM0R7LDvi7PEL27Q+fZu\nyVFL2menQyR6HqO9Sa5FhzTY9cDd3J+YArtBQLvu296yy8Iti6bYq0zRbOPsckR7gNQCVRf3Bw7t\nAGwBv3U9yyu3jtuDnJZXbXn41nzWA8Ou67b03y12vevOvbVYQUirSiBAeLLAxC/e5fbLHVolPnJ7\nIBmR2/kURteNXpNJbwxycfpxIsM7OH0tNBR0Q0Ya0VG+0ME9Uafe9XNx7gncySquYAMHbaaNNg46\nyFIXVXRpqm7mY6Mc0y7zPxv/gnCzzJoY5IZ0lNtzx6n4wwhm8TBG6J6cb1EaJ+0dJNhfIW3202h4\nUN0dBsUmstBZk4eZyC0z0lnDnWiiODukxDp/T/zHHhdoNvkvu/+BC1MzXIidIzmcYSy8RL+0SSyS\npy55yYh+JljE56iTSG4w7T7MoL7GZ7Vv4lZa6LoKLZAdBkSBftB8Ch7R4FO8xmR1GnexyX7fHC51\nkA4O/FSp46NgRDmRvY1fqeKM1pl2HKYkgrRxUJaCNHAjizYrjPKq9Gk21EESYofR2ir+1RaLsQNc\n6HuYbfrIFAagKvEzfV9lNjfJ7639GvlwjII3QtkZQHJ3WHcNse4Y5KS4Too0z/EabZwMtLfoqxao\n+YLcdkyScad4V9lGNZ9kwZygqIcJOCs8NvUGz1a+xyMXL+CYbHLbP8W6MkhgX5Fj4cv01XdY6x9g\nfu4g228Oce6583QGVBRnl20lwXXpBAtM9Hpq0pMQHmCec5138RS6vOM4y799EBv4Y2J+UeVFx0sM\nKbd4i10aw5LD2YNtlidpUQ1WxqS9xof9n98CQnto155haNEadk/WkgjK7CbuYJvDCo7KAlrm/Ukx\n9qCl89759gClBewWyNtbh1kPKMsLt3hqixbZm1lp3ZedU+9FB3oSQXsQ1rof2TZ+Qpon5fgGK4zS\nel9j89HZAwFtdJDRwQHlRoTGuhcp0SHpSxMzc5xpXyETTrI0NopS19HLKpW2F92AWttDtRRAeE18\nnipDrOGlTlt2UPe52CfmOKZfx1dpc9k4RY4I5WYU4dCp0MJNA5UuJoJOx4khFAgZaHUJb7fBsNik\nT93GFIJ6x8++1VWGGutkwyGaDieSYjIuLdx7RXcyZU5jDgMTOl5qJNkmQoGUf4M80fdbcxlCQnV2\n2Jb6esBjDqNqOn7RpBlyIoZMVFlDHxA9HTkSEfL4jBpCA9nUiWl53HqLsFpiXRrkLod4unseJ22a\nws2aOvi+BxvOlhkw08QNAwPB3fZh7uYnOR68jqpryLXLiACUCHGRs2S0AfydOo+aSe52DvO92rNo\nHhW32sQvVag5fZgmOOkwyQxxM0s/W7QabrytFpJmEuxWURWNO45DlKUWESQEJhElT9Rf5HT0PQ4v\n3yFRypLVw2yRZEkZw0zqDCQ3OWTOkjeDVFaCiJyMu90EWcflbrKp9HT4PmpkiVHv+nBWu3jcLSbE\nAvu7q6wbQw9k+35czK01ObtxmVBulQvsetT21317Crg9C9EOQrALinYQ/TDAtubfq/awj7cXerKD\nvAyoYneMZfY1WmtxCaibPeC2OG9rbXYd9t4ApT1Jxg7wdkWJ/W9jD4Tau+Qo7Hr89r+HCfRXtziz\nfgWXloSfFNCeiM5SdBeoD4bRck6UtsaYscoh7jBkrvN0+W0uyw/xT2P/C5XpCGGKnHjkPZxqm/x2\nnK33xvAeLaONKawwSow8w+Y649oiuiSxKg/TCrlYYgSXaPKrJ3+XAbHJ96/u4EKliYdlcx9Pld8h\nLu1QjPoY8qyjNg2ezb7JZiRBV1b46dx3cN9q0akrdI45aATclAlyk6N4aRAWRW64jmAiOMItLnKW\nbZIEKTPDYVKkeYo3yBIn0/WwuT3KgcQcZU+QP3b+Ij9X+wbDyhJbJ2IkSgWC3SqtmEzV4WaTFIuM\no/gFTnmGt9VHmWrO8kz9NdbDSS45H+IN6Ul2UnGG73VaF5j0sY2PGieuTNPWHNw2BlA5xK38CW69\nfpKdkwk6+1We3/8a4655HsXHPPtxRtsoEZ2vyj+HPGxwJHWVshRiRFrhmLjFO+IcLtHiYd5jjGX6\n2GbUWMGV1mkaHlb3pTjXvsCx5i3e8j6Cj2nOUOT74hmUoEbUzOOUmsztG2d2ZII76hQzHGaZ0XsP\nqAIyGj5RZXLqNicmrvOC61usyiN8w/05MiKJieAwMzzMJYq1CP/v9K9xa+QY7ww+wunUVd5bfhT4\nnQexhT8WJtcMQq/V8a73qEU7J93gfgWIvYiTBX52wLN7oPZ0dwtw7YE/y3u3quxZZnmndg7czgnL\ngGbeX4wK7ldpqIAigSqD0EA1d5Um9qQgi86w9NSW5231pbTTO9j+LtbbhwX6du/cUozY6Rb7Mcsc\nixqBV5pI9b9Iqf7g7IGA9lpmDHEjxIm+K+TqCVZm97F+YpAkm0xK02z3xZBEh+flV5jed5QmLjoO\nlZZwgt9gavI6kUgel2hQx4OOQl5EOS8/QVxkcYgOLtHiWOcWh7tzrLoGeUse473OBt13nqfPm2Ho\n2DprvhQZYhRFEI+oIxyCN0KPMVpeIWhUSPsTBM+U8bQaRPUy6W6SbUcfO/RhIvCIBm6aeKnTRWGT\nQZJkmGSaxr16ZVnijLLCQ0qRZyK/xbR6iMvth2lWfEw5Z0l4tqg5PBASdKoqoaUy4/EVHLEukmYy\n3lzF3WgxFZ5GdXa5Jh1lVRlEwuCnxCvE5SwKGk3c3OIoASp8gtfxDDeIF/NM3ahSzmfZCuzwuZNf\nQ0m0OVicw/12G+2AIDqVZ5I7OOReV/gKAapKgJISIkOyp/4gSYIdAlRwmS36zS1SrQy+cpuMr48r\nnOZrhZ/joPsu/a40DeGkiRtTwJO8QVs4UTsaBzOL4DFY8Y8wW5pitj5JR1M5mLyDPu/gu2+9wM6R\nBKnxDYwBwSXOsFjfTzkbg0WoF8OUHHFmg0doe12U3UGqVS/BdIVo4ruMx+Z5/UFs4I+JmQ1onzdx\n3CtuaOeKrcJLlppCZhfA7V4j3N+s1wIre9KNBfQauyBp2OawzntfGy6gY+6CrP0BYA9M7g2YWtfT\nTajrYJq7nr3dw9/r7dvVH/bje5Nn7P0q4f4ApXV9+7nWeXYPHKCzAdW2ifHRC0eABwTapWaUUEXi\n6KEbFCpR2otOcvkEK/4xRkMrLKvjqFKHh+TLSEMGK+YoJUIYpoTPV+PA/pleF3fa7JDABBShc00+\nSdTMkzB3SJLhsD5PVCty1TzOdU4wb3qo5o5DFyRhkPNEaOAhTaq30aUWGWeCSKGIMGHbH6E+5STQ\nrSHXJXaMPjYYZIMeaAboBTkLWoSiFmGFfXjkJi61RZwsdbzU8NJPmiFlh4nge+QJstkYJNvqo+QJ\nUnF6qd4TXbmbLZRFk+HGJkltG7feRC0b1DoBfMk6WVeUkhykW3IwKKUZ9yyiqxJVyccOiffle22c\n3B04SNyRJ9xcxmxXiUTzPDR5GYD4Sh7nTBfCMgEqHOUWblpEyCOALfpZZh9Byqx1R5jpTjHiXCah\nZelvbKN6NJq6m0rHYDU2yHVxjO/ln2XBO8aEY45B1qmyTgsXo6xgInB1OpxI36YS85D1xSi2I+Sr\ncZytNtFokXIpyK3Z42hdFb9UpTPg4A5HWNPGcNa7VOeDVJcjbMsDuA40kCY0jAHo1t1oJScjsVWC\noRL/4UFs4I+FSWhtleyM+IB+2fKMrWMWZWAHSpNdxYZ1vgWmFiVg0RKWKsMCQbvUzzpPso2VRc+j\ntmgY+xqsB4a9UqCdOzeBrtkDbnuNEuv6duC337P12a733ltPxF7O1T7e/uZhrcEuPdyrjGkWYaco\n0O+LInx09kBAe2B4lcgTSyRdaSam5hhMrvPSWz/PzdIpMk/0UVpMcMAxy4uTX+MAc5gIvm88Q1Aq\n46KJjxpR8jjoUCbI45wnSYY/4fN833yauuljSrpDx/ltzjgug2QSJ8uAuknrmXkCUpEODlKk0ZHZ\nop82DqY6d/mZ4p/zWuRpMu6THJFukybFbSXKhn+QrlApEOYqpzjKLfrZYoVRrjVPc6N8kobup+N3\nIUV0VLqk2GSYNWR0Vhnhz/gNfpEvc851ke/1f5L98t33a0wns3kGlndQtnXkbQP3bAfhNhEKVPwB\nvq29gEDnTPMyz1z8PilXBiZN5sL7cDrbTHGHMZbJkGSBCV41nycYLjM5/i9xJwz8VKkQoI0TxWmg\np2TkgEaQMse4ySITzDDJPhZR6RKgzBhL1KohvpU9hT4gc7x6m5+e/Q7fnnqWy9HTjLmWKcphBDon\nkxepyr1Sq3W8mNzAROIORzjKTQ53p3Flm6y7+tlW4njiFbyuIp26k4rDj/aQRGA4R+UrUaQ5A+fj\nHRx0SPjSPDJR5drWw2x2RqAIfQc28R6vkCZFvRjE0e2QEltMcudBbN+PiblpI5g2FYbY9ZAtztfS\nU9u1zEV2a3/YAdnqOgP3y/8sz3mvZ6pwv9et0Avivd+T0bgf9LHNYaco4H5e2rw3p/VgsXv59rRy\n61zr3iyz1uZnVwliSR0tELaA27ove9DUTodYNIs9M9K6XhVYQaFL8N5MdT5KezDtxmQV02tyl0No\nNQfbtQGK0QjuSI24yCL6JGSpS54IbpqkSPOweI8mLly0UOmioVBpB7leOEPT52XAv0YNPx3hpI6X\nBh6uSidZZYQVRglSYkRaZdD3XRx0EJisM0SJEBJGL2CoyKR9fSSdaQJyERNBEzdp0c95+XFctOhj\nmxf4FsOs4aXBJgM0ul6MtsIXA3/EicY1ItkC5wcf5a73EFtmitHWBgOdNAeNL3NaXEGVumiSzKXq\nWW7pJ3kk8BZ+fxlTNWEapEGzl/1sQjcqIQ+2eNT5Np7FFofn50h5Mzj7WpS9PpblETL0oaAxyTQq\nXQpEaLmcQIANxyAv1BaZ1Oeohdzk5Cg+Tw3pkIGz0qF1ucPG5BBOT5t+0mwwxDKj71M9q9IgHVXG\nLTXQvBLzw2O85zlDU3KRkLaZZz95ohyS7qIjYSKQMdiky3Y+yYX3Hqe6L4RrpEPywA65QASXaPML\nypeZ9+7njjRFNt9PoR2l23Vx/Mw1xsPzCMNk+dYE6cYARkKmFvXCkS5kFcpyGKWisT86ByGJqJ7n\nXflh+tmil/7wk2BRTFw96vDeEbum2fIOLYpib2DRHqxUbL+ze6mG7ZidZrA8ayf3z2lRDxZgGwKa\n5v2BPyugaE/SsWuy7enyFiDb3xKwHdtrFgjb9dXWd/v89rcJa/3WZ+teG/fOtcC9y/30UQs3Bvvp\n6U1+AkAbUyAbOrdbRymUE+RrcbSEg2CoSKBbRUoYeOXqvUYCHTzdBqnaFjveODhNHLSp4WWzO8Sd\n8hFyaoR9/nmi5OkT2/hFFYUuq4yyZI6T0LP4RIMiHQ4yi1XoaJkxCkTQ7t12U3Wxqg5wuH0XV6fF\ngnMcd72FQ+9S8oXwS1V81Pg0ryJjsMYwHVRMIQgrRT7p/w6Pti8g5wUXE2dY9u6jiZtPam/i1pf4\nKfNlvFqDjnBwRLnNd9vP09I8/LznT/C3KugFgXIXRB89+d8mtPwq+qjJKa4QzZVJLe9Q/6SXzFCM\nrDtChj7uGFNs6gM45DaypLNFP7JLR0dmVQwTaa5yQJtnOTgIGMhuk+q4F+f1No4Fg53xBD5PhaSR\nYVvrZ0sa4I4yxQYDlB0hkv5NPEqdusfDfGCMTVK0DCer2iib8gCmLJhggQAVAMoEWTFUZkuHeOfi\nE6AKfAfL9E1s4261SFSzHHffYNCxjmLo/NnCYar1MP3eTR4/dZ6gv8hKa4z5mcOkK4N4TtboJgRK\npI3mVih1Yrh22pyKXgKPQavt5nuZ50j5NoCvPZAt/NFbBJMEBu77QMnyhu1NcO20gd0ztfO20p7x\ndrD7MEWJXV8t9oyVAEn0jrW5nzywgNTygveWXLUnt9glenb+ey/Y2k3wwbVa89r5dLvu3O6BW2M7\n9N4eLMmg5XnvrskNjAMbwBofpT0Q0B6Tl4l1xlldPkDL7SQ2sUVhOclWbpByN0RfcgOXt9fpREFn\nNTvMNy7/PN6TJcaGF5hkhk1SrDsGEfE2R93XOcMlygSJk8VJm7d4jAAljhp3eKLyLhfUs/wRTxHA\n+37Z1FVGKBImTQoXLfxUezWfi02cWptYf47x+TVGKpu0zziR3Pq9tHiZNYa5wXFucYyG34XfW+C8\n8ji1hJeB0CYFVwgHbTw0eNnzLCWnhib180LhNRLmDsTheOgqStcg3izh+3Yb6WUTkWY3g+ACVJ1+\nNo4PssoIE2MrRANlbvRPsuwcJk+EKAXUTpcL9XMM+1dRHV2ucJoqfsDEYILrsQBOs4Euy3RwUFUC\nXAod59jgDCFvBUXVKRFC6PBc7nWc7i6b4X4aeBlwbXLW8R63pCM9GoctTnGFS+2z/LvCr/Op8Msc\n8sz09PXIaCikSTHT9ZE3nqMx4iUXjnKNk2SJ8zPpb/LC1iu8fvQxlgKj1AwvWk5m0neLnzv8FY46\nb3K1eZpvZn+WWidANJTl+OFLrDmG2SqmKDc9mG2BUAwcZoclbZTFjQO0vuZj5Ozyg9i+HxPzAFF0\nlPdf5y1dsx2kLYrC+mypJBR21R9WqrvMbr0OyyO2gNLuIVtmedRWxmWLXRrCad4vEYTdB8HeWiJ2\n4DbpebcO21otgLfPYT8X7uevrYcWH3ItbOOF7XOX3Za9Oj3KZG9m5/1zKEAIyPFR2wMB7a1KisL8\nJOV2mIg/y5h3jkKyxE49SdGIMmHWOKzd5dnu67xsfIpVeYTDI7cY9K0ywAZR8qwyQlNx4fNV6coq\nWeJUCHBIv8sh4y5VxUdfPsfp3HUmWCYT6SOJgWCMDQbZop8dEnRRcdBhnF4WnoIGDgNHuUPf+Twu\nRws5oTEl3yZLnA4OSoTYIkVN8/N86busOwe445nkevEUEbnEGe97nJMu4KDNrDhEW3bSlRx0URHb\nIBkmelTmIfMKwbUqnm81kTERDwOD9HbcQu+7t9QkOlsmPaxRDAZZcQ8g3DpdSSVDPxGK9MtpTjmv\n4pdqgMkIqxzcXiBm5LhqzHBQbRMwyzj0Dr5mk3bWhXemTqBZw+1tcagwT6erossyc64JKo4A4yxh\nIigbQaZrk6y8O07b7+b1x3YIUeQR+V1GvKuMKKtI6KwwipsmMXK4abAi15Eib3Dh9OP8/+S9eZAk\n53nm98ursu6z6+r7mOnu6bkPDDAACBAAQQCkSIJckZLlXUmrK8L2htcOy7Fr/SGv7Qgr1hH22rsb\nofXG7kq70q6WpLUERVIgAeIgwAEGmAHmnunpnr6P6rrvOyvTf1R/6JwWaNIiNUBIb0TFTGVlfplZ\n/dWT7/e8z/u+SqyLjMlBFon5dpAtg4BW2qWkVOYmrjPmXCPqTtPARVvTCfuzhI7l8TtKODxtTEMC\n3cI3ViRglIm5dmgoLto46bY0ard9bDB+P6bvx8T6vq6FtKeBZg9EPeypHuwFnuy0CdwbQBSgLMBs\nf60OO40hzin2FUWWxANAeLZ29Qi2ccT4Te6lNPiQa1Rtn4lxxbWJLEi7p28PPto729i9d6HNttM8\nglMXAdT934G4z/42O8v90dp9Ae3t+hDmzkG6CQceV5WEmiKcyKOUe5QKIYJykQlzlZPta/xB71fI\nucN89vh3ONq+gadZZ8M5jCyZuOQmY/o6XTTWGQXA1WtyoLdES3KS2MkxfXuZxqibwcA2R6igMcwS\nUxR2+XJRuP+UdZlp7oAEHa9KJ6si3ZSpnvNSm3ISUzNU8JMnQg0vLZwEelW+XPlTbnjnyOhR5qtH\n2ZZHkCWYci+Rkwe4y0F8VOnS7KtdqjFaPZ0yQSZ7Kwyt7aD+RwN+FXqflunsaHDXwkrLNA+4kHWT\n4GaFSCJPM+AkpUZJ1DPElQybrmHcVpMRZYsHve8QpEgHnXFW+WLxmxwy5/kj4DgqmtXFYXYYq22j\nr5rwCtSjLlqzTgaradqSzoZ7mJf8TyGpJoe4DcCl3hlu1I5Qfy9IPeqj+bDOF/kGpx3v8ZTjZZY4\nwALT7JAgTppJY4Vj7WvkmjVmzTbWlIRLajLRXOWofo14NEU+6idJijRx1hxtTk1fJEL+g79jSfMz\n6N/APCIhSyZ1PKiGgZcqht/BQDOF3yyTzcSQAyYRLUedEKXNyP2Yvh8TEz6r9YFnLJr1ivRrhb2U\n7/08rqAH7K3I9tMOAojtwT9p3zj7QVR433YTnnRv33Ei8CckiiJL014yVUCj/Y4Fd29PaRefi+uz\nZ4Qq3Atsdk26xb39MvfXIbFnlArZYP/8FtY9GpOPzu4LaI8NrOI+c4UNdYSGrrPKOBOs4qWKhUQd\nD7fVGf7U+zlky2BE2qCHwvBqCr3b4a1D5/CodU7zPklSVPHRRidKlkElhYM2h7u3cO10aa65ePfE\nSeRIlwTb3GCKVcYJU6CFExUDJ21GWtuMsc22K0pZ9bM1OsjtLx2m4XOhKR2SpAhSJEAZFYPD3ETX\n2qiDTbqKhK60SCbWuVg+za9n/h3BwQwDWpZjXEPFYBuddUZ5afg5NKvLWeltSo4AjYFFjhxaQI4b\nVCNOVqOjKNM9Wh2dy+opPEqdIW2TmCeNhInVUhh8K0s8kOfQ8dv4ek3eVR9gwTXNNAvU8PI+p5gd\nu0PXkti6XKFAl5BUpKG6ka0qut6EWbg+O8etwzOEXEUWlGkuyWe4Ix/kaetlTkvv8QpP4dbq/Fz0\nW9z45WPsqHFy5gAZOcZ1jpLjk+yQ3K0S2GaTYULVMuduv0f8Uo1PtN9h9sEVZLmHqUrszERIu+Os\nM0KSHQKUGWeVIEVkLFo4qeFluzXElfIpUE28zioxb4aH9Au0Nt288OKXqV4Jo5R7WJMSZ55/m7G5\nDdK/PEqn5IR/fj9m8MfBmliUMDE+ADZ7gkmTvXRwAXbiJUBJqCYEUNn5aqHYEMVHBUVhr9EN96a7\niy4ynd2xRZKPvfOM8JrtdUNEvRLh6WK7H7vSRID0j4JKe6KQAFnN9hL0h8ReLznYS7+X2OOxxQNF\nVCUUD7a9oK0BlLi3f/tHY/cFtOOOHZ4MfoPXrCdoSC68Vo1UJ4Elwzn/eR6XXyFKhpLqR6dN1fRx\nuXeSuCeH16yxLo1Qx0t8N5Flm0E2Ge57wnKYPBHa6NSHfJQJsT0QY7S1wUC+yEOtCww4c5hIDLFF\nkTCXOMPryuMscJAqbqbkJfyuCk5XnYvVB8iXB3jU/wMiSp6gWWKwl8KQlT5H7NQIU+AY1yg4w6wb\n45SNAOlcFLl5kxMDVygSwkmbaRYohcI4621OrN4k5k3jDdapfsHJyqFxCu4gA44sO1KMohEmUcsQ\nSpcYKOSJOvPIQRPTIeM1GmSlMGkljiEVKSpBClaY4VIKv1TGGWix7hohQ5Qd6V2K1Ai0K7jzbbR8\nr/8rGIGFoYO8GXmEE1xh3jrIVesoFhIb0gjneYQ0cQxZQ9O7+EbKtCwHLdPJjdIx8lKUwcAmIanI\nuLHGbHMRdJN4L423Vkd3dAkmyjiDTVJKgi1lmE0lSZoYbRy4abKeG+e9/FmODV+mjpfb1SP0/BIb\nzVEqhRDugQqtjJvUayOkT25h5RU633fSdTv6NFIYdL1LzJMmdnQbd7VK+n5M4I+F5YEGEq0PgNOu\nr7b3Vfywinb25T/7tgnQFjSHUI7AvQoLAXbC0xZd0sW4dmC10yr2h4PQlNu13MIztnvxYgz7cR9G\n0dgrBNppEftK4QN1C3sSPzvHbde7i/OLhKM9KWILiWX66pGP1u4LaPup8LR0hR0pTpEQutnhQudB\nkvIOz4a/yxPGq/RMlQvSQwyYOQpmmOvmURiEoFKiQIi0GaeLik+qMCA5yBNhiUmWpCl0pU1JCZI+\nFKM642ess05gq44vU+fZxjdZdE6xyEEOcZsbHOUF6Xm+rn8JNw18VHmW73Kcq8TIUKgNcLt9hAPe\nBRSlh8+sMlTfoqr4yDiiVDU/frnCMa6xwDSWF3oOleu3T9FrqfgHKlTx4aHGCZv/Ie4AACAASURB\nVGmdoLdEqF7h08uv001q1BNOSs97uCSfoECEL/N1Nq1hql0/T+X/nMi1ItYCGIMK0riFFDNpAptK\nlKscY0xfIyNHaJs646V1jsvXOBq4yr/iN1hgGrhNDei2HHhSXcyGQhcFNdkj44+xzCTT3KFpuWla\nLkbkDVJSkhd4nnFW0ehStzyYloyPKiGpxEZ5AkvWOB24iGKYjLU2eLL2BoYMpizRdakYcYPeSYn6\nkM6ic5zr8lEauGngRqZHC52F7Azfu/Nz6KEmBWmAV9LP4NRq9FoqUkkmHC9C0SL14hhX4yeRqya9\n2wr8IvBUf7Z2/Q56NYWgN4/HU/kbBNo5ZFroNP9C+raLe9USduAWYCZqa3dt+9rBEvbkfwJIBaiJ\nYGDTdo79QUB7L8oPAz/xkBBB0v3BRQf3BjbFfdgTe8Q92Tl4u7xQ0B92XvrDgqLiOHs97/08vlgt\nCMB300Bigb8xtUcyxDhPkjwDNHEhSVU+7XqZw9JNTnCFDWWUMn58VPlS+VuUCfBK4DHW5DEKhPFS\nY6Ots2kOc911jMPSTZ7kVYbZ5DaH+GP+NhImUXJMtZY4feMqY4VNrhugm/107TY6r/IU1ziGgw6u\n3aSdEEXipKnj4at8hWh4h180r5BUtoiSJdncwbVk4OkUcHhNrk8dIuseoIKfYTaR6bGlDnFi8hID\nco48Eby7T+NrHMNHhaCziBS3eDd6kqw/zCHpFkNsE6HQp16sm8z15vF2a2BBJ6CxfTaGM9bEmSvw\n5r8HV3KNn3MWscYNcr4IitTjcuIoltRjiE2e40VqeDnPBkFUNrxDvDh9lIO9u8z0FhjsZjjsukED\njShZQlKREWmDk1xGxaBOv263SJFfaB8ECY7r13gy/ioOqcsWQ1zJnSFgVOlENMYcqzgcbbaPDpH/\n5mXU13MEP1FnenAJp79FgTBOmgQp4aPKpfBDmAdk8u4IlgNGnUu0nQ6qrQCtlslR8zrqdJvm33di\nJCW6C26sU1J/bdsCPPD+Kw9wuzRH9WE/lrlfAPbX2Vo4KDOFQYw9r1GAjIc9ikGA34dlH8IeB233\nQEVtblERUNheIG6PKrFzwsLbt0sIhe3XVgsgtlceFPdRYe9h4WAv0UXou+0a7/3Zj3Zv3/7AEfy3\nSKQx9h0nQFtki4r4gElfiS2ODwDTGDgoA3/pTkk/M7svoG2gsMwEddw0cdOVNIbUbeLtDKOtbV5y\nP0NKSzBhrbCttfBbFZ6xXuJb1mfZkEYZYou79Wly3ThX9BO45CYRM88N4zBZOYasmiTYIUIet9Kg\n7nOT0QYohkoYToVws4Sn1mbTP0pWH+iXMiVIBwcGKnkipKsJLmw+yifjr6IHm7xvnOKMcokxdZ20\nL4bPqKLrbXxyFemuRXC9inlSxuNvcKxzA1etjUtq4aBNUQ+wRBuNLhli1Jx+6gk/N72zSFqPGeZx\n0aSFkzvMMJVeYWRrG23HhArIsoVutHHkuqhLEFmEQKfO8E6dtqYQj+dIhlJcdx0hTYwZ7nC6fYVD\nvQXW2gZ54xR31UlS/iQ6LdRel2w7xqo2SgV/n1+WysR3/dQeCjImTVyMsM5RrpGTI1QkPz6pisdV\no41OjgHWuhNoZper+lGccp0RaYuQq4Smd+h4HKT1ATS6HKguU89mcLmauAINqrqHCd8yj6qvo+g9\nVK3LnHyDm3eP0t1wQkYiM5RAH22gznRp5dy0uh6sM+A+VMUzUsWnV8mnouStKHFvikom8GNm3l8n\n66E6ugyNWvgbYG3fGxC0qys+DNTs6dt26sSuFrFLB+0p73bOGNuYlm08wUXbPVvRDcbu8cKeVFGc\nx54ub99mB2ph9roo9gQZPuQ+xPULukd8R9j2F9+DPTVfrATEKsETgtiAhbLa6ad/fsR2X0DbY9Wp\n46GLRtfUME2FjBKl3A7RK+jc1I6wqQ3ikppc9x1ltjfPrxn/hivSMZq4mGCFa83TZNqDbETG8Fp1\nJMvkm+0vMOe4xZPqqxzlOhYSJT3InUNTbPXiZK8tUHRrBApVotslPuE4T0AvIWNykyNU8VHHw5o1\nSr3sZ/vyGNlTcTR/hz9rf46Ao8yc6xbL0+NEyJO0dhgx1/Ffa2C9orE9nGBcX+PZ4vdRVkBWoTuk\ncD7yAFd2Mzuv8wwb+gjhaB4HXSZZ7gcYkahYfpasKQIrDQ68v9l/vMugeQ0G13NQBWsRHt5dP0pF\ncDZ7JDtZ5gK3eFl6mqvSca5xjLH2Nofadwm2DeaNOd6RTzPc2yRLjLrkoePSuCidJUOMOJkPdOob\njCBh4aS1m2V5k4d5i4bmYYkpGrhZZpK26aTXU3AoHSxFIkWSpukm1ClzvDrPuq9H81CAu7EJhuQt\nJnNrqFeyWDGJ1rROSQkx67yFw93kdZ5AxWC0u8HKlRl6axqyw+RK/hSOcAuPq0Rvx4HZ0OAB8B0s\nMTK4wiTLXPOdItuMc2TwCsuXDvIxqEl/30xxQ+gRCdcWsN3fJgC5R99btlMKwqMVgTk7tSAokv1d\nD0XpUhG0FAAJe4kpXdt7QW0IesROzwjQtXvM4roEmDtt57FLAR22c4hgpGXb114BRLONK7aJ78Gu\nOBEPMju9IoB/v0cvHiQaoA2D9wzIGfrNIz9iuy+gfda6yBgKL/MpTlau86nSa5yPn+U91wmuxY8Q\n1AtMcpcZ7rDEFC3ZyYvac6SlBB4ahClwbuBNznbe5rnGyxhOWNLHWXeN4JTb5ImwQ4JhNplghXVG\nGdgsElks8c3Sb3Lbc4jOoM6Yc4UmLuaZJUmKKZboovGo8RaWX2L+8UPUAi6KSpDnXC9yQF6kSIi3\nOUcXB8PGFs8Xv40nXqT2pEYvqGJtKCiXQYoCPZAXTUadG3hwscExGrgJUuIUl+9paKDQY9xY51zl\nEolStj8jp9kLofvprxlN4Iv0Z3cG2ITx3Do/P/RnDPu2ueA4yzs8yHfdT7PgPMD7rjuUtQe5WT/K\n5fWH0HoGCfc2j4z+gJZDp0yATYbJEmWBaTo4GGWdCZaZZZ4oWa5bx/hW+QtUFB/H/FcxkTlYusvT\nK69xfvBdNkODuKQ64/VNEoUcynYP1sF7uc5xxy3MpEVNceHPtyiEAxS8AQZKJZpOF1uBNlO79U4S\njh0+/dh3mGjeZVmepBtQabl16qaHJ8ZeRo7Cd1vPUtXcdBsac65bFINhOj6VoFrAWWj9iBn319N6\nXpnSZzwYV5yY3299QFU4uVfDLJJfhKTOboLSEJ1Z7P0aBagJVYf4XADo/voh9qCfoDPsQGlPsd9v\nEvd66zJ71QcF/y7G7tj2E561CIKKxCG7By3usWt7ie2w50mLzjoWe11+YO8BIqic9qRM/Rkd63vS\n3xzQDlBmkiWOkGRALtDVVFqSk7wWpqm5SJDGTQMTmRgZFKmHU2oxwgZd+g0CVFcXVTOwmuCSmsSk\nLJPqCl5qxMhQJkADNwo9KvhBVag7UuhyB8VhUPJHUdUh6njIECNJihE2SJLiaOkGRk/jbOIC88oM\nza6b5xvfJqlvU3QG2GYQFy0kyaKohKgNe8kmouAzMRoKG4EhYlIOF21kh8VArYCnGe4n12DhokmI\nIj6zSrBVJlSuELBqWLKMpvWQIlZ/1ocg6w9T9vgZ0LJ4Ki00Vw8GIBWKseoaRXUaRJ15Ju+uceXg\nUaSwhZsGLrWGRY+K5qWi+KjgoyDFGFK3GJDzHKovULTCpPU4BcLotDnA3V26ZJtBtvsyx3SF7oaT\nmfgCpkfmRPkKGfcAfqVKT5c5XX2Pw9Z1mlGdnqRwxzGNw9uh7N+kN9Ai3C1SN3VqHhfbkwHW4iNs\nOxJE1SJl2UeRMDImiU6aQ60FSrEQeTVMBQ9dVNqWjtdyo/gM2i0n1qJEJ+omH49xVzqA6ZDwKlW2\n6iMU5fD9mL4fG2tqTt4dO83QtgOL63/hcwFWAqyF12kHdOhPNcGH26mE/VmQ9hRw8d4eQLRrnIUH\nbgdPu+rDroXer2SxVxa0X7cYVwC48Nrh3pT0/UHY/asJ+7nFv8KTtif12GkUe6GslD/JxdFTNFVR\nQfyjtfsC2lXZR5QsT/IqV/3H+SP/L9JFQ7faRMnSQmdLGqRmeThoLjLFCmPyKhkpxibDrDDBcm+y\n31zAHees/C4JUkTJMMMdhtnkNZ7kLR5m3RpllHVygwPkD+T41eAPOMO73FLmuMsBFjnYT+3Gh58K\nn+NbBDINip0IZyPvsqaMYnUUPpG6QHdAIu8MYaIwZS1xSnmP9XCShcg0mwxziFu0x1QuJw9z7tL7\nOOU21qSEN9/CVe03+HXRxEKijc6x3jUmK2vod0ykLmT9Ed6aO8PB6WV8sRrStsVKaJSF0Ske4F0G\nqxm0rR5kYWHwAH/63Odx0uLB25dIvJnhUuwMd0IzDFnbPCa9wRBb3DYHcFg5PM4a1UEPZ1xv80Xz\nmzyTfpUWTrb0JG10DnGbWeZZYwwZk5BVomvp+BfqzHzvOrN/+xayz8KXbnMtOcONwBxfDzzPV976\nBqe3rtAOwIvac9wemMMbr1I++l3qn0qjpKx+F6CAiztPzTLPLKvWOI2gG1UycNGkh8xM8y5H8/O8\nHn+ckhrcLWFg9Dl0qcEC02ykxmi/4INzkHIM83XlKxzwLeI1G7y79Sht/8fjR3S/rIqfP+t+gZM9\nL3D9A75WeIx2CZvFXoq6ADMBToJGEdSHnUsWlfZgjy4QZaSFByyCknY5oaAUhMcqEn4EOMIe+ArP\nWHjBLvp6aQd7Wmn7mHYQb7NXE0R48WLVYOfB7d/F/vZjQr9u5/z3p9GLIK0MLJrTXO5+iRrL3Jve\n89HYfQHtVcbpkqKBi+7ugqSGl9XWBNVagJ/3f42eLvGK9RSvvfNpwlKByQcXCElFumisMs7Na8dJ\n7yRZjB+GEYXT0XfwUeMqJ/gBjxOgwizznOAKx3tX6UgaL6BwmRMomLhpcIr3GWaTODvU8bLBCO9y\nljsjh1gyp0grUXxUOalcxelpoWgSEXJMscTlzknOG49w0nmZDWWEJSaJkWGMdablBVyTVUqym1Ig\nSNPlohiAgd3gXm33XEklhTdYJ3i4jOuVLoHXqpz99hWKT/m58sAcPn+VSCnPY9czhJQizlYXRoAe\njDnWeJJXuc5Ruh4Na1ii6vKx0priTvkIkUCBJ4zXmNl5m2D5ZVBkvr3xBW4kjmGFJe5EZ/BotT5f\njZsmLm5ziAlWWGaSK8ZJfmPrDxliB+mEhc9qke8FWUwe4H3XSZboPzTfmHmENXMYl15n/K1N4rU8\n7z1xHLVtIjdl5qNTnHee4wZz+KiRIcZqY4KtK2PEwylmDt1Co0PGPcBV9RCD+hYHCHCNY/RQkLAw\nkYmQoxN2UX04wujhFZLDmzj0FhXVz/adQbr/q8bJxy7y3v2YwB8T65QcLP+HGUbW7zDAnj67Qh8g\n7UkrdnAVFIi9l6IANSHTs9chsZcxFbpqAc4me9SJnVfucC+4iuuyl4MVAC6AW7ed3x4QFfcg0wd0\n2FN/2AOf4sFj11/bVS52sN5fMEqUaLUDtwBscZ1iRZK/FWHzT2bpVDb5GwPaBcLcIkyOATAtTlmX\nWZdHKbdDrJSmyLmi9HTYYJSeorNujHGnNs2gcwO1a7CTH2K7OEy5FIaKxIJ3hmh0hxE2yBDjDjNM\ns0CcND6q9FBw0MFHdfdJ2yNCfrfMa4cGLjYZIdeO8p3q51nyTpBz9lOiT3IZn1Ih5wuh6F3U3WPj\n6SyVfABlukeyncZXaRCMl9CcHRS5RzuiYq3LSBctjDMymtZmvLXBeQ0KSphtBsnJA9R6WwRLFaQK\nOLY7DN5NszA9xY1PzjLhWeFQYZHR9HZ/RjXpz3wJLFWm03Owlp0g20pgjqikXVEUDGRMbklz/WCi\ntMqMlOZB6QKrjgPUFSfLyiRFT5BnjZc413iHWs3HqnuUojdIkCIaHZptF/7rNWTJZPNwkrrPQ04L\nse2L06Pf+zFPhErEyxZJdkjwjPp9Rq0NqiUv73clblmHeL31GD/sPsqyNsmE5y5Vy0e5FeRgZwl3\nr0aJQD8grWnUNTcdHOSLA6Q3h+jKKrJu4vI0CQSLDASyFE8OMJe4zqh/lQJhSr0gDdlNJJjFvfPR\nJzrcTzMbJqXX68j1JmH2KjvbO6QLcBZALHGv5wn3SvTsQTl70onIthQ0wX7lhfDQ7dw0tm37gdKu\n1b7nnviLHrVdtSI8anXfOHbqR1Ao4oGwP+PTnsUpKA9xj4IvF2Bup4J0IARY612KrRo0PnrlCPyE\noC1JUgD4V8AR+vf2a8AC8FVgDFgFvmJZ1ofS9D0UvsVnKBLic+a3+JXev+WWNken7eJC+THeiD6G\ngxaa3GXw7DaNmo/bmWOkQkmkikXj3SDWqAmTJpxXSI/HWWHigz6JPRRWGadMgB0SnFce4QEuMsx/\n4ijqB7xyhhgddHQ6RMlys5bk6wufJ35gi6gzhZ8KPRRSaoIbgRlC9D19jS6/sPB1Zm7e5e3EaQa3\n0xy8tcK1p2epuLwsy5Mk5W1iFwqM/o8pSr/vJmkYPFLZ5AX/8xSVEG4aVPDTy6q4X+qiGiYkgIsw\nX5/lVZ7kEc6T7OWgt9mfUSvAdSABa9Io3+0+x8vXPsOOI84fnPw7HHDf5YC6gM9ZY4VJ/lx/hnai\nyWH/PI/wQ7rTKtc4xipj/YqInQKPFC7CMtwcmmHeO4WHBgnSHG7exPtmjezEAO9/9ggrTNBDYYAc\nx7iGlxoXeIgx1nDQ4f/h5xk6t8VwZYNnV17hXXOCb2if5w/nf4s8A+jBJu0xjbrhJtwt8rsz/wur\nnhF+n99glXFUDG6RoYaX7GqC7W+M9+95AJiAB4+9STS5w+SheU5xiShZXuVJGoYbbazN9P+5yMbv\nDv1Uk/9nMbfvq7UbcPs8UekWIxK4rH5+nsaeVyiChi72PEnRLFdkPAovWQC72EcoNVrcq0YWXqjQ\ncmvcy5GLfT6s3oc4jyjMJDx3O21i58btJh5Ggr5wsxewFEFCe0ak8KCF521P8Olwb9q/fTUizi28\ndUEX+YBDgD+/Afk3+Th42fCTe9r/F/DnlmV9WZIklf5q7HeA71uW9b9JkvQPgP8B+IcfdvBkZQUX\n6zzGGwzLG1yXjlKQwnTdCmqsicdRw00d05TJLAxSaftREw26dR2zI2MdNCAjQ0mGGBT9Iar4mOU2\nD9x4n63UCK+cfZxMIEpdcuOmQSBfxdwqc2hrCSQwDZkbA0dZcffBqEiIGec8Xxl8gSXXKGkiGKgM\ns0lSStHExWhqm8HyCmOhFCGlhDvSYE66hSfaQp9rM6Gt0q2oKB2Jut9B+6QD879XuHVwjtRKFmlt\nndmpeWRnl1HWGWUdh9pB8oGkATEgCQOn8wQpcZEH0AZ76K42E8113JOt/ix9G7yRGoPnttCH2/i0\nKhPOBX65/CeElQJXg4eJS2lMZBalRV43Psn3rGeQNZOolCVGhnlmcJktpN11n8+o4aTNyzzNyNI2\nz9/6DtFHc3THZeaMW0wvLmOpoIx3iJTLlOUIhOFF6bndgqwGq9I4b7ofJT6WpX4ly4A7h2+qQIIN\nYo40Nc3DuLrCCeUKBcvHujqEUVWpfStIq+WmMhEhdnQbZ6IJnzSI+tME/GWc3hY5YqSLCdRgi6Ic\nIkqWw9wkdXOYVG6E1MMJzK/I8Hs/5S/gp5zb99d2mepnTKyESvedHs3bFqIOyP62YHYvUniX9pHs\nwTjlR3wm3tu9UTsIChMer92Dt/9fUDl2yaA9Kcag79mKWiZ2E7RHk3s72nTYA3D7ePbgpL0IFrtj\niGNU+g89i/4DTuwr0vU9hxVc/5WO8vsSXLf3df9o7ceCtiRJfuATlmX9KoBlWQZQliTpC8Dju7v9\nW+B1fsTENi0FLzUmWMGUZW4xR5EgWX0AR6iJ4jAYNFOc6F3lte6nqOEl6MnTNd20dSctj4qz0UWp\nQL3ro5rxU/RFUOM9ZhsLjBRTnDceors7jVQM3N0WvXYH2XCTVyJsm0luM0eWCDEyBCkRd2QYjqwi\nO5t46asqgpRw0sJARTJNfJ0asXoeuW3RsjQMS6UQClH2BGk6HfiNKuFeEavhwxHswcMg6yA1Qapb\nHMvdICltEwgWCbXK+Ms1pLwFSbBGgCOgJPs/jyxRbvjn8DvLRDN5eg6Fit+LM9XCCsCAkuNAYgG5\na3K2eoFHOz9E1k3yBHDSoo3OGh1uWEeoWj4e4w203Z9IgjQNxcVd5wShcImOu/+nzxDjQHONo/Xb\nMAcdRWbo3S41009twEMdHdm0SHTTPFK6wIZnkLrDTZw0LZzMazPcDM2x4XgHTfMzMJAmQo4EO1Tx\nc4ZLnFEvscwkd8wDlOpBjJaK3DLRux2SZoqyFmQ5cBA5ZqL4u6iONoWlUSTLYs5/hbrsYa01TiPr\npbHpw6xpqD2TgRMp1v6SE/9nNbfvv/VYGxlDnjzKzMImFtkPAoaCOrCrPOw6ZNjjiiXbfvbjhNmT\nc/bzx/YO5iJoZ1eU2GkXsY/wuIXt30ds25/6blePCO9ZKFwE2Auwtt+H/SXuw57eLvZt27YLmaKA\n51xogPOfeJjiVxu2q/zo7SfxtCeAnCRJfwAcBy4B/w0QtywrDWBZ1o4kSbEfNcAV31Eew7Xbm1Fn\nnRFucZg1bRSX1s8MPNC7y9/r/HOsafih8igo0HE7KLcDbFcHiR3bRg93WfmjWZrrPjI7g8w/e4ih\nkTS63yDvDmMBUbJodJE9Ju2QzO3YQd7QH+U165NUZD8xMoyzymFuklWj/CPv7/AJ3mSQFHkilAhi\nIREnTS3pJhMMMZTN4iga1NMe3rbOUfQGwYKCFOYQ8zzu+gHh7TJ6wUCqWZxtXWapboIfzqxfoVZ2\nkj/lJ1Io419oIr1lwaP0ddlRKHmCFAgTIc8OCd6QHuNRx7vkvSFujk6TnNmhJnvxSHWeDr7IwfQy\nTy29QXo6zHYoTpIUbhqsMs4Kk7SUMKOs83n+jO/wWW5ymEc4z5pziLz+HGcGLoEsfZC4lExsf6Dt\n0n5oYr5ucf2355ifniYnD/Cp6MvMFu7yu3d/j3cmT3EncoD87sokQ4z3OE2ODnnOMswmEiYddA6y\nyDirOOgwzyzXesdZd4yi/WKLMXmLWWWeaWWBxeVZ3rnxGJnBYbLxBFKkgzmvMyvP85mZF5lnhtcK\nT7L45mGaipvgSIED6iLT3OHtn27+/9Rz+6OwV9Kfxq1M8kvVbzBLFh974GbnguFe8BOgp+9+Zq89\nItK/hdlB215C1U5xfNh57AoOoYUWlIrQjrPvWEHT2GWD+ykM2TaOUMbYAVw8FIQXbff0BTgL+kME\nN8U5OuzFBsQ9m8Dtyix/+v7/QaH8z/g4mWRZ/98uvyRJp4ELwDnLsi5JkvRP6Pe6/HuWZYVt++Ut\ny/oLBY4lSbIGz8SJjLgoWGE8h0YYODJAZ3cxJJkWW/VR/FQ44rrOonyAtBWn2XWhqR16XY1SMUzE\nn2VAzhBN5Vk1JjBcCj+X+DO8Vp1SL8Ql/TRdRSNAmTFWSRgZ1s9vMfmJGE3ZRRMXBcJU8dE0nRir\nOpVWgFQ4yUOBtxh2rVMhgJcqEaNAspVBdhh0VJVKO0it7KPbVgkkili6RBM3OSL4qDLa2yCey+Ou\ntD9Yf52/Cw8/AnktyLprmNv+WY52bjBS3oQd2AgOkwklaOk6NcWNpFiMsNHPHDU1Hui+R14Oc0s7\nRIH+19xfASgk2hkONebxNmvkHBGuRo7RlTRKBFg4X8Dz8DG0poEvW0cPNnAG+n02JxprRLoF1j1D\n1FUPYBGiSKhTwtNtUDJDDNwpMH59ja1PJciPhKjjZpBtBvIF/CtNLk0cZzEyRYEIRxs38ZlVbrjn\nmH+7iPeRo0TIo9DDQKWGF6kpQVui4ApSrIaolQLIrh4ub52Qt8CItE6t6edW8TDdbR1LkmHIQmr3\nSOgpziQucrc+zXp1nEbVi7V8G2ntJk65idbrUvnha1iW9ZcqQvKzmNswa9sS3X39FVskhO7Y5D9v\n3CZSWyfT21NcmOzVIbEDqvBG7Wnf+8EN7qVC9jc0kIBr9J9uYvz9gU6LPamcqDwoAFmMYT/OXsNE\n0Brivf0hIe+e+4Ttnuyc9Yd52IL3ttcdEeoZcXzHdh47pZJUIO8d46vJ52lsXIX6/cgJyO6+hM1/\n6Nz+STztTWDDsqxLu+//lP5SMS1JUtyyrLQkSQn6+Xofap/+b2d44hdivNZ8ipwSweFqE2cHJ22a\nhpvM0ufJa262J29iEECqRainY4RiBZxSD89WCEeryJT6Pr+e+Ndcag2xYyX4W3EHOS3B+8YZHJVP\n4tE7THvu8Gky+AnzXVVh7pcOEqbAYC/FG8vHWFXGaY87yLw+jLMcwXXAyyPDG0yFWqwyTpIU080m\nZ9JlOn6ZHV+UeWuCbWsQqQNP5F6l6A1yJ3IArWtgygFMaYSJ9Cb+YhW1ajCyuUVHbfGp/yzIO5FT\nLOtPcLv9BR5z/AvOaK9hIeFtH8Iy51jQD3CkNs+DzXc5rayx7h5h0XkAv/EgyKN41ZMscAo3Dcas\n28R6WYYlLxPAmWvXySpO5KPTLEoHqTOEk/dI/NKjSEWJynyYc2PfZ2pwkTvMcLagMth087Xol2g5\n4vip8BgvErcU2tYgl6WTzF6b5/m3N7j2XITimB+NLk7CKKkw5jWd1LGHKCbn6BHnqUKWY0aa65Ea\n/0F2kvilQcbo0sDNNoPcYo58KUar6sEK9ghmTcIbMlW/n7ZHo+zqMDfwFglnDa+RIP3GELl8nGI0\nQnJyhYn4XWK6l8W1T9Ioz6GGOwTbJfzVKo5Sh25ZpfLDQz/xT+KvYm7DL/w05//LWV5DU8s8fnaE\nZK3O9Wv5e6RxAfYKHwkz2WvrJUBLAKidWhFAaq/DYS/wZAHPsJe4a6c9hPsnzmEv3mRnhIXkT+wn\n5HV2kG6xtzIQDwEZ+DT3BjMFv25Xt9gBv8O9dcLt12vQ97DFdyMCnw3goHSeJQAAIABJREFUxJEI\nKfcIL7w3QKMTBeY+9E/xV2v/04du/bGgvTtxNyRJmrYsa4F+kcybu69fBf4x8CvAN3/UGDskMC2J\nf9j637nsOMZ3XM8wwwJp4lywzlEpBNAcbRR6tHDSqHoxFtx0nHWcyRJDk6tk/0WSxp0QJ794kyfk\n87R1B0bYZEmbZL05Ru5WgpHYGtPTC0TI46GOixZr9CsFqm2DP//jL+DzVvjt3/49Bo/naJourgdm\nmFD76e03OUyREBXLj2nIuFstRuUtRowMPVOBLDi/2+Lrhx/gpU89w39X/KdsO5J8LfRFenEVJdbD\n363wm70/pOrd5MLgKb4vP8Xb9UfZ3J5kLTHBSmAVgFPFq5xsX+frg8/z8Oo7PL50Hoe/w9bUCKsj\n47zQfB5ZM0mqKXTa/QePleJvNb+JW66z7BwB3WJMXuMX+Y98i8/Rwsn6rqQxGdjhC6deYFa5jYzJ\nNoOcDzxEze8lqwz07xM/PRSGzC2CvRIFNURgpExX13gvcooWDk7yPhuMcjN2mDcee5yYI72b4bpM\nLhAkRZQz8nvcwsHD5ImzwwUe6uvSSXHAv4TL22RHThByFYgNZrgmH+PO8mF2Lg7hPNfmZOIyE+oK\nlx85xYWlh/nhG09ydvBdxvXlfps5w4Uqd/BHc5xVLnDCukLUzFIyg/yj/3+/gp/53P5orEvX1ePN\n336Ig8s66m+/es+nFT4oigh8eI0REbhscW/AUnTDEV6p4KztWYuGbX/H7jFCHSICjkKx0mCPdxaA\nae+eY9rGEmPv13wLALZTQC3u9cL3K0gE8NspD3uTCEGp1Hf3ddFfYrXpL5Yv/soJVsZO0PktA/J2\nseNHbz+peuS/Bv69JEkasAz8XfrfzdckSfo1YA34yo86eDU3yTtyjIbHQ1buLx8VekhYGLJCaCyD\nrnTQ6KssIr4CuZk4JdWH0VQZcGcpeyMsD0zwz4b/S55wvsq4usymNoiJzLi+yqfGvofs6eHodUk2\nskhKjx46EhZrjLGkHcD9VJVxx1J/+e6TkOkQ13aIL2WpdgO4DzaZWl5lurJEa1RFzihomwbGlEXF\nHWQnnmDp0SkuRM+yJQ/xXe/TGIqCIvUYU9cwUCkqIZpTDirXvcyrMxQJYWqghZqkHHHyZoSHjAsM\n1lOU20EcVgeXs4UeadFJKhA0CUolTjovU5YD6LR5iAsoGNQlL2/rZ0GCsuwjn4jjkDpU8TBdWMas\n67yWGyVUM3F7G2zrSUoECFHkAS6SUpKsMUaAEhX86LQIU2BZmmRDGcGSJBzNDYyCyu3YHItMcJtZ\nLCSySoxtV5JZbnOYm33grq4xXN8m3CsSX1AYfkNj8cwEhltjjDVaOFnaPMh85giumSqGT6Gq+qjh\npeeV6YZ0rm2eot11Uh4NcMC5gBFxcH7qCW7dOc5OYZD2GYWa20Mvo9D4aoC10xOYh2UcVodxafUv\nP/N/RnP7ozKjrfDDPz5Fr9TiSV79ABztQCgyJRX6pWzsBZyEltveU9Huhdu5cNEaTFAm9kp8Xfog\nZ6cWxHiqbZu976Ndl22X3InPBLjbuXixKrCDs72glV0BI4BaSPwc9B8eIphpb/Ygvi8hdVTo57P9\n4DuHeMd/knZj5cf/Me6z/USgbVnWVeCBD/noUz/J8eVGgAvNcyy2DhLQywT1ImX8VPEiyybOQAtV\n6mJZEm6rgero0Y446RoKqtHFYXWITOYohUN8bfhLFGUfR7s3WO+MMMQmY+o6Tw98j02l383G0e3S\nxEmFAGEManhZ0qaYfWyeKRYwULnpmMVAxUMNqjJK28SyJJLlNGO5DaoJF9a6TC+nkp0KUu4ESLej\nvHXyLBuOIZy9Fql2Ar9WZsy1xjCblAhSlEPsJAcoBto48aHTJu7YwQgqaEoby5IYNjexZIkdJUbK\nSJL3hSlpfkpDHizVYspcYqiXYpskFcPHs5nv0dSdXI6cYMMxSAcdh9VmOxinh0KeCBPtlxhubCO3\nRpCa0HbopLQEPrOOwzLwKjXCUr/lWoQ8RUIYqDRxsSRPcokHOMY1zK4MdQl6UCZIAw8mMnU8tNGJ\nk2aWeUIUGW2lCNTq1Ew3zmyd8J0yjaMemi4XDjqMs8p2bYTt3BCzU9dp4GbDHKXVcKGrHaZGFmnn\ndBZr0xQNH3PyTUZ86zhmW6QuJslth1HKHeotD3LNxLFi0JjysM0gpiWjtY0fP/n+iuf2R2W9jsz8\nfwoxGovieSBCY7FKr9T5AKjgXs2xmz2gEmngdomgvX0Z7PHQAhztYC4AVQQK27Zt9o4vAozt9Ufs\nCSx2T96evfhhCpT9ShI7jSPGE+cQVIn9ngRFYs/AFEFSbJ87Qhqhgz62r8e4kwnBT6VP+qux+5IR\nmfSnuLl+HGXV4PTgRQ4cX2SRaTLEMHoq6bVBFLWHctBgtTdOpRCkthzi8ORVgsE8eSnC9JnbOMwO\n77tO8tLaZ/hO5osYfo3J2B0e9bzBb27/IS2fm8vRE6wERsgSZQkXo8gMsYWMyTirxEnjpMWf8xnS\nxHmE87gOtTAsjS11kOpBD5KvR+BKA/mKRann56pxnOH5FDPzy1x8vshEfJl4M8uz776CO1Jn82yM\nS5z54J4u8BAZ3uQJ7uKhTlJK8aD2DhHyjLBO3eFmdWiCN7uP8WLzWbzeKtFIig1thAljhYfrF1DS\nMnW/i4bLQfw7BbqDCvHPptlkmDY6TloMdbeo4eOK4xh3oxPkwgPMxa+Rlx5nsTLLJ0Kv83z724R7\nRf7A83foSiphCn1lDB7WGKeCnxpe6nhIE6fkD+IcafFzrm9xgvdo4OZ1PskdZjBQ8VMhRAENA9lj\nUnZ4ueaeoxK9TXCwxOPKD/jX1q9xSTrDPzD/MZ1Jndaog+OuK6wyzk43SfruEGdcF/nyxJ+wOTTM\nld5xLjQfZME5jeSCcHKHoae3MEoaNxdP0M06CGpFDv/6FUYi60TJ4JOrvJt5+H5M34+pGcBVWk9W\nKfzOOdp//yK91/r10QUHDHsAKsDRDmoKew0N9lfjE/SBfSz7mdvsgaIdROxKEQGQdg9fcNDYrkU8\nWOzet10Dbu90I3TaTts2eyp7nT1QF519xDULkqPG3grBnvZvAd1TYUr/9DSd/7kMX73GxyWhxm73\np0eke4ftYI58OMq6ZwQnJynvpjNbsowWadNuO9naGUf1t0CRaKsugmoJ306NW28dRzvRwznWoliM\nojhM3MkaDmcbywVL6iTfCT5LSQ/gkepYikUbjTY6mwwTI8MDXMRFE5DYYAQLieHuNucaF+m4NOoO\nN+d4i+H0FkoKJL+JNAeSYqG6DDojGg1dZ8Cdx0RG7RmEiiXKuo8bHGWBaRr09curTLBCFpOThCng\nlepYSDhp0UHnonSWt9ce4e30o+w4R6gN+7F8Egl2MGSVNX2U4XAKf6lM6K6Fo2RguiV6WwovRQ5j\nOiXOcJENZQRH2+DB6vtc8D1AWfeDVmDAnaFhuclKA7ylPURAqWBICg3c1PGQJ0KULKd4jzvMMsg2\nT/MyJjJ+d5li3Iumd3Y7zvRbq7ULLlZWp2mMe2mHnfToktEjdB0O6g4XvaBMZ9TBjpYgRZJVa5yX\npE/T0N1IuskV8wQbqXEKOzFCnjxW2OSGY44iITKlOLXtEKXhMEhQSwVIKRKabBBK5vAFqzjVFrlQ\nGJ+jTETK4aWG5m//2Ln319tarMxH+dYfDPGZ9VWCpNng3qJPApAExSCCgHa9tt3jtVMXgn+2c8mC\n37ZL8mCP1rA3ArYXzrXLEQXvLYKP4jw/ij6xJ82Ia9ivRhHXYy/8ZOfl7WnvYl+R2SmUJcNAbi3K\nC//mKZbnBWHy8bP7AtohR56J6CI+uYqid8lZA2TNKJYFbquJ4uvSq3ko3o4RO7SFy9siHMnh1Fto\nWQP31RY7kUHaQQelWoTB8AZDgVViZHZBKMxLkScZJMUB7gLs1h7p0aBf3yJECZUuLZxkiTLMJpO9\nNR5uvMMl9QRNTecIN4gWc1CR6BxV6U5o1FQPssukO6zQTDo+oHZqspea182Sa5K3eBgZkwBlBsiR\not/QtswDPMx5QpTooeCkhYXEAtPczB1ldWMK4jKq0cNj1YmQI2PFyZhxwq0i7nQT11oXfKDIFo41\nky33MDhNepJCSknio85UfR3NZWDoKm10Bt15QhQAeFt+EAmLOW4hYZHpxlipTvK0/jJnPJdYY5wR\nNniy9wrVWgBJsSiE/JTx08aBiybjrJJuJpE3gZiE5AWlbtF0OGk4XHTRqPm8LA0mueI4wg4JCu0w\nL2SfJ+CoInt7rKsjZDNJmos+Io/cohHSeY8zGKhkqwmMVRdbvlEsS6Z6N0zFOUAknmZu5gq62aFi\n+FkwD+A3KyRJ0cKJ5P94BYg+Ctu4EiR/bYSHxmYIjeTpbqTuAcD9mZBwbz0QAZA9+t4r3JtoI7x0\nO+8sQN+emm7nsT+sY40AUTvlYa+2JwDXniVpV4TYZXxijP33JVQlQuZn2f4v1C724KXw/j8IYI4m\nKRizfO+fzNA21/kbDdoA08o8nw1/m6iUo2up/Mvmb7HQmaZggLHjpHfZAa9D4fkYQ6fWeXzo+xS1\nIMp4h7/7X/zfvLj5OS4tPIB2sEHHqdClH+zKE8EkQYgiU9xlltsUCOOnwmlWGMLNAtN8jS/zOD8g\nThoPdaZZYFjdpOu3OKjM4zaGuKyexD1p4BlskomG2FHi7EgJttUEx9O3GC6n2RgdoedSqLm9LD02\nxrx6kNT/y957B8mR31een7SV5X2194128MAAGGA8OaTIoYYURWlFkUeJkla6O610e9o9mY0zsRd7\nd3FShEJrTifpeCFpSVEixRW5HC6HnKEbP5iBRwNo711577Iqzf1RqOkCODxyKS44GvIbUQF0d1Vm\ndcavX37r/d57X3r4Zf4cjTpXOcYYK5RZo5tL3M9r9LJLngATLL4xg/Hxw88wPLnKC/JDRLU4QbJ4\nrDKBcgVxYw3t83XkoAnHaYUgFMG5V+OnRz9PBScuu8Yp+wIJRxd/0/0hJNnASxEBmwYqMRK8i6/z\nNE8wxzQiFmOsEC1muPH8CVIj3YjHbUZYw0ZgTj/IsUs3UP0NEidbE+4bqDhokCeAFG1y+uGXmNFm\nGc+s4LxiIPTBXm+MpdAE1x0HyfofpCy6KePBmaqz/okJjG4F17kqI+MLCJLEih1kvTLMUM1m0rOA\ngYxedWFuSzwfeie2KmBXBXBDTEvyHuGrfC37XhYaB1G6q/jllmM1RZRk/S3lefkhVRrdWeHTv/0z\nHCoOc+j3/pAa+zK9zq6y3VG26Yi7AbLKfqfcCfyd4NvukNvHbG90tmmPZsdr73ZdtoH67ujTzuq0\nuXcafNp1d4JfJxB3Di2+2/3YaeRp31Rq7KtYGsBTv/ExLrtP0vwf5qFWu/tCv2XqnoD2Nv302yo3\nGodwSVVUh06PvEcl42Vtcwx/qEBwIk9AzLPZP0hFcrFeHaWouZlRbvJAz0vcsA8zr08Q9iSRZBP5\ndrpdHY08QURsZuPHWE1PIowYTLrnqVu7XC8dY1GcpOp2sEcPAjZNFIJkqYouEo4YoVyBvlqCurhE\nyhUlHo0hOAzqogMTES9lTKdACTdBKQvYbEl9rAcGKeHBSY09eoiQZoAt3FTQ2eA+mgyzTriWZSS/\nhdNfoe5S6SLBjqePIh7clNmjh+vGUR6snidlh0hrEQ7btxB9VaqjDjKuCHZFQAvUGCztoMsypbCb\nZcZJiF1IksGYuYJliMzZMiG2sYFdeulnGwc6BfyU8NJ0qIwOL+MNF8gQRsRCo44qN7B6BLZcvVzm\nGHkC6DiI000DFU2tc0y9QsDOYzpFGv0SBCGrBbgmHCEr3sIr+0gSQ8QkpiTZDY1QrvnQr2toCwNY\nYQHvZI6q4SJTirGp1GnUNLJCGEab5NUAHkeZ8ck5EmoXhkskJwTJG0HKyz60zwisnxhHP+Em6E9j\nyXf/yf8oVhPTMFl7RWcsZvDAh2D1NShs3wm6nXRDZxxpJ8fdIg/vVKC0w6Jgv3Ntg3anSaeza26H\nU90djdoJ/J3mnc7uGe5UjnTSL+3qzEXp/D3gzo6+vUmp8+03iM5PE6EB6D8LzyQMNuJ1LKOt3n5r\n1j0B7S0GcJphXs/fj6kJ9Dh2OSjO0VVJsbYziXc4T//UKsP3b9BswFZ1iBulI/iELKJgodoNtFgV\nr5CnW45jCDIO6phI6DjQcdBEZjk7QXKtm2jPHpZboMYS89UHKCg+RtxLGMgU8VK2vRjIlAQfI/Iq\nWs0kmC0yxTJP97+LJecIEywCAiIWPewi+RpkfV7U20bZrB1m2T5AEwVNrPMaZxhjmfvt1xhprpM0\nUhyjhIGMs64zvrNJ1vLSkIL41QIlwUOCGCoNEnQxZ89wrH6LVecIN6NT+KZKeAaLFAecZAmjh1WU\nHpMDS2sIBZtixMtl4URruALXmTIXkGnyImECbLHBEFc4zgGWGGeJVznHRm0YbHj46PN0S3vkCKLj\nwEWVmJLAGIdNoZ9LnLw9Fs3FHj3ESDFgbDFRX8KjlakEXNQCLdfjHlFWGcVg8fbNytHiwl1Vbh5t\nwhI05xxsro3R9RPbDD26wtbGGMVCgHndjb7jxpJFhMkGdknC4yoyPjRPvSRTsxVWGKMo+TB3ZSr/\nj5+ljwZIjXRz1HMBSfgxPQKAblH5q03sUwV6PzZKaS2BvV35tg2/NkjdrcbodCN22rg7u9hO4O+k\nNOy7vtcJ3lrHzztVJe3ut9MV2Sk/bHPNb+ZybENpWwnS+Xo6jtH+XlsVAm8+WMEhgKfLg+/RLoy/\nyFG9sM5bGbDhHoG2AJQMH+aeg7A/xZB/k+t7J0nYXVgHbZJiDKsm0HA7CCpZNG+dhLObg9INVKvB\nP6/9IRvVMWqCC3ekgia3htK6qTDCKl3EmWQRa1ii0OWn4VMp42ZJ6KcvuMFxIclRrnKQG1RxcYFT\nPGc/QpgsH+ZvSMXKJEIRFpjgmuMQBhIxkrzAw+zQz3/Ln9Br7VKyvHxLeoya4GTEXuOV+lkKkh/J\nYWEhUEcjaOWZ3FmFvMgsh1tpgeYOo/o2/q0KjbKD7bE+JuUFBGzOc5aD3OCkdIHVwAC6JBO0snzp\n8feQcwSQMHmSp0gS4+vS45wdPk9TULjJNEO3kwMBqooT5XYMbQ0nVdyoNHiVs9Rw0scOLEmUEn7C\nZ7JEfGmaKNRxIGHSZSbxZWsMKTuMh5aZ5TDZ26PBTESi2QyPzb8MU02Itf60s4SRMTnCdWZvB22F\nyRAhjSVIyKKxv+VfgtHaKuek53iu752s3DhA8UshrG+KMCxg/6oDCiJmUKI65EJQbBy2jk8ooqo1\n6DfhPRIcNNC8ZfrFbZbiU99xzf3olclLc/fzsX/9cf5p5l9yUHqOWfNOY0qnsqOtzqiyn+PhY1/f\n7eZOXXMb8Nq65041SlsVAvuqDqPjuJ1cdqdyRWRfLuhgn3e2aCk82qPT4E7TTfv9dH5yaPPh7ZuO\n1PF9F/tGm84bgghMKrC0epp/8Yf/ktXETSD+vV/yH1LdE9DO50LYuX68viIOX52S4CXozCA6DDSH\nny4pjm2JbBTG6HVtIatNVFmnjx2susRs/SiCKOBoNkgv9CAXmlSafuyQwnjPIj3+OEu5aeoOFTnY\noEtI0EWZLiHBoLpw2x1Zw0mdKm5yhNiojRCnl0uuk1zWTt6+GAYV3AQqBXo3k0QiWfLRIAoNXI06\njYaTuLubvNgajxWR0qhiA7lpcnTlBi5HhdRQlGXXKGl1HSceGqg0bQUM2Pb0seQZYV4YZ6SwwcPG\ny4gBm0Fpi4rg4RXpHPlCiEbNQSHqoanKRMwszlwTn1LG8ok8rzwM2DjQcVGlx4wTMdIsy+PEpS62\nhR160ZBpkqUVaUpFYGNrhJCeYyZ6i6Cco4yHLEE8VDCQWbeGmCktY2oyGX+YldQEomxyNHIFHwUa\nDoXXwqfoUbeIJZKEruZpTpfxDLRGquWsAEvGAZxSjYrgolTx07wiE9ZS+B7Ms9vVj3OsRkTMEHKm\n2Av2kO8OtSKb6gJ8UQIPVCMeNlOjlHwBnNE4vqEiEVeS/hEPrvfXGRlcIexOkbHCJM2ue7F8/8FU\ntmxxsWLxpUM/yX2CF//slxFtC4t9eVsb7Nr0wd3VKZGDfVDudB52Kjfax2hvTnZubHZ2tW1AbtMv\ncsfx2pSG1vF1+2bTPnen2uXu7ruThvlOSpH269udvgVYosxzM09wyXqYi9c7X/nWrnsC2oV8CLsY\nZmBwFV1T2bSGOBd5BVMUWWeYo1wjXe5iJTeFQ6nhoEaj4kB2GSjUCRhFPP4CVGBtfgprTSRTN9ga\nGyGg5Ohx7fKt5DuJu2P41SzvUL/OaekCk8wzgv8NLXKOIHkCVHEi1S2K+HnB9QgpWmPGHuIFPJTp\nqcTpms8wOrWOEZUwkdGbGqbuoOryUMWFVyxx0nEJHQd2VeIf3/okKX+Evxr5R8x2zRD3VRmnjoqO\nq1mBgs1a/yDXI4fYM7o5sXeTQ9Wb+OQiGXeQRXGCb5qPsZEdx87KHPDfpEuME6zlkdM2QXeRIe8G\nX22+B02o8bDyAk5quKwq/fouT4nv55p4hJz9LEO2QVjIkCTGMa7irOg8e+tJ7h95mbMTLyFpBgn6\nyNBKKazg5mUeINIsklcCxK0eCokQfY5tDoZv4qRG3hvk6Yl385D9Iu61Gl1fy+HzlPH3FVAEg6wZ\nJmFMcVicJSl0sVPrx7olMvDgOv1PbJJfClLzuMg1Q4gWOGJ1lMdqSAcErBdlGl9wwCQYUYXKgp/6\nqAfzoIo8YBB1ptCG6gwObfJ48+tohs6/Mv4nstq3ZTj9iFcCS0jymen3Meca5JdyF1HTWeya/sYA\ng/YmJOx3p506aNjvgAXu7IbbyX5tQO+cJNM+RpsiaXPbVsejff67JYntTcw2uNY7fq6/yfvuBONO\nY04nXw93UjWdTssG0HA5qEYifPLYL3CjMgjXv/w9XN+3Rt0T0I4G9zg58DxJR4RsOUyuFONWeIaA\nliNAviWX07Icj71OWg2TXYxS+kKQa08eZ2bmBv9N+I/RlBrrjPCpqX7c0xV6tW26nXE0X5U9RzcP\nD3+T68njzC3MsDI+wYhnHQc6h7iBjoMybiq4cVLlQ3yes77zXLeP8A3eyTjLjLKKnyITLDISWKP2\ngMyye5RZDjPKKlWXm4rmQZOqTJNgkA3KeBGw8ctFAqN5cloAF1VMJGQMhmlZ28M7WYTP2RzL3WD0\n8Dq66CC2nMZdrDKTW+LGxBTu/gpPyE+z2jtGOerjIe0FDibm6N1LkOkPshHoA8Hmo45PI9KaPSli\nsSSN85LrQXbEXiZZwGl/i7MMUMXNw7zIJgO87jxNfVTj1dSD7Ob6OHjqKie8F3mY56ng4VXOckU+\nTngwS5+4w09J/5FHR59DE3W62SVsZ3BUm/xE5lsEKnkUSSf1jwNUu50olsEH61/ilj2MoIwgCyYF\n/OjdKv2/tUYokMKqCXBZ4Jb/EHt2L6WqF8nXYKhrnT7vLrlgkOsHj4Eic9hzlf868n/xl/wSS+4D\nXJZOoNJghDWe5ClmNpfQixrvnfgq5wMFvvndl9+PVlk2PH+exMMOnv3L/5HDf/BJup95HdinRxzs\n0xGd0ro2IHfSB212680GDLRf0+z4fidF0dnltp/Tdle2M086TTzWm7yWjq/b6pROGWLbgt75CaGT\nimnrytvcdvu88UeOsvjPfp7Mn2Xgxb3v8eK+NereSP5kyFYjpLPd1AUXktokrndjCgL96g5r+gj1\nausjdWEriJmUifXGibpSeKUitgQiFrJkIngETK+I7lDJ54LUDY2QlOY+z0Wc9Rpqo0EmG2XDHCHS\ncBF7Jo3pk9g620sVF3Wc1AQnVcWFiEWIDF20QpBqaMgYqGqDXMxPmBTTzCFhUrydmREiy6C5yai5\nxlX5KC6xyjjLuMQKQTHLNHMU8eIwGoyWd8k5Aqj+OvoxCW+sgNNRJa/4sHpsmi4Jn1HCbxSJCUm6\nhTjTxiJ2VWLammNwextlxeRvBj7EltaHkyqj0io5gsxyGAGbgujnJfGBFr9tb6JTpIskWUKkiFLG\ni+gwOd33KkgCTr0CUrvzsMkRRMSiX9xGdjcINXN0VRax00LrM7VoU+pxIyg2A44NRMsi5wiw0D1O\nQfSjmAaj0gYhMUtEWuYWrdQ9t1il6AxQUT3YioDSXyOXjlB4fQy6IOLew68W0KsaSrDJ9NkbBIwS\nx5UrDPg3cS7XKG/7WEpOEx5IMhTeYJgNVE0na4ZRZZ0Bx1vPYvyWqESawpKH6zf7iJyYIiBncXxt\nDRrmG0DY+W+nbrkNjm8WudrmlDuH7HbKCjtpDLiTRuncDG0fq+2qvHuD0sk+RXL3zaL9viW+nUbp\n1IZ3dvidNybbIaE/PkLiyASzt8IUluKQqPxnXd4fdt0T0K6abl7beQAhB+5wAe9gjkwpglprEHLl\nmKvOkMtEYUeG56Ants2R37jEffJrKBi8wjmCZKnYPrBESk0flYYLY9VJtD/OtHcWl1HlvsDr9Hm2\n+YuFX2PdGIN6FMcnCwi9TcyDEl61Qkru4hX5LFlCKDQ5zlXclGmgUCXAHj23FSIwwxynuECCLgoE\nMJDxUiJs5PA2KuTFIKrQIGYlkSsGEdKctl/nBgdJNSuMJHawowLVcQeZf+bDXyqjWxrrvj58E0Ui\npSzqsoFHK9Nj7+K1yoQzRfzxMkLERkpYZHZDzOtTZPEzyQIiFmkiXLJPErDylPByUzzItDBHWMgw\nL/qwbYGa7eRF4SGc1JmU53kw/BK+cAFTkLjFDGU8zNtTxK0euknwgPhSa4BxI8VgJt4KL86CIUu8\n+NAYjX4Jd6SMLcKeGGWRCfboAQnSrjCmPE+YDEX8qDQI1bIs35pBH9DoObJF4PEU5tdECl+NIrzb\nQtV0RNNibu8QMSXJoxPPMsEiYbJs009zU4NFhYzZjfGYRD4UQMYRW4ilAAAgAElEQVQg0RthThhn\nl16C5O7F8v0HWbWrZbb/uwUSfzxE32mLyGwKO17GbJh3aKnbHXAnZdHWeLfBz8m+Drq9IdjkTvC4\nO3u7/dpO6V0bdNu0xd3nbStHXLTs6J1g3jmhBva75/aYsrYUsX0TaZ+v/X5tWoBt9nqp/tppUptD\nrP/myn/OJX3L1L1xRLqy+EbW0fp1Ki96yHyim+YplawuU1/1Un6nF/xS6+o+AFpPnS4xQZweNOqc\n5BIhMuQcIba6Btiy+7FMkbGZq4ScGaSKyV9f/0Umo3PMjM1ybuQFGrJCXOmi+tAeQwubnPhfbmI/\nIGAfVXhh4iEc6AyxwU/wDDdoufjcVNhkgGXGidPNfVxkiA1ucAg3FRSanOd+vq48TkjK4pJqDBhb\nuIw6iQMR8qqfMi4O2rfIlXbhPHTPpFkcHOMzoZ/n3Te+yYHaMv0PbiM5DFRBR5BtEEFtNOlOZ5h3\nTHJzchqPWqbXu0vsYJIPRL/ALr1vjEObYJH32M/wjsTzLAvjPNX9JGuMEiRPjSW8pQrdZgYtUOdU\n7TLHa9dRbR3BYZBz+EkrEYqCD6EB79t7hrAzhRW1mRemkGyBQeKtMdRekHwmhxu3sDYEfM0yr/We\nJOfzcYbXuMApdumliUIRLzWc3M95Vhll0TOB/740B5yLHOUKMiZrx0ZZ7J3CEy1TcbnY1AeoN5wI\nooWEeXtcnE2EDD919O84MnaFdXuYQsRHyMriblbZkgdIyRHGWEG+Q63743qzuvynAuVzPZz7tx8k\n/IlX8Hx58Q2jTWfGR2dqXqc0sG2BV9h3TLYDqNpuw7YLsa0KgX3KA749q6TtM+ycVtPZ5Vc7ztMZ\nUiWyr0hp53y3X9MpVYQ7N0TfeP67Rsn+yhle+nIXi6/8w9X43xPQluoG+pZCM2ehrzpp5h2EtTRN\nRSanhkGyW1c+BfQBHhsRi7XmCCIWR+TrNAUFSTLodW2R133UBY0RzwoOUSe1E2P+mRn0ow6Co2nO\nNl+lgcKLUhF1pIEzpaNebbJjdJNX/FRwU8FFA4UgLV49Q4gcAWq4MBFxUsdbq+Bs6tTcLqJmhqCZ\nJ+HoIiOGCYsZDnMdA5mEFGM+OElGCmHbAke5Rl3W+Fb4GDWniy2pl2XGOe28hGSahMoFcoKfouXA\n08hQNV2UTB9afgNvvYKoWdwcmabc7UK9bX0H0HGwxQAGMn4KuKUKA8Im7+Zr9OX2iJDmhu3Dsmp0\n1ZOcSl3msHWTIXuTsupCFJq3/1CbRAsZYoU0ZcuDLik0kJhjGlNSabiv0eyTkQwbh9REU+o0kdBR\nyQt+Nu0BknaMhNBFRXCzxjBJamzTj4sq2UaIvXIPekJDDNu4fRV62cMR1bGiAiYSltmFojc5HrhI\nWE2TJ0CENAAB8vgiOdyRIgp1DCtAxgpzXThMimgrN4ZtEvxYPfLdKjUrYONCOzpCzxGBfiPMxAuX\nadZ0mrSkfe2ut80Bw50Jfe3EPKnj52LH89rA2wbJTulemxb5TrMcO92Wd4dZdW5gdipT7p5G0/n+\nrbuOZQGmSyPx8FESRybZ2Rli4WWB9M27TfD/cOqegHYzqZF8ph/rqghh0N5TY/yhOcoeD/lzPhAs\nWJZgXQEdDKdCcdzHYn2CquXG8Mp0CQmcdhWvXcJh1mlYCiE7QwOVWs6J9SWBLaufW08c5Bc3P0PI\nlyYpOgiGc9jj0BAVrpw8wuWRI+QJkCKKixpbDOClRMjOMWsdwRREhoQNnuQ/cbxwA6VisuEY5HB9\njlg1zWfCZSqqC//tcNmS4uaqcphL3EeGMA5BJyDkWQ15Of+eX2WHflR0DnIT67CNWRFwpQzWxBBF\nPESrhRbIWb3ojQUOzc4RyBX4ow//BilXlBJeznOGAn5Umi1KAlDEJmtdAwyyyT/l39C3myJpxXjV\nHKHsKDNc3eRn1r+I4IFK2MmuP4ZXLGLaMg1B5VBigfGdNf7oxD8h6wvgFUps04/DoVNUNcoRD46i\nQThRJBEKUfFqrWQ/DLbsAT5lf4yjXKNbiBOnizglYBoTicX6JKubY/AVlb3jGXZ7+4iRIijkGGKD\nJQ4gShajzhU+NPR5qoKbL/ME3cQRsHBRZZVRXuc0O/RRNP2k7SifUT7MmLDKgL1JwM5zQzh0L5bv\nP/hKz8I3ft2i698+wZHfPsfgzQ3MnQQ127xDQlen1U13jhLr3CDs1Ga3JYSdtEm723Wwv9nYBt5O\ngG5z1u24rzdLJGw/2m7GNl3TPn87bKpTpNfJu79xXEGiFo1w5Xd+gZvXA2z/xuL3eRXfOnVPQFss\nWZx97/PMJk/QHJYIPpRGDJgIgoXDVaU558S6KMHrwGMgSwYeSkhlgbrpJusJYyNglmXWN8bJ+vzE\nQnv0sUMfuxwIrrDwwcO4j5ToV7eYHxlDkofZIUvZq9M8JLNybAi9p8VJ+8lzmtcJkmOWw8xwizO5\nC5xbuIgQtTFjAjWPgqHKBKwiR8TrdFsp/FaZD/OZFmdNBC8livjYZJAkUWxEguSQadJNnA/w//Jp\nPsotZrjJQSoLz6LutJZUQM0jdBukp/3YThvJ0eTa8DR2UKLc8DAduEk/W3QTR6WBjxJRUmwxQJQU\n93ERF1XyBDjP/RwbuE5PPsGxnVmcZTcboV7czir+5QpaqkH/wTiy2KSGk3H/Co6eKnpA5IPa56nb\nDkqCh+d4jC1hgE8LH6WJjOIy8fRU6NL2WtkoVOgiQZ+9AyaUJQ8NFPrZoU6ebuK4qFJzOskPBqi+\nx82Op4vXS6fxuMqocoMsIQRsDjHLpLXAi/HHqEpOprvniJKijsYNDlLCi5M6QfLEpBRNXeV85iGO\nMM8ACf6s8etk/IF7sXzfNpX/802uTQRIv/vf8FMXPsnJ2S+xSgvsHNxpkumU+am0wLI9rbztMGxv\nRLY7a7hTftd+fhu423wz7HfLMvtdud5xzE6ZX4PWTaL9aAN6+0bRqR9v89gSMAq8eugn+Q+nPkrq\nT/MUF3b/HlfvrVP3BLR97gIHD8yye7ofT0+Rg4PXsRBZT4zAmojUNBFcAqZPQYwZiCEDCxFrR0Zq\n2Pi78vikIhXBQ01wYYoysmiiCTrVhpuE2EPzmIJuaCRf6eGFww8heQy2xCtc97vxhfNkPX7Cuzmm\nSws0ehX62MWtV9GLTvAKqHaT040rFC0ve3SxygAFzYtLrhIR0xQVLztaP4rQZJANoqToZRe7IuIq\n6+gBDcshECb7RgSqidQywLDLAFs0BYVVZQTZYZBWA1RVB42IimZX6W3sQk2kGlQQ/U0mWSBCGoUm\nTuooGPgoYDKMiEWUFDmCpIiyQx/9vm16cnG6N5MEroWpdmkIHqijYmkGmlBDzluIeRhX1qBu46zV\nOKLdoN7rYHOgH406ZcFNCS8ZwqCARylhY1PCSwOVXnbRqBMR0kSFFFHSLaMRGfrZZpdeUCAaSBJ0\n5sgbfoq2jx36iJDGTQWVBoO33Zy3yBOx05wzXsQQZaqiix0iWEh0kWCQTZJijHVG2dIHWZVH0aQ6\nlzmBIDS/++L7cb1R+tUiyT2V5GNHGLIfJeau0HXgNRqpCrWdffoB9rvVNgB2AmMbgN8s+rTthOzc\nfIQ7jTJty3r7dZ3Jf52GnU7qRb993HrHsdqUTKfO3Ab8veAKe1hdOc0VHuFGZRiefw0S5b/X9Xur\n1D0B7b6xLfp90PXBbe7jIj/L53iNM+RWIjT+kwfnzxWwH29SCygop2owaJAXAjRuqPgrBY4ev0pY\nyVBy+6hNa2yYQ2BDSfDwTPU9PFN6H5ZXga8KbN0YJPB/JokEUiCk+ULoHJMsMNOYY+b8IrJ2i6He\nNS5wCqlk88vzf8V/OPABbgVnODk9y5JnlAXnGBIme84mDUR8lHjdfZKX3Q8gY3CCyzzEi/gpEEyV\nUFcsXj56iqQjAtjE6eEmGgt8CI06D/ESH+OTvDZ9hqen3ombKmkhgoTJCS4zbK/TVUrhvGxQHXZQ\n9mtYiJhIFPHivu1aFIAybpJE2WSQbfrJE8BDubUplwfWoOvzGQgA45A8FyQ/6SFo5XBtNNGuNhjb\n3YQVWo7dXmj8pIY+4KCElygpHuF5Xuc0NZxvdL/LjHONozzECzgEnQl5gfu4RIwka4zQRYIRnDzF\n+ynio1/Y5qe0L7DGCBc4TZowITLM3FbACFhkxRA/3/tJBo1NuvQUFxynmBOnqOJGo04/25zgMp/i\nY2wK/RgOmy963svznrNYGEjflgH34/qulUjD336ZL9qPsTt8hk/94i9QeGGVa1/Y1223KYl2d922\ng2vsg66Tfd1zgRY33p65WGV/cG/bwFNjXzXSpjpg36jT7qzvTujrpEk6w6o6M7Pbpp82v338FETP\n9vCxP/nfuHSjATefbunX3yZ1T0BbFRs0BYX7hfP0skvB9nN/8zzNYQdLP32AjBWlesuJcN3m8KFZ\n3FKB67UjjJxd4lTuIj9z9Yu4+issRA/wquMsA9IW0+Y8j1VfYufmKMIGBE8kabzTSbXbS3EpjL7n\nRpnvI5OLUA9tYEkCHIaa7GSHPhaZwO8psjnRjeLTScsD/Cvf76HJFapo3LQPMSKsMSm0Ot7B5A59\nxS/wSv9pvFqJSDODL1XFeUHHek1C6jPxRQpErTSH0gvslAQ8XCJNhAI+XuYB3EKFEWGdON1UcVHC\nQ41zaHqTIWMPqdvGWWqgvGJiFwWSQ2FS0y1eO0+Abfqpo+GihocSWwywRw8+ii1uf9BB5gE/r7x7\nHMm2OWHN4itVkJdMisN+5of72PH3k62GMUsioWqOd4jP4xysELVSTAoLLAkH+Es+zgkuM84SDlvn\ns/UPc8k4SY4g3Vqcw8p1PsAXuWCdZtGe4AHhZbZxs0MfH+CLJImBAH3sMGks8qj5AmklRMxM0mvG\neU05jS1KhIU42/SzLB2g4XCQF/2sFA9wcfd+ens26fLvsUsvc/VpRMPiqP8qtiKgCg1muEWAHH9+\nLxbw260sG5tbLKcEfvvTDyA/9CS+31f46J9+Gntjjy3rzk3BNm/d3gRsT0qHfXqiMwmwTXd0qjra\nHXHnhBrYB95O+SHcOY2m/V46o15hP5fEBgYBa6iPv/31/4qXdxvw2Twr6RvYtgn22wew4V6pRzDJ\nE2CSeRzoJOiihz38kRyOSBV1o4Gl1pBjTZxqlabuYDs3xHj/CqFImvqcE49Zwk+hxaeK0G0nkDHx\nUqJP3cYTy5M1YlQSfhpJF424CzntJ17rZpMBXGKNSiiIJQrs2DGWNibx2CXmhyZIiWFKeEhKITw4\nyJWCXFg5w16sl3x3gBFhjRlrkZCZR7GbaNRxGxVcWzpK1kIXBLTXsziSAgOxFG65Rsxy0csyMi2q\np4qL4cYW7noVtWKiYpBRwxQCHjYZQlVMpB4LOdtEypg06wpFw0MePwHyqHaDym1gzAkBthiggos6\nDkyCVHGRCQbZHROZPTODu15jMreEd7uCI99k14qxFe5jJTzaoj6AnOWjqzbFqLVKuJZnWpsjKcWY\nZ4oJFnEbNfqau6TMKIuNSYyqymp4jH5li2NcZY4ZdBxESaHSGswcJYWNQAkvNVxMmYuM1jeIV7pQ\n5ToOR51VRm6nC9ZIEyUpxsiJQepobFUHublxhJLuIdcdRItWKNseomKKGe0WSTFGDScR0m+oTX5c\n30/FyZbhqYujuKaGGZ1wcUReJTq2CP0ZHFcy6PnGG+O72puOna7JzmpTIZ0KlLvDotqW+U7lSNvI\nc/ewhc7Y2E4VSfs9NGnJDpWgSv1YiOxGhBRTzPpPsXGtSv3KGrDzA7pWb626Z0MQthjgPi5iIrHB\nELYiMGscJt7sxjNUJjSUwPmOKkvmKIVsCH3NS0Lt5aXYAzx35hHOiK8zKq7wIC+xxQApMczTrsep\nnZY4bb1MXXFiXHYQvzHQmhvkBlMW2RCHKePmpnWIzcw4ITnLmeCLrDwzgdOqc/lXT7AqjhAiwz/h\nj7nAKZ7dfg/lTwSZf7eP4nu92IrAamwMPeIgKiU5iI3YtGDdhl4QTxkEf3cRtQLdT9jEPxSm7lXw\nUKKPHdyUOchNeioZPDs1xpc2sQSBfNTH3Ilxntce5u8cH0Cz6wS6CjjtKnkrQLcUZ4p5TnCZiJ1G\ntx38vvi7XOEEmwxykJu3eeHW2C4Bm1XCyAzQ69gj2+VBrTUwqjIF0Y+NQIQ03cTRqGEJIl9zPcbp\nYoAnCs8wE5mjIalYiCwzTkAvcTZ/mWCwgCoY6Ck/m+5h5l3TjLDOA8LLOKlhCDJ97HAEiWf4iZY5\nBoUmCl1GhkPlZYb3dtHDIpVhlWNcJUOYDCEipPFTwEBpuSl1IAtbWyOUen2MPr5Aj7ZHjCSjrFJH\no4iPNBEquO/V8n1bV/Vzm8x9wcP/XPs4j/33Kzz58RcI/MqLFC+kSXJ74C0tSqQNvG16ojOwqd2J\nd+aBtBUhcKeRpv18veMYnZLCzo67Deadrs0KLdDWJnwY/+4MX/zEo3zr342h//MlTKPccYS3X31P\noC0Iwm8Bv0LrSswCv0SLxvosMASsA//Itu3Cm73eRYUB5knQhY2ALQjMcoj59Az6hoeRyQ0wYWtt\nhErRje2EwHiaOD0IJZuj3ssMiJsIts037HfSTZyQkGWJCbJKiHwpQPpiN2XRg+/9aSp4MFMqQgM8\nZplGTmMt0cOEZxG3t8iScIDaGQcOu0pR9LKaOEDRDCF0wVJlmsulM+h+J5JWx7QkPHaZSXGBbjGO\njIGLKrPaIdwna3STpltN0vNxE6kBwrBAMyLTFFszKkt4EG4vIEGysUIC5SMqDrOBqDWxZIHN+iCL\nxgRnXK8xJi8TIc0y44TJECPZstgLGlsM0MMuw/omx6o3WHCPYanwEf6GHfpuUyVXGWYDXVD5a+Ej\n9EbjhI0MtmzTV99j1NxkTptAkkzcQgUHdaSGgV52cDV4nEscJ2738Kj+ImE7w+f9T2KqIkeka7gG\n6oy4lullhyI+pl9fIlpJsXJuCIUmQXJ0s0f5drrhNHNk1CB/53+SqJIiowVZE4ao4UKjTtROMd1Y\nQBNqZNQQN5mmlnHCK2DpEvpBB8V3+Mhmo+SNCO5IlYwUJmVGyehh2Pz7GST+vuv6bVO6halXqbDN\nlW82yO8ewLtxjN53pBh73zwnPnUF41aG+UaLry7z7UMJ2puAndQI7G9iWrSAFlpKFdiXCrZNN525\n3Z353J2ZJgc0sA5GeOWjx3npqUn25qI0//cSazd1qtY2VKq8nQEbvgfQFgShF/hNYMq27YYgCJ8F\nfh6YAb5u2/YfCILwu8C/AH7vzY5hIdHPNllCGMg0LYW56kGS5W566gkiZopCMkjmpW5QoW98g9Pd\nL7FWPIDDaNBFEoUmGTvMheYpTkqXcNgNlgsT1DUHgmnTLDjo7dshfDDFXGGGkhbAdFeRZYNKzUs2\nGyMUewVnoMyOfRB7xqJhKqzWx9nMjVKx/SzEJrlVO8Se2E/scJze2CYj9grdxPHUKqhNA9WtU5c0\nyqqH0HgGpd5EqRkoTzSoo5ISfFTdCjUkNuxhPOUKwWYRp9hEqlrookp8OIpm1WlYDqqyC1ejSo+x\nRy97rUHAlAmTwYFOES8LTJDQu1muH8B0i3RbaXxGCdsWcFPmMLMk6CJHEAkDG4EUUc5zln7vNoNs\n4qOA3LBxGXUWmxO4qBCRUgCUJA9Lyhi3hGkWmSBDGK9VwpQkXtdOkK8G8At5RiMrTAtzeCiTJoJc\nMvAUKgSaeRxWHQmDOk4UmngoEyLLltLPsnKAQc8mJbxs04eJjJsKeQIErQJusUKc6O24AF/rI3LN\nRqqaOOw6ktFyjCp2ExOJiu0GE4Ta9w/aP4h1/fYqA0iwcxV2rgaBo0wG8tijTgbcdWqhEgthH0bj\nGl6lgmPeJG+1QLxNgdwN5HAnPVKjBeYe9oG8k23uHKjQDqnyAPKMSD4QYXczxKblQPJ4WR89zsXA\ncRYTPvib6+wLAt/+9b3SIxLgFgShHUWwQ2sxP3L75/8eeI7vsLiTtGb5tbIpfKSMKCtbU/iUIo+e\neYqsGiR7PQLPAw/CEfd1/sD4HZ72PsG8OIUhSFzjKFvmAIWanwVtkr1qLwsXD9E3vMGBiXncj97k\ntPwaB6Ql/iLwS6wfGiZ9OEHe66NQDGP6RTbkIYKk8VGkpHjJ6FGeST6J3nCgaw4+y8+xKE4QiqV5\n54Gv8KT0JaaY5zqHeSr101zMnuG+A69y3H2JI1xjiA2qDjevK8eIkiJJjFvCDMeEKxRocp3H+a31\nP+ah7MsoziZSzSLlDbEWHsGWBWwEynh4t/NZntC+TFLsYpt+cgSJkCZFhAvcxzrDbGeHyW7GODh5\nlUt+nb9Qf4GHxReYYp55plBp4KZCmigv8SBJYhhI2EARX8us4jhDQQpwrXwEv6PAqHuVEdao+53c\n8k6h36ZGCvj4ivYuQuRQbIP13QM0BZnwWBoD+bZuvEjpASeVpoMpe4nrlkGJMZ7lXfSyx2FmWWeY\nVUZZZ5gsIWIkOcAyKg02GOI5HuGC4xQIUMNJhjCpkRj8MnARvK4SM+It+iM79Ni79Eo75AiwKQ0y\n7F4nPJPh89/vyv8BrOu3b+nAFVa+arHzoouniu/GPj2F9AsneX/qw5wOzeH5rTLfbMDubXR2sm8t\nb284wr480MGd0a7tDrzNcdc6nm/S2uzsAk4A6m+qvHD/OV7+k0e4cKsXzi9Q/zWTenmF/W3SH536\nrqBt2/auIAh/CGzSurE+a9v21wVB6LJtO3H7OXFBEL7jlNVWEEyTyxxnlz7SQoSsEqLLkWDAuUkV\nDdsHHAACsCaP8OfSLzO7ewzbFHlg6HlKkhcrJ2G85mQnP0zSNKg4PMSbfQTyBR499Bm61Tg5gpyR\nXkO0TdYENz5Fx2VVqZc8FA0vFjY6KqW6l6ruRJccOMNVnK4ihigz6F5DdTaJuFKEzTQeq0QBP/3+\nTVRVJ6sESBOhhoscQRJCN7PSYYr4CJJj3F5iQN+lr2kywdfoi25ge0zyqoekGaOkegiJGV4VzpEj\nwLv4OivCKKuMvmGpD92epD5obHLSuMoNdYas9yZWv0zYmcQWoYiXITZx3/7QqVGn39pmypzDto5R\nFzVCZHBSo4aTJDHyYoC6rNHtjNOQVNYZwkJEk+rIkkE3cY7XrvJE5VlSvhBJNUrWDiGGG1SbXi7k\n7kd2G4w7lnBR45rzKDcch3A3a1wWF9E5xBAbdBNHockSB96wncsY5AlQwc05XiFAa1P35eIj7Nrd\niJpBr7pDTEmQCnRz9PQ1os4EG/IwbqmCnzzbDJAzArjsKvfJFzmyd/P7Bu0fxLp++1ZLVGdUoVyF\nMiKs5ZD/403OV0L8H87HUQyb9f4ZjMMaPY9u8aB0nqnEMs7X65jzkNuDZXsfxNtyvnZMazvoaQQI\n9oIyI1A6pbEQm+CicYatb/XDbI2vb91Cespm89IgpUvb2CkX6CIk2wz6j159L/RIAPgALY6vAHxO\nEISPcucnG97k6zfq1h99kz/7O4lNVjCnD6JMjWEWF8lLW1zyLLNl10nEC5BZxTVfZi/d4P++GaGW\nzBEmjdK/Rk3SSGRL2LMFilturKYMU5ArwkI9zcWja1gRm5wWoFe8TtoqUnvVwinXsBNu7NUY2ak0\nhWCTmqWhFzVsU0RTG7idFQS1QJwsCk0M2+AKBk1LJ2bL3JT20IRVNAwSHKdBjippXNjUjAIpc4E1\neQS/lCdpb7PRKLB8vsaI/BWetiqohhOxYZN2GBhymaCQ47ywRZYKKnvM42fd9nLAXiJGCpdVpdp0\nEzYzxKw0knWdgCQjqSYVxfXGxPMsAkLLhoRFFZdVI/FKBlG4QF5Ywscmu3hJCjF2yGAioVEnRoIU\nUfasXrJmA7FhoRoNBtwbmM1buGsLbHlG2FV7yBLCwzXqjQhblV4aWpx5pUpESlER3NRwYeGh8KrG\nqlhF5OuUabCIyA4WdbaQMNHJUkOjjobAJgFyNK15iqUyWWMIW7YJO28hAo7KZRT3NepqjdWLE1RI\nskoGEZPN2X9PaW6Xr4hZXil+/1TzD2Jdt+qzHf+P3n7ci9q6R+e5XdtgbMMNstxgCFCgqeKuK3QV\nNSqSl8VyELeu0zRt8rbAGiJNVCQUFKSOuNQW4Ko0GMAiYNqoukC5orFS9HLZ0EjqCjXDAFzwlWbr\nDbAFrN3b3xu4d9c6dfvx/1/fCz3yOLBq23YWQBCELwDngES7KxEEoRtIfqcD/PRv9XLkIzN8jp+l\nhpOwnSFrhhEYpyidIWcMU57vRdBCnH3sWYSIzfPxdyAFGhiBPCvex7BFAbMpMVAWSTzdR245Bo8B\n34Diyw2+UflZhJMG8qkqqvcqftlgSLyG96MPkfhWH9m5UeQH97CnLfRSAHNBI6DkGT8+R1jO4BRr\nGMjYCFRsN1vWABPCN+kRLuDCT0jIImJS5wgxkhyhiYTJcGqbgcQsXxga4qr3QRbt9zNtP0WvcpFj\nHxmhgJ+uvRSPXnwZ/VCcwoCHrBymW9BI4SbGGbpxolpFHtBXCNg55JqFuCKhSk1Up4V+M42tCTTG\nFM4PjvOC50Gu8hBhMii0rOn9bINtsCWsMPyRM5xlgY9YL3NBOMXz4n2UOM4EixzlGv2UeY77eLr5\nPgrpMMaiA9duhanHXqQ7GmXACmBJg0yJDYZZx0OZeWuKz5qnWCq+gyQmA8ELBMVWmFXtNo/d85H7\nKOCngB8DmRFSFPFSwcMQy28Mb9DoZ4gFxuwV8uYozdyD7MQHmR78WzzeArZ5jIgUQRPrCISo4KZO\nkyE2+KD9El5b5jPC72DqMjh/6nv5a/gvsq5b9XPf7/l/AHX4h3Teg4AAGRe1SyJ7Kz28wCO83jyD\nVLKwa2CgUMOPzRgCIwiEsG/nC9rkgVVElrhCATnXRJgFc02kpjgp2V4aBQUqEjDJnffNH9bv/MM4\n7//6pt/9XkB7E7hfEASNFtn1TuACrU3kjwO/D/wi8MXvdDVXM8IAACAASURBVIAE3RTxESBPP9uM\nC8sIcmsAbc4OIoomaleT5P0Ngj0Z3M4y95mvMeZdxOMskRHC9LILis2V4Any/giUK/DXazAbQKm6\niU3sUh9Wydt+blw+iuQ2KVR2KF4dItrMcPx9n2ete4jdYi/mkobsamI6ReK7A1QCXiLuJP3yNuvF\nMbYaA5Q8Ll6tPciWMYI7VMAnFxFsmxV7jHV9hLXGGAPuTapOD/WIxqJ6gCwh/HaBnmSKYi7LVMZi\nzTuA4LHYG4sSEnOECwVkl8VJrlHTXUhFg4ZfxvCJ5GU/zrqOalaYjx7Aq5QYULZwDDeoqc7/j733\nirE0Mc/0nj//J+dUOcfO3dNhelKTHM6MSIqiSEWv8joAxq4NQzCcLrS+WsC6MBaG7V2tJYurtbSS\nlhTjcIacYU/omQ7TOVTO6eQc/+iLGnEBC+sVrN3WWFMPUEDdVB3UqRdv1fnO970v2ViCj5SzlIly\nltsYH58XKJjMsIgguKwIPXShQ9P180SYQxN6nOU2cYpo9DAclav2SxTEBMPiJrs+F3dAJBisI/ks\nHrtzPLCP0xNVwlR/cn6+XRxha2GCWn+YQKKOJciHu/bUqBJmH4EcKSwkctk+ek2d4YEtKrkYhVyG\nmdkl2n4P2+4QjiDSbAW53niejcggk75FfjbxDcpaiI3mGMWDNK1GiICvQXCqTLUWp9kOUJUStDU/\neqnDox+cwpjR/m2S++vwN9b1pxsXei2cHnQq0PlJH85fInF4Q9kFckCDf5M+0uVwiv1xK6ThHL5D\nWf3Lr+3xb+Kkjvh/8teZad8UBOHPgbscDpHuAv8MCAB/KgjCbwJbwM//277HpjVCqjNGUK3TL+0x\nzBY+WrTwciD0YUoyRlylFfVgiSIescUZzw0u8wERKqwwyTBbNPCzxAxC14bt7mFNUNtFmRXpO7WD\nMa5C26Ww24cZlLF6Iaz1fjKxHMev3CVficGBgFYzUQY7WKrEzuooHqmG4LE4xV12uyM4HYWYXman\nNsxSZ55kYBef1EDCoeaGqPUiOG2Ri/qHtD0eFrUpPpLO4qHDrLvAcHmHWrXIzEERU5YoB0JUJoKE\nCk2ClTZ6t4Soivg7XTJrWcqjATbCAzwQT1AxDkhJBW4MnCOj7ONxmgQDTSpimDV9mCWmUDC5yHV2\nGaDd9KLnDQaTO+j+Dn3IxCjSEbw8FuaZ4wknuc80SxyQ4RHHuGq/hM9uMyhuE/A36Hl0HEvEq7Yo\n2THWrDGSQgETla7kwUSh3EzQW/NCREAQHRxEFAwilIlS5jY2hqvQdXXq9RBWScWb7iCUobvtwzvW\npixEWW+NEw7XyBsZlmtz+AMVpn2LXNF/yJvC56lWomQ3BhEbNkF/hQEPNHtByr04ebefg1AaNdel\n/Hoa2/j/vj3y70PXR/y/8Zfb1C0O/z4e8e+Lv9b2iOu6/4i/+r96mcOXmP9OKs0Yb6x/kedH3sby\nySwzRZkobTz00Ninj32rn0I7yap3HFOVGWSXBgEiVJjnMYvMcJ+T5EjSuy/CdRVGnoGgSmtU5sPu\nCww0txkI7BC8UgcJyrt7lKZaLIqzZItxan8RQ/GYDH1llboeoFEJQRd0sUtMKTPKJtFohfPOB+hy\nhx+Jr3HLuki9F0KWTQJyg4DYwJBVurIHVeiy0ptkpTWFGuqSVrPkSWL4tMNXdLvQjXuQVYep4hae\nTg+hBdIO/Pn4z7IhjfDf7v8uK7Fx3uEyjziGoptEtAq6dLhCtyJMENMPG2FypBhglxohbnKeChH2\nHg+x/k+nee0//TZTFxboskKAJlEqpMjioYOETZTyYX+lIJFQ82zUJ+l2/PxW7H9noXaM14tfYmRo\nkzOeO1wSr/Ni+xpRs0TJH+T3+E/w99f4r770j/kXjV9nszpCwZfgDeFV+tnlq3yDEbIE3Qd81/oi\nnT6VULqG5DFJTOVwhgWSgTzZh/207oXpvqIzklrnuOcBLdVDwU7wO+bv8DX1z/ms/Bb3vc/gnaxB\nyWb996fxf75GdCZPMZvhnOcj+sZ3+fZvfI3moOdvlD7yN9X1EUf8bfBULiJDahUj3OKs+BHFXowf\nW1eQdROP1MFDBxeBpJhnVN3AEuWfzEnfa71IxsnynP8dBrt7iI5A3RNAvmSiy4Pkg4MEI3V8sSY5\nMhRbcSSfQdMJ4Roina6fTGIPr9wgJFVQZ2xaHh/ZUAJjyYNZ9kAQRrQtRsRN2njRlQ6GqbLQOE5b\n85JMHuDXajgI1IwwRsNDp+zHbKqsm9MEvVVG9A0CYgMvbRxRZDU8woOISXX4WRLeLCPSJqLPxNJc\nHF1AUFzqvgBr6ihvzb7IQnyaBaYPz7Il6KGifHyeILoOgVYbW1IQPC57dj9Z0iiyiYtA3Qyy1xhg\nz+pHocsOXQbwk6CAjUyw0SJq1SkGw+SkFHkhQUwok9GuMc4GY+I6NT1MX2iHqhwmKpYYETbwKQ2q\nQoj7nGCCVRxNpJnwYlZVmq0gW95x2rKOqhjE9BJddHpCgiFxm2OeR8SFIppgUN8Kkd3q4/6Fk9Ri\nQdIT+xSUBLguSS1PrtzHXmuQ/V6GSuZtUt4Dfnr4G/jiNSreCDfPXMJaVxAKDrHTeSL+In6hgXS8\nh6t4noZ8jzjiE8XTaWPX8hixLMeEh7zbe4Hr3YuMyhtkhAM018AvtkjIBWbkRRaYpUoIA5WHndOs\nOi1Svn2eM26QMQpsSkNYryi4VxQq+2mCUoW4XaC8EKfW9dGpp2g3UtiChtxIMunPMuZdJeEWCF2p\nsiGMseaM0F4JYLY05As9+vVdEhTYpw8PbfJ2mrear6AHm6SDe2Q4YLczyFq1n+52EGdbhrrL2qlp\nzg1f50rkxwBU7TA5O8XDwCx3Yzpvzv06P8efkiTLgZZAdXpItoudlHAUl66s8b2zr5AljeXKzDlP\nsB2ZmhtEkh0k0UJ3ukTbNQxVo6PrPK4d48DKkJaz+MwWZkeFJLQ1LzlSHFChhY8BZw/ZtPE2u8im\nw4E/w7o0xh79JChwWf6Ay+I1cmKSeCDPdODR4TomccYFhW1PP9sM8Z77PJ913kLG4oZ4gXojSK+h\nk/X3I6tdVI9JTC/TZIyGkOGY/JgplgjQ5Cbn2V8eYO3aNI0ZL7FMiVggz1p3jEbTjx2Q2K6NU67E\ncU2JfCzFcGyDX/J9HRuRZd8UBz+Tpvy/pBCXHAZe2iDqK+GaLnqyiXQQ+Dt++3bEEX+Vp2LaRtPD\nxsYUHw2dZ0MYw3Jkik6cuhFE7llc8n5IRCmTJ0GWNDYi/ezzYuhtuq7Ou8ILHPj6cASZ72a/jBgx\nQXCxixLZewMUH6boLHtwG5tYvh3sV0NwUsNVwBBVlq0p3u88x7B3C1NRDqNBgy66t0MsdUBRi+Iw\ni8phKFNZjeJN1HCkw2qsCVZp5kJ0nwRwbknwAKS2TfhEkVRonz72kbDJtTO8X/ksTlzGYZuzfMQm\nI5SIkyZLQijgSCIb4ihL4jQtfKwxzjRLhJwa321/kVI9hcfs8VLmhzQ1PzvSAOFIjbvicb5tfJnd\neyNUt6M0mjHEPQerrYAGZSmKTosQNUaocbzziKnsBpuBQe5FjrMhDaPTZZAdopQZLu2SrpYwhjQU\nr4mDSIYDNHpsMQy4JCjwZb7Fd9tfpCX4OO27i2erg9btEDuTJanmmBKXkAWTOAVGeUCEKm285Ehz\nn5McDGbgLMh+m/JanNrtGB08nJ56i//owh+y3DfNk+Q8T9w5fJ4mAZqMsc6P+CwbjDHLAumvXKXP\n2CcT2EfA5UDKMB94zON/pfB3I9b+iCP++jwV0y72YpSLcd7te4GqHiLgNnEkkbbrRVJsVNHARmLP\n7efAytBr6xgVH1PxBVy/yzZDZI0+RAtUvUdXVOiKGp54i7bpp7segnUg48c9FsM/2UIaMLE2OlTE\nMKJrY8oKG70xjIZKqxNES3YRZJuurbFvZihbESTbptUOYiHjjTToSRoCLiGq6LYBokBwqowpavSy\nHoxVjUIwydL0FH5a5MoZ8o9TPJ4/hmreYsQVWOrMHjbN6B+xJoyzJQ5TJoqKQYYD9uhHwkbCpiJH\nyJoZpDrcD59kz80QpkpBTbDCJEtMY8Rl6Lo0nSA8aoMiwM9AttSHsaRimHeoOw51KciGd4gH3mPk\n1QTTxipt2UND9hGmiqNB0R+jJ6kYaNjIzLCIjUSOFA4CU6xwnId8KF+iQYB9+mj7PThNme4tH/7Z\nFkZS5c96P0fJvkfYtrlvnGBOfkJKyROhwuTAEqa2RbadolqP0SQMAqiiSUSo4PM0EW0Lw5LxiU18\ntDBQSVCkwxY1QkT6S0QpkSbLKhNsicN4xA5T44tHpn3Ep46nYtodw0Og1uCxNQ+4BKnTNryIqo3X\ne9hy3nT8rDsTFI041WqU1c15VL1HxF+kg4etTh9es8PF+HusWROUrBE8I3XcQbATCk5ZRHo5hvc3\nNQYT60iaRe5OjbIQwUubpJpntTBJ7SAGezLJE7sQssnnU+ihDrJmYXVlnJJKwG0xGNykIQU+zvIQ\ncRUBJWUSfz5Lp+qj9CRN84Mwq+o0xrREgiK5eh+sw0Emjc+KkyXNVmeEsFvngnqDO8IZHggnCAk1\nxoVVNKdH0YxTk0LYskTak8NQvBSdFHfN0wg4BNwGhq1RkSI0xAD+41WUYZPKVgJer+F4RJxLOoWP\nMpQrMSRjgF3bIaxX+TCTYI8+klaJS72bPGCebWmAsFvlIJSiF1HQ6dJDw4XDs3y8HLgZKm6UrqWT\nNAs8o93CkQUechxrREZuWJTeTIPvCYV4gm92v8Kg9bsEzDRX21dIe7JcUG4ywyJWSsYIaXx77Wv0\nRA/aZAcVAzt+mPaYJ0nD9uP2ICDWEUSXFSbpZ4+4UOQhx6mZYQxXR1N63BNO8YATh29Qf/4BV5+G\ngI844hPEUzHtL3e+xUv7d3jPuMC1x89z5/oz2OMSwckKkbEKESqUejHW6xNk/HuEkjXygRRBX4Uo\nZfrYJxhooLomqtTD3NJo14IwCcr5LqH+IvWVKH2jOxyP3+OSco0CCb7rtqh2BYpWnLodpPUwBO9I\n8CZUfzUBUy6UVfTzdSIjRaJaGdOjEqPEC/JVHnOMDUZZYpqskEIUHXy0ScSKJGfyrGVnsCMSPTTq\nBOkNKYReK/AL8T9h69E9qjzDZGCZOHl+IL3C3c4psm4aj6fDrjBIu+VjYe0kkVSR+cwDfp0/YCU2\nxfuB59nSB/EIHaa7y/zykz9jJTDB/lQfI8ImbZ+PlbEp+B8MOo6XcqCDE9KwHQmnpxKwikiKzW3O\nEKOMLJq87nuZqhAia6f5QetVxtR1zntuMskKIWqkybHBCCHqPOt+yExjlaHdXSJrZULnGgT76kQp\nc6rvAaVOku9s/yyqp0dYqjLg2yFnZHi38ln0cI8tdYT3uYxGjwIJ1pRx/MMVxq0qQeqc4h5dVeMb\nfIVT3Odl+Uf8tPc7eMU299xT/NB6mWfkW5wU7vM87/IHO/8xd7rnmJl4RE0NomKQJM/Q0SrZEZ9C\nnoppx+USl/y7LEsjDPq2MKMqS9U5uhs+WnYIKeMQVOok5RySZGOrIh69TdZMU81HKO6mMFMSomRj\nrkxTup/EzGt0xvwowwbedIeZ849RfT1atg9cAcNW6NkqY9I6ZTvKRmcU95ECCyL0XGJqAU+kTU/V\n8Pga6NJhLnTAWycqlgCQsBBxKBFD8ltkhB2CSo3j3UcMWPt8f/oL7HQHKL2XppGMIkYtksNZomKJ\nHcEh7yTJKAe4AnTRCYoN0m6WsFBBxaAnapheibhSYJolBtjF1iVyepLixwFL884j/P4Gw55NXhbf\nRMbGUFQm5BXCc3XqdpAFe5rCWIaSFaO0b7EujGK48mFJhNDAFGR+LLzIlLDMMFu8I73IrjjACJsc\n5yFpstQI0UUjSpnjPGRQOsDwaNwJn2JJnWKrPUq2NMCJ6CPG+jbwnO2iJdooYo9z4ke8iUXJjTCm\nrFCWotzjNJMs46fBgLhLwxeg2QzSavophyKU1TCr9iQj4hYD4i4hscY2Q7R7Pi42P2LMv8agu8t0\neY0Ba49lfZq2cHh5qdGjg4cs6ach3yOO+ETxVEy74IvTHS9QViP0Te4yN/iY1lU/qzvT7OWHaV4I\nEssUOBG8z0P3GDU7RFCus9idobkbwr2q4py1cRUB989UuC1C1sVKeDAvePC+ZPDsi++xKk9wp3aW\nsFym5MaoGUu8pt2jJMXYrQ9gbao4Fgifc5m6uEDq1B5VwoddjE6ILWuYSXkFGYsVpmgSwEMHA5VY\nJE9fZAcRh2f2b/Pq/o8wZyXevPcq975/Dvu0TPxUlqHEJnmS5ClRsSK4skBcKBKzy8ypT4iLRRQM\nVNtE17uEJouccm/zjHOLrJDGQWRU2OARxxhgl0lthcXZCaJuiS8632VRmEUSbMZYZ8rYoEKYH/ue\nY3F2hkV3hrv3W1wXXiNtjPK8+i4ht0bRiXPDvsC8+Jjz8k1+5P8cJgp1gvhpEqDB4fKlhxF3gwlW\naPu8PBmb4M2xz/OEeVZz02wtT3Bp7kMup9/np5/7C96yPseOMcCcssBtOUNXa5MQchSJk3NTaE6P\nc8It5oXHrDnj5EoZmtth1gbHkUMGmtYlryVZk8fJkWKVCY6bj/nvq/8jbVWBnktorcMz4zcx+6BJ\nAMNVaTgBtnvDbInDT0O+RxzxieKpmPaDxgneHjV4p/ZZbFtkOvyYL579Jo9zJ3l970u8/p0voXoN\nGqf8GCMifdFdLvEh654ximNxpJDLtjRMoZKEYwIY4JlqM/iVdbqjGnq8S9hfJi7kiat5XEWgl/di\n5nXynRAeX4tz8dssvnaCciUBcbDTEj7aZMgSp0hH8PBAOcGgsEOcIl30j5t2RL7DlwjQoI99Dsiw\nlhzljn6cV3I/Yj6+yO3fOMWT0Bz1YBCdLv3sURc2mZO/T0mMkS+l+SeLv01wokI8nSPDAQ+zp1np\nTNHs03jTfpVb1nlEj8PLyg85L93ERmKIbSZY5Q/4DTY6Y+itHi+H3kBTu3yPL/BjvUOFCIvCNLMs\nMM8TskKR+rJNsxuiddLHkjXFjjWE4xVZkGbpoX1czhBgiWlucp45njDNEg0CJI0S/q6J4O0womzx\nOd4iTgl/uIlzQuQZ6TbT7TUK3hgX79/imfYdihfCyHYaw/CRdw+LLgQD7hYu0PYFmAk/Zk58jK1q\n3LYvYvyJFzOgIzwjMza1SSRSYpkpWvio6CEepGdRtB4h6gTj3cO5PRIWMmvWOJs7Y9S/HcXp+5uV\nIBxxxP8feSqmvZKd5vvCIBUpgiDa7EsZkqk8CS3LuLxELp/GkmS8Sgszq9CuBSiFkrSUIKatY8sO\n9qICB9JhrwgtXLuONSqhjvfQvG326aNYSNItedgJjFCuJbBa66zdnCIQr2FmVGxJAh0E1WWmsMIF\n4Tq+ZIMEBWqEaAh+FMGi4QTYN/tISnkG5R3OcJeiHafoxlElA9fr0pE1Bjq7DGrbpP37OCGBdW0U\ncA8bZ4QcJ6RrrDPKA/E099WzDEvriJZFox3mwO5DkB3mhAX2hD7ut08jPIGwr4kv2SUWL9OxvVzv\nXibrz9AVNFTR5IA+Gt0Ad9tnUfxdWqKPg2Yfcb1EVC4jCxb96h5Bt06/sEdH0CmSoN4NUVdDlOQY\nTduPT2yRlPKUiFEmSoAG+/RhCRoJoYTsdBFtG0NSiVIm5paxXZkNYZSwUKWLxLC6i2Fq3DTOYwkm\naW0fR5DoWSqGqeIIAhUhwpY7jGC4dFba8O4qjpGhP1HimP4QRTTwdrqcq99lOTRBS/fxXfk10mSZ\nUldIJko4uoBOlwAN1oUx2pIHn7+J7LGpPA0BH3HEJ4inYtrbGyMUc1/m9MgNZJ9BmRjXuEwynOdK\n6A3eHXuRFj4y0gGrb8yzVpljbXIOgg5CF9wN4Nsc5q19Adiq0N1rsrE6Sn9sn4CnzjUuU15NUb8V\nY29q/DBBwrnOk2+eQEi4CK+6uA8EhJqDlLJ52f82Xxj/NqV4AC9tdhjkgXiCLYZYt8e42zqD5ZGJ\nymW+wjf5Y/uXuGq/xEviVdJClphapDsqEd9rML+2zI9nrqBoBl7aeGkTcBvMu4/x0qIT8bLyzDhe\nGpRbMR7mzjIUW+dU+COeF97jmnCZWiFC/ZtxfhD+ErfPXeDXLvwei7053i58nudG3+bz/jcY0Tf5\nDj/N3dI59neGiY5mQYFqKcZKfIqwXKZJldPTj5h3HzHDItPyIv3CAf+y9KuofpOQr0a1G2JKWeIz\n4tsfj3KStPHyYz7DkLJFQKky3NuiYCV5X3qOOEXMpsb+6jC/P/nrzIbP8Zz7PtnjabasIf6o8StE\nlf+V09Fb7DBIpTVMx/JwLPUIj9ymZEZ5WDtB460t+D/eh//5s5z6zG1+M/Z7fI8vkMoW+Qcr/5Q/\nm/0yP9Bf5uv8Ksd5SFfVmYs9wgZCbpVx1tmRBigNRxn5+1sE3TrrT0PARxzxCeKpmLaomYhxg+Xi\nLMFujUg8zwC7hKgh4nJMecjO2ggr1+ZodgMQAbyQie7i12qYSZXi612a2xpsjcH5KOGUzZmTb3M5\n8gERq8z/VvkHtG/64XUOi31DIIkW879wl/nYQybTy9wKn2ff6sPVYF0e4Fv+L7AtDvBq8UeE7Rqj\niU0MSaHoJnAtkYoTPSwhRsCQFUJilayQ5iHHMVHw0uYg2seiPseab5QsaXpoFIlz4IS50/4cHdFL\nQGrwReW73GhdZKMxhm1J5Jb6uKvKVOYjjOnr/L3k19n5lREe3j/F9qNRvp34Km6fQ2Zom4BeJ0eK\nbYZY6UyiKAbnR67h89aJihWS8TwPtOM08ZMkT5lj5LoZfrbwXRSPxbDnAMKw2Jvne5Uv0/b4KUlx\n7jhnuN88RVQpMajscm//HNvaCKRcppQVRBz62KdGCDFgcXHqXUqBCOutcbL7Q4SSJXzBBs/4b9GR\nD0gSRsKh6kRoWT4kLE5yn1i3wv6DERqpCfjPE5CKU7CSLDLNcR5ihDV+Z+a/oxYIYKIwyA4xivjc\nJoptMSJtkSfFH9q/hk9s8RnpbQbYY6y6xR8+DQEfccQniKfWxu5+CM64BH6QsbGQqTRjNGpBtGgb\nG4mKEUFPdglnmqhRA4/Tweu2CfftYgR8dLxR9IE6+rxNuL+LrLr027tMyKtkOCBvZaj1NLAgoNXw\nhvIMn15nPLDEtLvAgjqLT2gQ8ZV4whSbDIIA2wyRoEATH6VqgmY3SJ+yjyA6HJABXCq7MbplH9nJ\nDILPRcEkRomaJ8QDzwma+JCwcRDZYIw8mxSYoeEGGHR3OMl9JCwUySDhz0ELTBT2GGCKZaZ8SyRP\n5qkbQbacYZa706TdPUZDy4fZU+0hdhpDVLUwE/oqV/S32WAUFxGv3ELEIWpXyPQWka05TBTaH7eV\nW6LElL7EE/sYu/YAKXmfmFhCch127EF2zUFydj9b1VFqwRA+oUZJiuF1O5i2QlfUMTWZjLaDjUvJ\nTFBzQ9Tx4es26D84wOioqIbJpfINbEGmK3uolaOYXo20kOWz0lsszMyRS6RI+O/Qp+6QddOE7Do7\n9hAf8BzBep2gViMSqDDdWWXQ2aesRikRY9cY4HrxMlPBRca8G5zsPGSmvfq05HvEEZ8YnoppO4aM\n899ojPzRE/yxOjYya4xTyGXIPegnejGLO+Qif6VNLJAjoRWICWUe3z+FZaqcOnWXXOJZqqeHyPzi\nFolEHrcmce3+C0wPLDE+vsKJxG0qJ8M8rJwFCfp9W8T7F4j4/VSIcN85yb39c9iyyPjYCvfc0/ho\n8VN8n834AI+Y5gnz3Nx+jmbDz5Uzb2LrImWiSFjsfjDM1vUJwv9lHtXXJUCS93ieDh6qhIlTJEyV\nHip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f4IwNxcCDBBQ9PrtKeqEFpeeTVHnX4DRG0sP2ME0UU8VWZNcO5OZtQhnsQ1et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qUWM9BKc/isdYh6muBNGcDzU6CErINWJzbqCHr4R7tq6hJPpEDCk7MK2qwx/f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qYxdsNyiiu3cKbqMY5G3EC/3cmxqy+nwGQlO3geid4iCp77AqkoG0U6hdrgxxm5BlUvZBMfMkFc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\niz1fo3ZfHG9C+VUB2d/SQvFNN5Hy5z9jrH8X9n8MShrknAZASdJw0Jtg8oX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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1094,21 +1093,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 2", + "display_name": "Python 3", "language": "python", - "name": "python2" + "name": "python3" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 2 + "version": 3 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython2", - "version": "2.7.6" + "pygments_lexer": "ipython3", + "version": "3.5.1" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/tally-arithmetic.ipynb b/docs/source/pythonapi/examples/tally-arithmetic.ipynb index 25c57f3c5..56b3cb45c 100644 --- a/docs/source/pythonapi/examples/tally-arithmetic.ipynb +++ b/docs/source/pythonapi/examples/tally-arithmetic.ipynb @@ -4,9 +4,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "This notebook shows the how tallies can be combined (added, subtracted, multiplied, etc.) using the Python API in order to create derived tallies. Since no covariance information is obtained, it is assumed that tallies are completely independent of one another when propagating uncertainties. The target problem is a simple pin cell.\n", - "\n", - "**Note:** that this Notebook was created using the latest Pandas v0.16.1. Everything in the Notebook will wun with older versions of Pandas, but the multi-indexing option in >v0.15.0 makes the tables look prettier." + "This notebook shows the how tallies can be combined (added, subtracted, multiplied, etc.) using the Python API in order to create derived tallies. Since no covariance information is obtained, it is assumed that tallies are completely independent of one another when propagating uncertainties. The target problem is a simple pin cell." ] }, { @@ -16,18 +14,6 @@ "collapsed": false }, "outputs": [], - "source": [ - "%load_ext autoreload\n", - "%autoreload 2" - ] - }, - { - "cell_type": "code", - "execution_count": 2, - "metadata": { - "collapsed": false - }, - "outputs": [], "source": [ "import glob\n", "from IPython.display import Image\n", @@ -52,7 +38,7 @@ }, { "cell_type": "code", - "execution_count": 3, + "execution_count": 2, "metadata": { "collapsed": true }, @@ -76,7 +62,7 @@ }, { "cell_type": "code", - "execution_count": 4, + "execution_count": 3, "metadata": { "collapsed": false }, @@ -111,7 +97,7 @@ }, { "cell_type": "code", - "execution_count": 5, + "execution_count": 4, "metadata": { "collapsed": false }, @@ -134,7 +120,7 @@ }, { "cell_type": "code", - "execution_count": 6, + "execution_count": 5, "metadata": { "collapsed": false }, @@ -163,7 +149,7 @@ }, { "cell_type": "code", - "execution_count": 7, + "execution_count": 6, "metadata": { "collapsed": false }, @@ -200,7 +186,7 @@ }, { "cell_type": "code", - "execution_count": 8, + "execution_count": 7, "metadata": { "collapsed": false }, @@ -227,7 +213,7 @@ }, { "cell_type": "code", - "execution_count": 9, + "execution_count": 8, "metadata": { "collapsed": false }, @@ -240,7 +226,7 @@ }, { "cell_type": "code", - "execution_count": 10, + "execution_count": 9, "metadata": { "collapsed": false }, @@ -259,7 +245,7 @@ }, { "cell_type": "code", - "execution_count": 11, + "execution_count": 10, "metadata": { "collapsed": true }, @@ -295,7 +281,7 @@ }, { "cell_type": "code", - "execution_count": 12, + "execution_count": 11, "metadata": { "collapsed": false }, @@ -323,7 +309,7 @@ }, { "cell_type": "code", - "execution_count": 13, + "execution_count": 12, "metadata": { "collapsed": false }, @@ -334,7 +320,7 @@ "0" ] }, - "execution_count": 13, + "execution_count": 12, "metadata": {}, "output_type": "execute_result" } @@ -346,19 +332,19 @@ }, { "cell_type": "code", - "execution_count": 14, + "execution_count": 13, "metadata": { "collapsed": false }, "outputs": [ { "data": { - 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"execution_count": 14, + "execution_count": 13, "metadata": {}, "output_type": "execute_result" } @@ -380,7 +366,7 @@ }, { "cell_type": "code", - "execution_count": 15, + "execution_count": 14, "metadata": { "collapsed": false }, @@ -392,7 +378,7 @@ }, { "cell_type": "code", - "execution_count": 16, + "execution_count": 15, "metadata": { "collapsed": false }, @@ -429,7 +415,7 @@ }, { "cell_type": "code", - "execution_count": 17, + "execution_count": 16, "metadata": { "collapsed": true }, @@ -445,7 +431,7 @@ }, { "cell_type": "code", - "execution_count": 18, + "execution_count": 17, "metadata": { "collapsed": false }, @@ -460,7 +446,7 @@ }, { "cell_type": "code", - "execution_count": 19, + "execution_count": 18, "metadata": { "collapsed": false }, @@ -476,7 +462,7 @@ }, { "cell_type": "code", - "execution_count": 20, + "execution_count": 19, "metadata": { "collapsed": true }, @@ -491,7 +477,7 @@ }, { "cell_type": "code", - "execution_count": 21, + "execution_count": 20, "metadata": { "collapsed": true }, @@ -511,7 +497,7 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 21, "metadata": { "collapsed": false }, @@ -530,7 +516,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 22, "metadata": { "collapsed": false, "scrolled": true @@ -556,8 +542,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: ae083cf5d491e6a778d5b762dad19c8d5fe45238\n", - " Date/Time: 2016-04-30 06:37:41\n", + " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", + " Date/Time: 2016-05-05 14:51:45\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -613,20 +599,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 7.0900E-01 seconds\n", - " Reading cross sections = 4.0400E-01 seconds\n", - " Total time in simulation = 1.7108E+01 seconds\n", - " Time in transport only = 1.7093E+01 seconds\n", - " Time in inactive batches = 3.3970E+00 seconds\n", - " Time in active batches = 1.3711E+01 seconds\n", + " Total time for initialization = 7.2500E-01 seconds\n", + " Reading cross sections = 4.4400E-01 seconds\n", + " Total time in simulation = 1.5547E+01 seconds\n", + " Time in transport only = 1.5527E+01 seconds\n", + " Time in inactive batches = 2.2880E+00 seconds\n", + " Time in active batches = 1.3259E+01 seconds\n", " Time synchronizing fission bank = 1.0000E-03 seconds\n", - " Sampling source sites = 1.0000E-03 seconds\n", + " Sampling source sites = 0.0000E+00 seconds\n", " SEND/RECV source sites = 0.0000E+00 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 1.0000E-03 seconds\n", - " Total time elapsed = 1.7835E+01 seconds\n", - " Calculation Rate (inactive) = 3679.72 neutrons/second\n", - " Calculation Rate (active) = 2735.03 neutrons/second\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for finalization = 2.0000E-03 seconds\n", + " Total time elapsed = 1.6291E+01 seconds\n", + " Calculation Rate (inactive) = 5463.29 neutrons/second\n", + " Calculation Rate (active) = 2828.27 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -644,7 +630,7 @@ "0" ] }, - "execution_count": 23, + "execution_count": 22, "metadata": {}, "output_type": "execute_result" } @@ -673,7 +659,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 23, "metadata": { "collapsed": false, "scrolled": true @@ -684,27 +670,6 @@ "sp = openmc.StatePoint('statepoint.20.h5')" ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "You may have also noticed we instructed OpenMC to create a summary file with lots of geometry information in it. This can help to produce more sensible output from the Python API, so we will use the summary file to link against." - ] - }, - { - "cell_type": "code", - "execution_count": 25, - "metadata": { - "collapsed": false, - "scrolled": true - }, - "outputs": [], - "source": [ - "# Load the summary file and link with statepoint\n", - "su = openmc.Summary('summary.h5')\n", - "sp.link_with_summary(su)" - ] - }, { "cell_type": "markdown", "metadata": {}, @@ -716,7 +681,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 24, "metadata": { "collapsed": false }, @@ -752,7 +717,7 @@ "0 total (nu-fission / absorption) 1.04e+00 6.14e-03" ] }, - "execution_count": 26, + "execution_count": 24, "metadata": {}, "output_type": "execute_result" } @@ -776,7 +741,7 @@ }, { "cell_type": "code", - "execution_count": 27, + "execution_count": 25, "metadata": { "collapsed": false }, @@ -816,7 +781,7 @@ "0 0.00e+00 6.25e-07 total absorption 6.93e-01 4.11e-03" ] }, - "execution_count": 27, + "execution_count": 25, "metadata": {}, "output_type": "execute_result" } @@ -838,7 +803,7 @@ }, { "cell_type": "code", - "execution_count": 28, + "execution_count": 26, "metadata": { "collapsed": false }, @@ -878,7 +843,7 @@ "0 0.00e+00 6.25e-07 total nu-fission 1.20e+00 7.60e-03" ] }, - "execution_count": 28, + "execution_count": 26, "metadata": {}, "output_type": "execute_result" } @@ -901,7 +866,7 @@ }, { "cell_type": "code", - "execution_count": 29, + "execution_count": 27, "metadata": { "collapsed": false }, @@ -946,7 +911,7 @@ "0 4.72e-03 " ] }, - "execution_count": 29, + "execution_count": 27, "metadata": {}, "output_type": "execute_result" } @@ -967,7 +932,7 @@ }, { "cell_type": "code", - "execution_count": 30, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -1012,7 +977,7 @@ "0 (nu-fission / absorption) 1.66e+00 1.13e-02 " ] }, - "execution_count": 30, + "execution_count": 28, "metadata": {}, "output_type": "execute_result" } @@ -1032,7 +997,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -1077,7 +1042,7 @@ "0 (((absorption * nu-fission) * absorption) * (n... 1.04e+00 1.32e-02 " ] }, - "execution_count": 31, + "execution_count": 29, "metadata": {}, "output_type": "execute_result" } @@ -1098,7 +1063,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 30, "metadata": { "collapsed": false, "scrolled": true @@ -1114,7 +1079,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -1243,7 +1208,7 @@ "7 (scatter / flux) 3.37e-03 1.44e-05 " ] }, - "execution_count": 33, + "execution_count": 31, "metadata": {}, "output_type": "execute_result" } @@ -1262,7 +1227,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 32, "metadata": { "collapsed": false }, @@ -1294,7 +1259,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 33, "metadata": { "collapsed": false }, @@ -1318,7 +1283,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 34, "metadata": { "collapsed": false }, @@ -1349,7 +1314,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -1430,7 +1395,7 @@ "3 7.32e-04 " ] }, - "execution_count": 37, + "execution_count": 35, "metadata": {}, "output_type": "execute_result" } @@ -1443,7 +1408,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -1584,7 +1549,7 @@ "8 3.20e-03 " ] }, - "execution_count": 38, + "execution_count": 36, "metadata": {}, "output_type": "execute_result" } diff --git a/src/output.F90 b/src/output.F90 index 4b4b966dc..786d9a10e 100644 --- a/src/output.F90 +++ b/src/output.F90 @@ -54,7 +54,7 @@ contains write(UNIT=OUTPUT_UNIT, FMT=*) & ' Copyright: 2011-2016 Massachusetts Institute of Technology' write(UNIT=OUTPUT_UNIT, FMT=*) & - ' License: http://openmc.readthedocs.org/en/latest/license.html' + ' License: http://openmc.readthedocs.io/en/latest/license.html' write(UNIT=OUTPUT_UNIT, FMT='(6X,"Version:",8X,I1,".",I1,".",I1)') & VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE #ifdef GIT_SHA1 From 7a671655865aefa8b99847cf843dc9b5fbd70514 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 7 May 2016 14:36:32 -0400 Subject: [PATCH 082/147] Finished generating ipython notebook and incorporating in to docs --- .../pythonapi/examples/mgxs-part-iv.ipynb | 1871 +++++++++++++++++ .../pythonapi/examples/mgxs-part-iv.rst | 13 + docs/source/pythonapi/index.rst | 1 + openmc/summary.py | 1 + 4 files changed, 1886 insertions(+) create mode 100644 docs/source/pythonapi/examples/mgxs-part-iv.ipynb create mode 100644 docs/source/pythonapi/examples/mgxs-part-iv.rst diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb new file mode 100644 index 000000000..bc85af5c2 --- /dev/null +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -0,0 +1,1871 @@ +{ + "cells": [ + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "This Notebook illustrates the use of the openmc.mgxs.Library class specifically for application in OpenMC's multi-group mode. This example notebook follows the same process as was done in MGXS Part III, but instead uses OpenMC as the multi-group solver. This Notebook illustrates the following features:\n", + "\n", + " Calculation of multi-group cross sections for a fuel assembly\n", + " Automated creation, manipulation and storage of MGXS with openmc.mgxs.Library\n", + " Validation of multi-group cross sections with OpenMC\n", + " Steady-state pin-by-pin fission rates comparison between Continuous-Energy mode and Multi-Group OpenMC.\n", + "\n", + "Note: This Notebook illustrates the use of Pandas DataFrames to containerize multi-group cross section data. We recommend using Pandas >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of Pandas.\n" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "# Generate Input Files" + ] + }, + { + "cell_type": "code", + "execution_count": 1, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "import math\n", + "import pickle\n", + "\n", + "from IPython.display import Image\n", + "import matplotlib.pyplot as plt\n", + "import numpy as np\n", + "import os\n", + "\n", + "import openmc\n", + "import openmc.mgxs\n", + "\n", + "%matplotlib inline" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "\n", + "First we need to define materials that will be used in the problem. Before defining a material, we must create nuclides that are used in the material." + ] + }, + { + "cell_type": "code", + "execution_count": 2, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate some Nuclides\n", + "h1 = openmc.Nuclide('H-1')\n", + "b10 = openmc.Nuclide('B-10')\n", + "o16 = openmc.Nuclide('O-16')\n", + "u235 = openmc.Nuclide('U-235')\n", + "u238 = openmc.Nuclide('U-238')\n", + "zr90 = openmc.Nuclide('Zr-90')" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "With the nuclides we defined, we will now create three materials for the fuel, water, and cladding of the fuel pins." + ] + }, + { + "cell_type": "code", + "execution_count": 3, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# 1.6 enriched fuel\n", + "fuel = openmc.Material(name='1.6% Fuel')\n", + "fuel.set_density('g/cm3', 10.31341)\n", + "fuel.add_nuclide(u235, 3.7503e-4)\n", + "fuel.add_nuclide(u238, 2.2625e-2)\n", + "fuel.add_nuclide(o16, 4.6007e-2)\n", + "\n", + "# borated water\n", + "water = openmc.Material(name='Borated Water')\n", + "water.set_density('g/cm3', 0.740582)\n", + "water.add_nuclide(h1, 4.9457e-2)\n", + "water.add_nuclide(o16, 2.4732e-2)\n", + "water.add_nuclide(b10, 8.0042e-6)\n", + "\n", + "# zircaloy\n", + "zircaloy = openmc.Material(name='Zircaloy')\n", + "zircaloy.set_density('g/cm3', 6.55)\n", + "zircaloy.add_nuclide(zr90, 7.2758e-3)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "With our three materials, we can now create a Materials object that can be exported to an actual XML file." + ] + }, + { + "cell_type": "code", + "execution_count": 4, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate a Materials object\n", + "materials_file = openmc.Materials((fuel, water, zircaloy))\n", + "materials_file.default_xs = '71c'\n", + "\n", + "# Export to \"materials.xml\"\n", + "materials_file.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now let's move on to the geometry. This problem will be a square array of fuel pins and control rod guide tubes for which we can use OpenMC's lattice/universe feature. The basic universe will have three regions for the fuel, the clad, and the surrounding coolant. The first step is to create the bounding surfaces for fuel and clad, as well as the outer bounding surfaces of the problem." + ] + }, + { + "cell_type": "code", + "execution_count": 5, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Create cylinders for the fuel and clad\n", + "fuel_outer_radius = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218)\n", + "clad_outer_radius = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.45720)\n", + "\n", + "# Create boundary planes to surround the geometry\n", + "min_x = openmc.XPlane(x0=-10.71, boundary_type='reflective')\n", + "max_x = openmc.XPlane(x0=+10.71, boundary_type='reflective')\n", + "min_y = openmc.YPlane(y0=-10.71, boundary_type='reflective')\n", + "max_y = openmc.YPlane(y0=+10.71, boundary_type='reflective')\n", + "min_z = openmc.ZPlane(z0=-10., boundary_type='reflective')\n", + "max_z = openmc.ZPlane(z0=+10., boundary_type='reflective')" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "With the surfaces defined, we can now construct a fuel pin cell from cells that are defined by intersections of half-spaces created by the surfaces." + ] + }, + { + "cell_type": "code", + "execution_count": 6, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Create a Universe to encapsulate a fuel pin\n", + "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin')\n", + "\n", + "# Create fuel Cell\n", + "fuel_cell = openmc.Cell(name='1.6% Fuel')\n", + "fuel_cell.fill = fuel\n", + "fuel_cell.region = -fuel_outer_radius\n", + "fuel_pin_universe.add_cell(fuel_cell)\n", + "\n", + "# Create a clad Cell\n", + "clad_cell = openmc.Cell(name='1.6% Clad')\n", + "clad_cell.fill = zircaloy\n", + "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", + "fuel_pin_universe.add_cell(clad_cell)\n", + "\n", + "# Create a moderator Cell\n", + "moderator_cell = openmc.Cell(name='1.6% Moderator')\n", + "moderator_cell.fill = water\n", + "moderator_cell.region = +clad_outer_radius\n", + "fuel_pin_universe.add_cell(moderator_cell)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Likewise, we can construct a control rod guide tube with the same surfaces." + ] + }, + { + "cell_type": "code", + "execution_count": 7, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Create a Universe to encapsulate a control rod guide tube\n", + "guide_tube_universe = openmc.Universe(name='Guide Tube')\n", + "\n", + "# Create guide tube Cell\n", + "guide_tube_cell = openmc.Cell(name='Guide Tube Water')\n", + "guide_tube_cell.fill = water\n", + "guide_tube_cell.region = -fuel_outer_radius\n", + "guide_tube_universe.add_cell(guide_tube_cell)\n", + "\n", + "# Create a clad Cell\n", + "clad_cell = openmc.Cell(name='Guide Clad')\n", + "clad_cell.fill = zircaloy\n", + "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", + "guide_tube_universe.add_cell(clad_cell)\n", + "\n", + "# Create a moderator Cell\n", + "moderator_cell = openmc.Cell(name='Guide Tube Moderator')\n", + "moderator_cell.fill = water\n", + "moderator_cell.region = +clad_outer_radius\n", + "guide_tube_universe.add_cell(moderator_cell)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Using the pin cell universe, we can construct a 17x17 rectangular lattice with a 1.26 cm pitch." + ] + }, + { + "cell_type": "code", + "execution_count": 8, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Create fuel assembly Lattice\n", + "assembly = openmc.RectLattice(name='1.6% Fuel Assembly')\n", + "assembly.dimension = (17, 17)\n", + "assembly.pitch = (1.26, 1.26)\n", + "assembly.lower_left = [-1.26 * 17. / 2.0] * 2" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next, we create a NumPy array of fuel pin and guide tube universes for the lattice." + ] + }, + { + "cell_type": "code", + "execution_count": 9, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Create array indices for guide tube locations in lattice\n", + "template_x = np.array([5, 8, 11, 3, 13, 2, 5, 8, 11, 14, 2, 5, 8,\n", + " 11, 14, 2, 5, 8, 11, 14, 3, 13, 5, 8, 11])\n", + "template_y = np.array([2, 2, 2, 3, 3, 5, 5, 5, 5, 5, 8, 8, 8, 8,\n", + " 8, 11, 11, 11, 11, 11, 13, 13, 14, 14, 14])\n", + "\n", + "# Initialize an empty 17x17 array of the lattice universes\n", + "universes = np.empty((17, 17), dtype=openmc.Universe)\n", + "\n", + "# Fill the array with the fuel pin and guide tube universes\n", + "universes[:,:] = fuel_pin_universe\n", + "universes[template_x, template_y] = guide_tube_universe\n", + "\n", + "# Store the array of universes in the lattice\n", + "assembly.universes = universes" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "OpenMC requires that there is a \"root\" universe. Let us create a root cell that is filled by the pin cell universe and then assign it to the root universe." + ] + }, + { + "cell_type": "code", + "execution_count": 10, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Create root Cell\n", + "root_cell = openmc.Cell(name='root cell')\n", + "root_cell.fill = assembly\n", + "\n", + "# Add boundary planes\n", + "root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z\n", + "\n", + "# Create root Universe\n", + "root_universe = openmc.Universe(universe_id=0, name='root universe')\n", + "root_universe.add_cell(root_cell)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "We now must create a geometry that is assigned a root universe and export it to XML." + ] + }, + { + "cell_type": "code", + "execution_count": 11, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Create Geometry and set root Universe\n", + "geometry = openmc.Geometry()\n", + "geometry.root_universe = root_universe\n", + "# Export to \"geometry.xml\"\n", + "geometry.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "With the geometry and materials finished, we now just need to define simulation parameters. In this case, we will use 10 inactive batches and 40 active batches each with 2500 particles." + ] + }, + { + "cell_type": "code", + "execution_count": 12, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# OpenMC simulation parameters\n", + "batches = 200\n", + "inactive = 10\n", + "particles = 5000\n", + "\n", + "# Instantiate a Settings object\n", + "settings_file = openmc.Settings()\n", + "settings_file.batches = batches\n", + "settings_file.inactive = inactive\n", + "settings_file.particles = particles\n", + "settings_file.output = {'tallies': False}\n", + "\n", + "# Create an initial uniform spatial source distribution over fissionable zones\n", + "bounds = [-10.71, -10.71, -10, 10.71, 10.71, 10.]\n", + "uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)\n", + "settings_file.source = openmc.source.Source(space=uniform_dist)\n", + "\n", + "# Export to \"settings.xml\"\n", + "settings_file.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Let us also create a Plots file that we can use to verify that our fuel assembly geometry was created successfully." + ] + }, + { + "cell_type": "code", + "execution_count": 13, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate a Plot\n", + "plot = openmc.Plot(plot_id=1)\n", + "plot.filename = 'materials-xy'\n", + "plot.origin = [0, 0, 0]\n", + "plot.pixels = [250, 250]\n", + "plot.width = [-10.71*2, -10.71*2]\n", + "plot.color = 'mat'\n", + "\n", + "# Instantiate a Plots object, add Plot, and export to \"plots.xml\"\n", + "plot_file = openmc.Plots([plot])\n", + "plot_file.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "With the plots.xml file, we can now generate and view the plot. OpenMC outputs plots in .ppm format, which can be converted into a compressed format like .png with the convert utility." + ] + }, + { + "cell_type": "code", + "execution_count": 14, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "data": { + "text/plain": [ + "0" + ] + }, + "execution_count": 14, + "metadata": {}, + "output_type": "execute_result" + } + ], + "source": [ + "# Run openmc in plotting mode\n", + "openmc.plot_geometry(output=False)" + ] + }, + { + "cell_type": "code", + "execution_count": 15, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "data": { + "image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nVDE0OjIyOjAzLTA0OjAw01pE9wAAAABJRU5ErkJggg==\n", + "text/plain": [ + "" + ] + }, + "execution_count": 15, + "metadata": {}, + "output_type": "execute_result" + } + ], + "source": [ + "# Convert OpenMC's funky ppm to png\n", + "!convert materials-xy.ppm materials-xy.png\n", + "\n", + "# Display the materials plot inline\n", + "Image(filename='materials-xy.png')" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "As we can see from the plot, we have a nice array of fuel and guide tube pin cells with fuel, cladding, and water!\n", + "\n", + "# Create an MGXS Library\n", + "\n", + "Now we are ready to generate multi-group cross sections! First, let's define a 2-group structure using the built-in EnergyGroups class." + ] + }, + { + "cell_type": "code", + "execution_count": 16, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate a 2-group EnergyGroups object\n", + "groups = openmc.mgxs.EnergyGroups()\n", + "groups.group_edges = np.array([0., 0.625e-6, 20.])" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next, we will instantiate an openmc.mgxs.Library for the energy groups with our the fuel assembly geometry." + ] + }, + { + "cell_type": "code", + "execution_count": 17, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Initialize an 2-group MGXS Library for OpenMOC\n", + "mgxs_lib = openmc.mgxs.Library(geometry)\n", + "mgxs_lib.energy_groups = groups" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now, we must specify to the Library which types of cross sections to compute. OpenMC's multi-group mode can accept isotropic flux-weighted cross sections or angle-dependent cross sections, as well as supporting anisotropic scattering represented by either Legendre polynomials, histogram, or tabular angular distributions. At this time the MGXS Library class only supports the generation of isotropic flux-weighted cross sections and P0 scattering, so that is what will be used for this example. Therefore, we will create the following multi-group cross sections needed to run an OpenMC simulation to verify the accuracy of our cross sections: \"transport\", \"absorption\", \"nu-fission\", '\"fission\", \"nu-scatter matrix\", \"scatter matrix\", and \"chi\".\n", + "\"scatter matrix\" is needed in addition to \"nu-scatter matrix\" because OpenMC's multi-group mode can treat scattering multiplication (i.e., (n,xn) reactions)) explicitly instead of adjusting the absorption cross section to maintain neutron balance, and using this explicit treatment would require tallying of both types of scattering matrices." + ] + }, + { + "cell_type": "code", + "execution_count": 18, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Specify multi-group cross section types to compute\n", + "mgxs_lib.mgxs_types = ['transport', 'absorption', 'nu-fission', 'fission',\n", + " 'nu-scatter matrix', 'scatter matrix', 'chi']" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material,\" \"cell,\" and \"universe\" domain types. We will use a \"cell\" domain type here to compute cross sections in each of the cells in the fuel assembly geometry.\n", + "\n", + "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell or universe) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property. In our case, we wish to compute multi-group cross sections in each and every cell since they will be needed in our downstream multi-group OpenMC calculation on the identical combinatorial geometry mesh." + ] + }, + { + "cell_type": "code", + "execution_count": 19, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Specify a \"cell\" domain type for the cross section tally filters\n", + "mgxs_lib.domain_type = \"cell\"\n", + "\n", + "# Specify the cell domains over which to compute multi-group cross sections\n", + "mgxs_lib.domains = geometry.get_all_material_cells()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "We will instruct the library to not compute cross sections on a nuclide-by-nuclide basis, and instead to focus on generating material-specific macroscopic cross sections.\n", + "\n", + "**NOTE:** The default value of the `by_nuclide` parameter is `False`, so the following step is not necessary but is included for illustrative purposes." + ] + }, + { + "cell_type": "code", + "execution_count": 20, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Do not compute cross sections on a nuclide-by-nuclide basis\n", + "mgxs_lib.by_nuclide = False" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Lastly, we use the `Library` to construct the tallies needed to compute all of the requested multi-group cross sections in each domain and nuclide." + ] + }, + { + "cell_type": "code", + "execution_count": 21, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Construct all tallies needed for the multi-group cross section library\n", + "mgxs_lib.build_library()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "The tallies can now be export to a \"tallies.xml\" input file for OpenMC.\n", + "\n", + "**NOTE:** At this point the `Library` has constructed nearly 100 distinct Tally objects. The overhead to tally in OpenMC scales as O(N) for N tallies, which can become a bottleneck for large tally datasets. To compensate for this, the Python API's `Tally`, `Filter` and `Tallies` classes allow for the smart merging of tallies when possible. The `Library` class supports this runtime optimization with the use of the optional `merge` parameter (`False` by default) for the `Library.add_to_tallies_file(...)` method, as shown below." + ] + }, + { + "cell_type": "code", + "execution_count": 22, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Create a \"tallies.xml\" file for the MGXS Library\n", + "tallies_file = openmc.Tallies()\n", + "mgxs_lib.add_to_tallies_file(tallies_file, merge=True)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "In addition, we instantiate a fission rate mesh tally to compare with the multi-group result." + ] + }, + { + "cell_type": "code", + "execution_count": 23, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate a tally Mesh\n", + "mesh = openmc.Mesh(mesh_id=1)\n", + "mesh.type = 'regular'\n", + "mesh.dimension = [17, 17]\n", + "mesh.lower_left = [-10.71, -10.71]\n", + "mesh.upper_right = [+10.71, +10.71]\n", + "\n", + "# Instantiate tally Filter\n", + "mesh_filter = openmc.Filter()\n", + "mesh_filter.mesh = mesh\n", + "\n", + "# Instantiate the Tally\n", + "tally = openmc.Tally(name='mesh tally')\n", + "tally.filters = [mesh_filter]\n", + "tally.scores = ['fission']\n", + "\n", + "# Add tally to collection\n", + "tallies_file.append(tally)" + ] + }, + { + "cell_type": "code", + "execution_count": 24, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Export all tallies to a \"tallies.xml\" file\n", + "tallies_file.export_to_xml()" + ] + }, + { + "cell_type": "code", + "execution_count": 25, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "\n", + " .d88888b. 888b d888 .d8888b.\n", + " d88P\" \"Y88b 8888b d8888 d88P Y88b\n", + " 888 888 88888b.d88888 888 888\n", + " 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n", + " 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n", + " 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n", + " Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n", + " \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n", + "__________________888______________________________________________________\n", + " 888\n", + " 888\n", + "\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " Version: 0.7.1\n", + " Git SHA1: 179e9ab147e505563d118ed58096b3d225160ffa\n", + " Date/Time: 2016-05-07 14:22:04\n", + " OpenMP Threads: 4\n", + "\n", + " ===========================================================================\n", + " ========================> INITIALIZATION <=========================\n", + " ===========================================================================\n", + "\n", + " Reading settings XML file...\n", + " Reading cross sections XML file...\n", + " Reading geometry XML file...\n", + " Reading materials XML file...\n", + " Reading tallies XML file...\n", + " Building neighboring cells lists for each surface...\n", + " Loading ACE cross section table: 92235.71c\n", + " Loading ACE cross section table: 92238.71c\n", + " Loading ACE cross section table: 8016.71c\n", + " Loading ACE cross section table: 1001.71c\n", + " Loading ACE cross section table: 5010.71c\n", + " Loading ACE cross section table: 40090.71c\n", + " Maximum neutron transport energy: 20.0000 MeV for 92235.71c\n", + " Initializing source particles...\n", + "\n", + " ===========================================================================\n", + " ====================> K EIGENVALUE SIMULATION <====================\n", + " ===========================================================================\n", + "\n", + " Bat./Gen. k Average k \n", + " ========= ======== ==================== \n", + " 1/1 1.05162 \n", + " 2/1 1.05369 \n", + " 3/1 1.02989 \n", + " 4/1 1.00126 \n", + " 5/1 1.03151 \n", + " 6/1 1.00183 \n", + " 7/1 0.99379 \n", + " 8/1 1.04193 \n", + " 9/1 1.01578 \n", + " 10/1 1.03349 \n", + " 11/1 1.03354 \n", + " 12/1 1.03646 1.03500 +/- 0.00146\n", + " 13/1 1.00873 1.02624 +/- 0.00880\n", + " 14/1 1.04263 1.03034 +/- 0.00745\n", + " 15/1 1.01556 1.02738 +/- 0.00648\n", + " 16/1 1.04897 1.03098 +/- 0.00640\n", + " 17/1 1.01796 1.02912 +/- 0.00572\n", + " 18/1 1.02276 1.02833 +/- 0.00502\n", + " 19/1 1.04003 1.02963 +/- 0.00461\n", + " 20/1 1.00695 1.02736 +/- 0.00471\n", + " 21/1 1.00012 1.02488 +/- 0.00493\n", + " 22/1 1.03580 1.02579 +/- 0.00459\n", + " 23/1 1.03427 1.02644 +/- 0.00427\n", + " 24/1 1.06024 1.02886 +/- 0.00463\n", + " 25/1 1.00742 1.02743 +/- 0.00454\n", + " 26/1 1.02556 1.02731 +/- 0.00425\n", + " 27/1 1.02207 1.02700 +/- 0.00401\n", + " 28/1 1.05847 1.02875 +/- 0.00416\n", + " 29/1 1.01125 1.02783 +/- 0.00404\n", + " 30/1 1.03213 1.02804 +/- 0.00384\n", + " 31/1 1.02241 1.02778 +/- 0.00366\n", + " 32/1 1.02675 1.02773 +/- 0.00349\n", + " 33/1 1.05484 1.02891 +/- 0.00354\n", + " 34/1 1.01893 1.02849 +/- 0.00341\n", + " 35/1 0.99044 1.02697 +/- 0.00361\n", + " 36/1 1.02602 1.02693 +/- 0.00347\n", + " 37/1 1.04107 1.02746 +/- 0.00338\n", + " 38/1 1.03237 1.02763 +/- 0.00326\n", + " 39/1 1.01489 1.02719 +/- 0.00318\n", + " 40/1 1.01065 1.02664 +/- 0.00312\n", + " 41/1 1.03722 1.02698 +/- 0.00304\n", + " 42/1 1.04339 1.02750 +/- 0.00298\n", + " 43/1 1.00921 1.02694 +/- 0.00294\n", + " 44/1 1.04576 1.02750 +/- 0.00291\n", + " 45/1 1.02580 1.02745 +/- 0.00283\n", + " 46/1 1.03464 1.02765 +/- 0.00275\n", + " 47/1 1.01552 1.02732 +/- 0.00270\n", + " 48/1 1.03357 1.02748 +/- 0.00263\n", + " 49/1 1.03439 1.02766 +/- 0.00257\n", + " 50/1 1.04281 1.02804 +/- 0.00253\n", + " 51/1 1.02902 1.02806 +/- 0.00247\n", + " 52/1 1.02245 1.02793 +/- 0.00241\n", + " 53/1 1.05271 1.02851 +/- 0.00243\n", + " 54/1 0.98630 1.02755 +/- 0.00256\n", + " 55/1 1.02690 1.02753 +/- 0.00250\n", + " 56/1 1.04107 1.02783 +/- 0.00246\n", + " 57/1 1.03029 1.02788 +/- 0.00241\n", + " 58/1 1.01874 1.02769 +/- 0.00237\n", + " 59/1 1.04211 1.02798 +/- 0.00234\n", + " 60/1 0.99584 1.02734 +/- 0.00238\n", + " 61/1 1.05166 1.02782 +/- 0.00238\n", + " 62/1 1.05572 1.02835 +/- 0.00239\n", + " 63/1 1.02694 1.02833 +/- 0.00235\n", + " 64/1 1.03314 1.02842 +/- 0.00231\n", + " 65/1 1.05850 1.02896 +/- 0.00233\n", + " 66/1 1.01100 1.02864 +/- 0.00231\n", + " 67/1 1.03784 1.02880 +/- 0.00227\n", + " 68/1 1.04084 1.02901 +/- 0.00224\n", + " 69/1 1.03932 1.02919 +/- 0.00221\n", + " 70/1 1.02564 1.02913 +/- 0.00218\n", + " 71/1 1.00027 1.02865 +/- 0.00219\n", + " 72/1 1.02385 1.02858 +/- 0.00216\n", + " 73/1 1.04885 1.02890 +/- 0.00215\n", + " 74/1 1.00298 1.02849 +/- 0.00215\n", + " 75/1 1.02009 1.02836 +/- 0.00212\n", + " 76/1 1.04505 1.02862 +/- 0.00211\n", + " 77/1 1.02889 1.02862 +/- 0.00207\n", + " 78/1 1.01306 1.02839 +/- 0.00206\n", + " 79/1 1.01817 1.02824 +/- 0.00203\n", + " 80/1 1.00533 1.02792 +/- 0.00203\n", + " 81/1 1.04439 1.02815 +/- 0.00201\n", + " 82/1 1.02212 1.02806 +/- 0.00199\n", + " 83/1 0.99419 1.02760 +/- 0.00201\n", + " 84/1 1.07132 1.02819 +/- 0.00207\n", + " 85/1 1.02710 1.02818 +/- 0.00204\n", + " 86/1 1.01702 1.02803 +/- 0.00202\n", + " 87/1 1.02134 1.02794 +/- 0.00200\n", + " 88/1 1.05231 1.02826 +/- 0.00200\n", + " 89/1 1.05290 1.02857 +/- 0.00200\n", + " 90/1 1.05751 1.02893 +/- 0.00200\n", + " 91/1 1.03970 1.02906 +/- 0.00198\n", + " 92/1 0.99678 1.02867 +/- 0.00200\n", + " 93/1 1.04471 1.02886 +/- 0.00198\n", + " 94/1 1.00820 1.02862 +/- 0.00198\n", + " 95/1 1.05823 1.02896 +/- 0.00198\n", + " 96/1 1.05118 1.02922 +/- 0.00198\n", + " 97/1 1.03617 1.02930 +/- 0.00196\n", + " 98/1 1.00585 1.02904 +/- 0.00195\n", + " 99/1 1.06663 1.02946 +/- 0.00198\n", + " 100/1 1.01802 1.02933 +/- 0.00196\n", + " 101/1 1.02695 1.02931 +/- 0.00194\n", + " 102/1 1.01642 1.02917 +/- 0.00192\n", + " 103/1 1.02567 1.02913 +/- 0.00190\n", + " 104/1 1.03519 1.02919 +/- 0.00188\n", + " 105/1 1.02439 1.02914 +/- 0.00186\n", + " 106/1 1.03779 1.02923 +/- 0.00184\n", + " 107/1 1.01304 1.02906 +/- 0.00183\n", + " 108/1 1.02541 1.02903 +/- 0.00181\n", + " 109/1 1.04297 1.02917 +/- 0.00180\n", + " 110/1 1.00442 1.02892 +/- 0.00180\n", + " 111/1 1.03102 1.02894 +/- 0.00178\n", + " 112/1 1.00380 1.02870 +/- 0.00178\n", + " 113/1 1.04010 1.02881 +/- 0.00177\n", + " 114/1 1.01297 1.02865 +/- 0.00176\n", + " 115/1 1.00130 1.02839 +/- 0.00176\n", + " 116/1 1.02001 1.02831 +/- 0.00174\n", + " 117/1 1.03847 1.02841 +/- 0.00173\n", + " 118/1 1.00371 1.02818 +/- 0.00173\n", + " 119/1 1.02650 1.02817 +/- 0.00171\n", + " 120/1 1.00767 1.02798 +/- 0.00171\n", + " 121/1 1.00408 1.02776 +/- 0.00171\n", + " 122/1 1.00235 1.02754 +/- 0.00171\n", + " 123/1 1.01212 1.02740 +/- 0.00170\n", + " 124/1 1.03278 1.02745 +/- 0.00168\n", + " 125/1 1.00818 1.02728 +/- 0.00168\n", + " 126/1 1.02132 1.02723 +/- 0.00166\n", + " 127/1 1.03677 1.02731 +/- 0.00165\n", + " 128/1 1.04148 1.02743 +/- 0.00164\n", + " 129/1 1.01245 1.02730 +/- 0.00163\n", + " 130/1 1.04172 1.02742 +/- 0.00162\n", + " 131/1 1.04519 1.02757 +/- 0.00162\n", + " 132/1 1.02495 1.02755 +/- 0.00160\n", + " 133/1 0.99747 1.02731 +/- 0.00161\n", + " 134/1 1.02411 1.02728 +/- 0.00160\n", + " 135/1 1.05750 1.02752 +/- 0.00160\n", + " 136/1 1.02341 1.02749 +/- 0.00159\n", + " 137/1 1.02212 1.02745 +/- 0.00158\n", + " 138/1 1.03464 1.02750 +/- 0.00157\n", + " 139/1 1.05920 1.02775 +/- 0.00157\n", + " 140/1 1.01911 1.02768 +/- 0.00156\n", + " 141/1 1.03076 1.02771 +/- 0.00155\n", + " 142/1 1.03648 1.02777 +/- 0.00154\n", + " 143/1 1.00382 1.02759 +/- 0.00154\n", + " 144/1 1.00366 1.02741 +/- 0.00154\n", + " 145/1 1.01638 1.02733 +/- 0.00153\n", + " 146/1 1.02418 1.02731 +/- 0.00152\n", + " 147/1 0.99267 1.02706 +/- 0.00153\n", + " 148/1 1.02575 1.02705 +/- 0.00152\n", + " 149/1 0.98560 1.02675 +/- 0.00153\n", + " 150/1 1.02725 1.02675 +/- 0.00152\n", + " 151/1 1.03723 1.02683 +/- 0.00151\n", + " 152/1 1.00857 1.02670 +/- 0.00151\n", + " 153/1 1.00642 1.02656 +/- 0.00151\n", + " 154/1 1.03461 1.02661 +/- 0.00150\n", + " 155/1 1.00088 1.02643 +/- 0.00150\n", + " 156/1 1.02589 1.02643 +/- 0.00149\n", + " 157/1 1.02494 1.02642 +/- 0.00148\n", + " 158/1 1.03303 1.02646 +/- 0.00147\n", + " 159/1 1.02276 1.02644 +/- 0.00146\n", + " 160/1 1.03293 1.02648 +/- 0.00145\n", + " 161/1 1.04758 1.02662 +/- 0.00144\n", + " 162/1 1.01033 1.02652 +/- 0.00144\n", + " 163/1 1.03883 1.02660 +/- 0.00143\n", + " 164/1 1.00519 1.02646 +/- 0.00143\n", + " 165/1 1.05958 1.02667 +/- 0.00144\n", + " 166/1 1.03849 1.02675 +/- 0.00143\n", + " 167/1 1.02306 1.02672 +/- 0.00142\n", + " 168/1 1.02693 1.02672 +/- 0.00141\n", + " 169/1 1.02584 1.02672 +/- 0.00140\n", + " 170/1 0.99388 1.02651 +/- 0.00141\n", + " 171/1 0.99376 1.02631 +/- 0.00141\n", + " 172/1 1.00453 1.02618 +/- 0.00141\n", + " 173/1 1.04516 1.02629 +/- 0.00141\n", + " 174/1 1.02402 1.02628 +/- 0.00140\n", + " 175/1 0.99012 1.02606 +/- 0.00141\n", + " 176/1 1.02084 1.02603 +/- 0.00140\n", + " 177/1 1.03959 1.02611 +/- 0.00139\n", + " 178/1 1.01719 1.02606 +/- 0.00139\n", + " 179/1 1.01671 1.02600 +/- 0.00138\n", + " 180/1 1.03691 1.02606 +/- 0.00137\n", + " 181/1 1.04276 1.02616 +/- 0.00137\n", + " 182/1 1.02002 1.02613 +/- 0.00136\n", + " 183/1 1.03081 1.02615 +/- 0.00135\n", + " 184/1 1.02432 1.02614 +/- 0.00135\n", + " 185/1 1.02225 1.02612 +/- 0.00134\n", + " 186/1 1.04722 1.02624 +/- 0.00134\n", + " 187/1 0.98045 1.02598 +/- 0.00135\n", + " 188/1 1.02555 1.02598 +/- 0.00135\n", + " 189/1 1.03645 1.02604 +/- 0.00134\n", + " 190/1 1.00407 1.02592 +/- 0.00134\n", + " 191/1 1.03033 1.02594 +/- 0.00133\n", + " 192/1 1.04175 1.02603 +/- 0.00133\n", + " 193/1 1.00555 1.02592 +/- 0.00132\n", + " 194/1 1.00183 1.02578 +/- 0.00132\n", + " 195/1 1.04328 1.02588 +/- 0.00132\n", + " 196/1 1.03041 1.02590 +/- 0.00131\n", + " 197/1 1.04791 1.02602 +/- 0.00131\n", + " 198/1 1.01366 1.02596 +/- 0.00130\n", + " 199/1 1.04471 1.02605 +/- 0.00130\n", + " 200/1 1.02416 1.02604 +/- 0.00129\n", + " Creating state point statepoint.200.h5...\n", + "\n", + " ===========================================================================\n", + " ======================> SIMULATION FINISHED <======================\n", + " ===========================================================================\n", + "\n", + "\n", + " =======================> TIMING STATISTICS <=======================\n", + "\n", + " Total time for initialization = 1.4810E+00 seconds\n", + " Reading cross sections = 1.1600E+00 seconds\n", + " Total time in simulation = 9.8823E+01 seconds\n", + " Time in transport only = 9.8622E+01 seconds\n", + " Time in inactive batches = 2.1290E+00 seconds\n", + " Time in active batches = 9.6694E+01 seconds\n", + " Time synchronizing fission bank = 1.4000E-02 seconds\n", + " Sampling source sites = 1.1000E-02 seconds\n", + " SEND/RECV source sites = 3.0000E-03 seconds\n", + " Time accumulating tallies = 2.0000E-03 seconds\n", + " Total time for finalization = 0.0000E+00 seconds\n", + " Total time elapsed = 1.0031E+02 seconds\n", + " Calculation Rate (inactive) = 23485.2 neutrons/second\n", + " Calculation Rate (active) = 9824.81 neutrons/second\n", + "\n", + " ============================> RESULTS <============================\n", + "\n", + " k-effective (Collision) = 1.02505 +/- 0.00122\n", + " k-effective (Track-length) = 1.02604 +/- 0.00129\n", + " k-effective (Absorption) = 1.02501 +/- 0.00111\n", + " Combined k-effective = 1.02544 +/- 0.00091\n", + " Leakage Fraction = 0.00000 +/- 0.00000\n", + "\n" + ] + }, + { + "data": { + "text/plain": [ + "0" + ] + }, + "execution_count": 25, + "metadata": {}, + "output_type": "execute_result" + } + ], + "source": [ + "# Run OpenMC\n", + "openmc.run()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "To make the files available and not be over-written when running the multi-group calculation, we will now rename the statepoint and summary files." + ] + }, + { + "cell_type": "code", + "execution_count": 26, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Move the StatePoint File\n", + "ce_spfile = './ce.h5'\n", + "os.rename('statepoint.' + str(batches) + '.h5', ce_spfile)\n", + "# Move the Summary file\n", + "ce_sumfile = './ce_summary.h5'\n", + "os.rename('summary.h5', ce_sumfile)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "# Tally Data Processing\n", + "\n", + "Our simulation ran successfully and created statepoint and summary output files. We begin our analysis by instantiating a `StatePoint` object." + ] + }, + { + "cell_type": "code", + "execution_count": 27, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Load the statepoint file\n", + "sp = openmc.StatePoint(ce_spfile)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next we will save the value of keff from the continuous-energy calculation for later comparison" + ] + }, + { + "cell_type": "code", + "execution_count": 28, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "ce_keff = sp.k_combined" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint." + ] + }, + { + "cell_type": "code", + "execution_count": 29, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "su = openmc.Summary(ce_sumfile)\n", + "sp.link_with_summary(su)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next we will extract our fission distribution results from the statepoint for later comparison." + ] + }, + { + "cell_type": "code", + "execution_count": 30, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Get the OpenMC fission rate mesh tally data\n", + "mesh_tally = sp.get_tally(name='mesh tally')\n", + "openmc_fission_rates = mesh_tally.get_values(scores=['fission'])\n", + "\n", + "# Reshape array to 2D for plotting\n", + "openmc_fission_rates.shape = (17,17)\n", + "\n", + "# Normalize to the average pin power\n", + "openmc_fission_rates /= np.mean(openmc_fission_rates)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "The statepoint is now ready to be analyzed by the `Library`. We simply have to load the tallies from the statepoint into the `Library` and our `MGXS` objects will compute the cross sections for us under-the-hood." + ] + }, + { + "cell_type": "code", + "execution_count": 31, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Initialize MGXS Library with OpenMC statepoint data\n", + "mgxs_lib.load_from_statepoint(sp)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "The next step will be to prepare the input for OpenMC to use our newly created multi-group data." + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "# Multi-Group OpenMC Calculation" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "We will now use the `Library` to produce a multi-group cross section data set for use by the OpenMC multi-group solver. " + ] + }, + { + "cell_type": "code", + "execution_count": 32, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "name": "stderr", + "output_type": "stream", + "text": [ + "/home/nelsonag/git/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", + " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n", + "/home/nelsonag/git/openmc/openmc/tallies.py:1997: RuntimeWarning: invalid value encountered in true_divide\n", + " other_rel_err = data['other']['std. dev.'] / data['other']['mean']\n", + "/home/nelsonag/git/openmc/openmc/tallies.py:1998: RuntimeWarning: invalid value encountered in true_divide\n", + " new_tally._mean = data['self']['mean'] / data['other']['mean']\n" + ] + }, + { + "data": { + "text/plain": [ + "{10000: 'fuel.2g',\n", + " 10001: 'fuel_clad.2g',\n", + " 10002: 'fuel_mod.2g',\n", + " 10003: 'gt_inmod.2g',\n", + " 10004: 'gt_clad.2g',\n", + " 10005: 'gt_outmod.2g'}" + ] + }, + "execution_count": 32, + "metadata": {}, + "output_type": "execute_result" + } + ], + "source": [ + "mgxs_lib.write_mg_library(filename='mgxs', xs_type='macro',\n", + " domain_names=['fuel', 'fuel_clad', 'fuel_mod',\n", + " 'gt_inmod', 'gt_clad', 'gt_outmod'],\n", + " xs_ids='2g')" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now we will need to recreate similar xml files from above, beginning with materials.xml" + ] + }, + { + "cell_type": "code", + "execution_count": 33, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Instantiate our Macroscopic Data\n", + "fuel_macro = openmc.Macroscopic('fuel')\n", + "fuel_clad_macro = openmc.Macroscopic('fuel_clad')\n", + "fuel_mod_macro = openmc.Macroscopic('fuel_mod')\n", + "gt_inmod_macro = openmc.Macroscopic('gt_inmod')\n", + "gt_clad_macro = openmc.Macroscopic('gt_clad')\n", + "gt_outmod_macro = openmc.Macroscopic('gt_outmod')\n", + "\n", + "# Now define the materials\n", + "\n", + "# 1.6 enriched fuel UO2\n", + "fuel = openmc.Material(name='1.6% Fuel UO2')\n", + "fuel.set_density('macro', 1.0)\n", + "fuel.add_macroscopic(fuel_macro)\n", + "\n", + "# 1.6 enriched fuel cladding\n", + "fuel_clad = openmc.Material(name='1.6% Fuel Clad')\n", + "fuel_clad.set_density('macro', 1.0)\n", + "fuel_clad.add_macroscopic(fuel_clad_macro)\n", + "\n", + "# 1.6 enriched fuel moderator\n", + "fuel_mod = openmc.Material(name='1.6% Fuel Water')\n", + "fuel_mod.set_density('macro', 1.0)\n", + "fuel_mod.add_macroscopic(fuel_mod_macro)\n", + "\n", + "# Guide Tube Inner Moderator\n", + "gt_inmod = openmc.Material(name='GT Inner Water')\n", + "gt_inmod.set_density('macro', 1.0)\n", + "gt_inmod.add_macroscopic(gt_inmod_macro)\n", + "\n", + "# Guide Tube Cladding\n", + "gt_clad = openmc.Material(name='GT Clad')\n", + "gt_clad.set_density('macro', 1.0)\n", + "gt_clad.add_macroscopic(gt_clad_macro)\n", + "\n", + "# Guide Tube Outer Moderator\n", + "gt_outmod = openmc.Material(name='GT Outer Water')\n", + "gt_outmod.set_density('macro', 1.0)\n", + "gt_outmod.add_macroscopic(gt_outmod_macro)\n", + "\n", + "# Finally, instantiate our Materials object\n", + "materials_file = openmc.Materials((fuel, fuel_clad, fuel_mod,\n", + " gt_inmod, gt_clad, gt_outmod))\n", + "materials_file.default_xs = '2g'\n", + "\n", + "# Export to \"materials.xml\"\n", + "materials_file.export_to_xml()\n" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "For our geometry files we will simply repeat what as done for continuous-energy mode, except change the cell fill (i.e., the material) to use our newly defined materials." + ] + }, + { + "cell_type": "code", + "execution_count": 34, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Create a Universe to encapsulate a fuel pin\n", + "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin')\n", + "\n", + "# Create fuel Cell\n", + "fuel_cell = openmc.Cell(name='1.6% Fuel')\n", + "fuel_cell.fill = fuel\n", + "fuel_cell.region = -fuel_outer_radius\n", + "fuel_pin_universe.add_cell(fuel_cell)\n", + "\n", + "# Create a clad Cell\n", + "clad_cell = openmc.Cell(name='1.6% Clad')\n", + "clad_cell.fill = fuel_clad\n", + "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", + "fuel_pin_universe.add_cell(clad_cell)\n", + "\n", + "# Create a moderator Cell\n", + "moderator_cell = openmc.Cell(name='1.6% Moderator')\n", + "moderator_cell.fill = fuel_mod\n", + "moderator_cell.region = +clad_outer_radius\n", + "fuel_pin_universe.add_cell(moderator_cell)\n", + "\n", + "# Create a Universe to encapsulate a control rod guide tube\n", + "guide_tube_universe = openmc.Universe(name='Guide Tube')\n", + "\n", + "# Create guide tube Cell\n", + "guide_tube_cell = openmc.Cell(name='Guide Tube Water')\n", + "guide_tube_cell.fill = gt_inmod\n", + "guide_tube_cell.region = -fuel_outer_radius\n", + "guide_tube_universe.add_cell(guide_tube_cell)\n", + "\n", + "# Create a clad Cell\n", + "clad_cell = openmc.Cell(name='Guide Clad')\n", + "clad_cell.fill = gt_clad\n", + "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", + "guide_tube_universe.add_cell(clad_cell)\n", + "\n", + "# Create a moderator Cell\n", + "moderator_cell = openmc.Cell(name='Guide Tube Moderator')\n", + "moderator_cell.fill = gt_outmod\n", + "moderator_cell.region = +clad_outer_radius\n", + "guide_tube_universe.add_cell(moderator_cell)\n", + "\n", + "# Create fuel assembly Lattice\n", + "assembly = openmc.RectLattice(name='1.6% Fuel Assembly')\n", + "assembly.dimension = (17, 17)\n", + "assembly.pitch = (1.26, 1.26)\n", + "assembly.lower_left = [-1.26 * 17. / 2.0] * 2\n", + "\n", + "# Create array indices for guide tube locations in lattice\n", + "template_x = np.array([5, 8, 11, 3, 13, 2, 5, 8, 11, 14, 2, 5, 8,\n", + " 11, 14, 2, 5, 8, 11, 14, 3, 13, 5, 8, 11])\n", + "template_y = np.array([2, 2, 2, 3, 3, 5, 5, 5, 5, 5, 8, 8, 8, 8,\n", + " 8, 11, 11, 11, 11, 11, 13, 13, 14, 14, 14])\n", + "\n", + "# Initialize an empty 17x17 array of the lattice universes\n", + "universes = np.empty((17, 17), dtype=openmc.Universe)\n", + "\n", + "# Fill the array with the fuel pin and guide tube universes\n", + "universes[:,:] = fuel_pin_universe\n", + "universes[template_x, template_y] = guide_tube_universe\n", + "\n", + "# Store the array of universes in the lattice\n", + "assembly.universes = universes\n", + "\n", + "# Create root Cell\n", + "root_cell = openmc.Cell(name='root cell')\n", + "root_cell.fill = assembly\n", + "\n", + "# Add boundary planes\n", + "root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z\n", + "\n", + "# Create root Universe\n", + "root_universe = openmc.Universe(universe_id=0, name='root universe')\n", + "root_universe.add_cell(root_cell)\n", + "\n", + "# Create Geometry and set root Universe\n", + "geometry = openmc.Geometry()\n", + "geometry.root_universe = root_universe\n", + "# Export to \"geometry.xml\"\n", + "geometry.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next, we can make the changes we need to the settings file.\n", + "These changes are limited to telling OpenMC we will be running a multi-group calculation and pointing to the location of our multi-group cross section file." + ] + }, + { + "cell_type": "code", + "execution_count": 35, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Set the location of the cross sections file\n", + "settings_file.cross_sections = './mgxs.xml'\n", + "settings_file.energy_mode = 'multi-group'\n", + "\n", + "# Export to \"settings.xml\"\n", + "settings_file.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Finally, lets tell OpenMC we want to tally fissions over a mesh for comparison. " + ] + }, + { + "cell_type": "code", + "execution_count": 36, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Instantiate a tally Mesh\n", + "mesh = openmc.Mesh(mesh_id=1)\n", + "mesh.type = 'regular'\n", + "mesh.dimension = [17, 17]\n", + "mesh.lower_left = [-10.71, -10.71]\n", + "mesh.upper_right = [+10.71, +10.71]\n", + "\n", + "# Instantiate tally Filter\n", + "mesh_filter = openmc.Filter()\n", + "mesh_filter.mesh = mesh\n", + "\n", + "# Instantiate the Tally\n", + "tally = openmc.Tally(name='mesh tally')\n", + "tally.filters = [mesh_filter]\n", + "tally.scores = ['fission']\n", + "\n", + "# Add tally to collection\n", + "tallies_file.append(tally)\n", + "\n", + "# Export all tallies to a \"tallies.xml\" file\n", + "tallies_file.export_to_xml()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Before we run the calculation we will close the StatePoint file (as we are about to over-write it), and then we can run the multi-group calculation." + ] + }, + { + "cell_type": "code", + "execution_count": 37, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "\n", + " .d88888b. 888b d888 .d8888b.\n", + " d88P\" \"Y88b 8888b d8888 d88P Y88b\n", + " 888 888 88888b.d88888 888 888\n", + " 888 888 88888b. .d88b. 88888b. 888Y88888P888 888 \n", + " 888 888 888 \"88b d8P Y8b 888 \"88b 888 Y888P 888 888 \n", + " 888 888 888 888 88888888 888 888 888 Y8P 888 888 888\n", + " Y88b. .d88P 888 d88P Y8b. 888 888 888 \" 888 Y88b d88P\n", + " \"Y88888P\" 88888P\" \"Y8888 888 888 888 888 \"Y8888P\"\n", + "__________________888______________________________________________________\n", + " 888\n", + " 888\n", + "\n", + " Copyright: 2011-2016 Massachusetts Institute of Technology\n", + " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " Version: 0.7.1\n", + " Git SHA1: 179e9ab147e505563d118ed58096b3d225160ffa\n", + " Date/Time: 2016-05-07 14:23:45\n", + " OpenMP Threads: 4\n", + "\n", + " ===========================================================================\n", + " ========================> INITIALIZATION <=========================\n", + " ===========================================================================\n", + "\n", + " Reading settings XML file...\n", + " Reading cross sections XML file...\n", + " Reading geometry XML file...\n", + " Reading materials XML file...\n", + " Reading tallies XML file...\n", + " Building neighboring cells lists for each surface...\n", + " Loading Cross Section Data...\n", + " Loading fuel.2g Data...\n", + " Loading fuel_clad.2g Data...\n", + " Loading fuel_mod.2g Data...\n", + " Loading gt_inmod.2g Data...\n", + " Loading gt_clad.2g Data...\n", + " Loading gt_outmod.2g Data...\n", + " Initializing source particles...\n", + "\n", + " ===========================================================================\n", + " ====================> K EIGENVALUE SIMULATION <====================\n", + " ===========================================================================\n", + "\n", + " Bat./Gen. k Average k \n", + " ========= ======== ==================== \n", + " 1/1 1.01863 \n", + " 2/1 1.02630 \n", + " 3/1 1.03077 \n", + " 4/1 0.99715 \n", + " 5/1 1.02328 \n", + " 6/1 1.02283 \n", + " 7/1 1.00540 \n", + " 8/1 1.02232 \n", + " 9/1 0.99782 \n", + " 10/1 1.00838 \n", + " 11/1 1.01803 \n", + " 12/1 1.02530 1.02167 +/- 0.00363\n", + " 13/1 1.00514 1.01616 +/- 0.00589\n", + " 14/1 0.98994 1.00960 +/- 0.00777\n", + " 15/1 1.01028 1.00974 +/- 0.00602\n", + " 16/1 1.04607 1.01580 +/- 0.00780\n", + " 17/1 1.03300 1.01825 +/- 0.00703\n", + " 18/1 1.03149 1.01991 +/- 0.00631\n", + " 19/1 0.98692 1.01624 +/- 0.00667\n", + " 20/1 1.05205 1.01982 +/- 0.00695\n", + " 21/1 1.01572 1.01945 +/- 0.00630\n", + " 22/1 1.02517 1.01993 +/- 0.00577\n", + " 23/1 1.00274 1.01861 +/- 0.00547\n", + " 24/1 1.04739 1.02066 +/- 0.00547\n", + " 25/1 1.01883 1.02054 +/- 0.00509\n", + " 26/1 1.02021 1.02052 +/- 0.00476\n", + " 27/1 1.04696 1.02207 +/- 0.00474\n", + " 28/1 1.02751 1.02238 +/- 0.00448\n", + " 29/1 1.09537 1.02622 +/- 0.00572\n", + " 30/1 1.03685 1.02675 +/- 0.00545\n", + " 31/1 0.99812 1.02539 +/- 0.00536\n", + " 32/1 1.02526 1.02538 +/- 0.00511\n", + " 33/1 1.05466 1.02665 +/- 0.00505\n", + " 34/1 1.04816 1.02755 +/- 0.00491\n", + " 35/1 1.00148 1.02651 +/- 0.00483\n", + " 36/1 1.02315 1.02638 +/- 0.00464\n", + " 37/1 1.05771 1.02754 +/- 0.00461\n", + " 38/1 1.01675 1.02715 +/- 0.00446\n", + " 39/1 1.03707 1.02749 +/- 0.00432\n", + " 40/1 1.01903 1.02721 +/- 0.00418\n", + " 41/1 1.00332 1.02644 +/- 0.00412\n", + " 42/1 1.02533 1.02641 +/- 0.00399\n", + " 43/1 0.98531 1.02516 +/- 0.00406\n", + " 44/1 1.00406 1.02454 +/- 0.00399\n", + " 45/1 1.01057 1.02414 +/- 0.00389\n", + " 46/1 1.02755 1.02424 +/- 0.00378\n", + " 47/1 1.02783 1.02433 +/- 0.00368\n", + " 48/1 1.00003 1.02369 +/- 0.00364\n", + " 49/1 1.00442 1.02320 +/- 0.00358\n", + " 50/1 1.03215 1.02342 +/- 0.00350\n", + " 51/1 1.01672 1.02326 +/- 0.00341\n", + " 52/1 1.03702 1.02359 +/- 0.00335\n", + " 53/1 1.02063 1.02352 +/- 0.00327\n", + " 54/1 1.04596 1.02403 +/- 0.00323\n", + " 55/1 1.01926 1.02392 +/- 0.00316\n", + " 56/1 1.03058 1.02407 +/- 0.00310\n", + " 57/1 1.06126 1.02486 +/- 0.00313\n", + " 58/1 1.06411 1.02568 +/- 0.00317\n", + " 59/1 1.03278 1.02582 +/- 0.00311\n", + " 60/1 1.04472 1.02620 +/- 0.00307\n", + " 61/1 1.00186 1.02572 +/- 0.00305\n", + " 62/1 1.01133 1.02545 +/- 0.00300\n", + " 63/1 1.03713 1.02567 +/- 0.00295\n", + " 64/1 1.01363 1.02544 +/- 0.00291\n", + " 65/1 0.98126 1.02464 +/- 0.00296\n", + " 66/1 1.01500 1.02447 +/- 0.00292\n", + " 67/1 1.02437 1.02447 +/- 0.00286\n", + " 68/1 1.05057 1.02492 +/- 0.00285\n", + " 69/1 1.04903 1.02533 +/- 0.00283\n", + " 70/1 1.02199 1.02527 +/- 0.00278\n", + " 71/1 1.00536 1.02494 +/- 0.00276\n", + " 72/1 1.01658 1.02481 +/- 0.00272\n", + " 73/1 1.00866 1.02455 +/- 0.00268\n", + " 74/1 1.01800 1.02445 +/- 0.00264\n", + " 75/1 0.99176 1.02395 +/- 0.00265\n", + " 76/1 1.03336 1.02409 +/- 0.00262\n", + " 77/1 1.02699 1.02413 +/- 0.00258\n", + " 78/1 1.01596 1.02401 +/- 0.00254\n", + " 79/1 1.02292 1.02400 +/- 0.00250\n", + " 80/1 1.04804 1.02434 +/- 0.00249\n", + " 81/1 0.99494 1.02393 +/- 0.00249\n", + " 82/1 1.02646 1.02396 +/- 0.00246\n", + " 83/1 1.01223 1.02380 +/- 0.00243\n", + " 84/1 1.02572 1.02383 +/- 0.00239\n", + " 85/1 1.02709 1.02387 +/- 0.00236\n", + " 86/1 1.00315 1.02360 +/- 0.00235\n", + " 87/1 1.01809 1.02353 +/- 0.00232\n", + " 88/1 1.01566 1.02342 +/- 0.00229\n", + " 89/1 1.01093 1.02327 +/- 0.00227\n", + " 90/1 1.02812 1.02333 +/- 0.00224\n", + " 91/1 1.02288 1.02332 +/- 0.00221\n", + " 92/1 1.04070 1.02353 +/- 0.00219\n", + " 93/1 1.03697 1.02370 +/- 0.00217\n", + " 94/1 1.03486 1.02383 +/- 0.00215\n", + " 95/1 1.06359 1.02430 +/- 0.00218\n", + " 96/1 1.04811 1.02457 +/- 0.00217\n", + " 97/1 1.01303 1.02444 +/- 0.00215\n", + " 98/1 1.01243 1.02430 +/- 0.00213\n", + " 99/1 1.03238 1.02439 +/- 0.00211\n", + " 100/1 1.02054 1.02435 +/- 0.00208\n", + " 101/1 1.00402 1.02413 +/- 0.00207\n", + " 102/1 1.03800 1.02428 +/- 0.00206\n", + " 103/1 1.02541 1.02429 +/- 0.00203\n", + " 104/1 1.06867 1.02476 +/- 0.00207\n", + " 105/1 1.03192 1.02484 +/- 0.00205\n", + " 106/1 1.00100 1.02459 +/- 0.00204\n", + " 107/1 1.01098 1.02445 +/- 0.00202\n", + " 108/1 1.02930 1.02450 +/- 0.00200\n", + " 109/1 1.02173 1.02447 +/- 0.00198\n", + " 110/1 1.01411 1.02437 +/- 0.00197\n", + " 111/1 1.03920 1.02452 +/- 0.00195\n", + " 112/1 1.01984 1.02447 +/- 0.00193\n", + " 113/1 1.03912 1.02461 +/- 0.00192\n", + " 114/1 1.04124 1.02477 +/- 0.00191\n", + " 115/1 1.04802 1.02499 +/- 0.00190\n", + " 116/1 1.04129 1.02515 +/- 0.00189\n", + " 117/1 1.03072 1.02520 +/- 0.00187\n", + " 118/1 1.05167 1.02544 +/- 0.00187\n", + " 119/1 0.99954 1.02521 +/- 0.00187\n", + " 120/1 1.00093 1.02499 +/- 0.00187\n", + " 121/1 1.04929 1.02520 +/- 0.00186\n", + " 122/1 1.04556 1.02539 +/- 0.00185\n", + " 123/1 1.03298 1.02545 +/- 0.00184\n", + " 124/1 1.01603 1.02537 +/- 0.00182\n", + " 125/1 1.03522 1.02546 +/- 0.00181\n", + " 126/1 1.05644 1.02572 +/- 0.00181\n", + " 127/1 1.03754 1.02582 +/- 0.00180\n", + " 128/1 1.01524 1.02573 +/- 0.00179\n", + " 129/1 1.01263 1.02562 +/- 0.00178\n", + " 130/1 0.99835 1.02540 +/- 0.00178\n", + " 131/1 1.01268 1.02529 +/- 0.00177\n", + " 132/1 1.03975 1.02541 +/- 0.00175\n", + " 133/1 1.00702 1.02526 +/- 0.00175\n", + " 134/1 1.02335 1.02525 +/- 0.00173\n", + " 135/1 1.04378 1.02539 +/- 0.00173\n", + " 136/1 1.04610 1.02556 +/- 0.00172\n", + " 137/1 1.02284 1.02554 +/- 0.00171\n", + " 138/1 1.05720 1.02578 +/- 0.00171\n", + " 139/1 1.00965 1.02566 +/- 0.00170\n", + " 140/1 1.03719 1.02575 +/- 0.00169\n", + " 141/1 1.02413 1.02574 +/- 0.00168\n", + " 142/1 1.03125 1.02578 +/- 0.00167\n", + " 143/1 1.03641 1.02586 +/- 0.00166\n", + " 144/1 1.02137 1.02582 +/- 0.00164\n", + " 145/1 1.01522 1.02575 +/- 0.00163\n", + " 146/1 1.05163 1.02594 +/- 0.00163\n", + " 147/1 1.03612 1.02601 +/- 0.00162\n", + " 148/1 1.03346 1.02606 +/- 0.00161\n", + " 149/1 1.02306 1.02604 +/- 0.00160\n", + " 150/1 1.01764 1.02598 +/- 0.00159\n", + " 151/1 1.01787 1.02592 +/- 0.00158\n", + " 152/1 1.03263 1.02597 +/- 0.00157\n", + " 153/1 1.01877 1.02592 +/- 0.00156\n", + " 154/1 1.02870 1.02594 +/- 0.00155\n", + " 155/1 1.03071 1.02597 +/- 0.00154\n", + " 156/1 1.04229 1.02609 +/- 0.00153\n", + " 157/1 1.03973 1.02618 +/- 0.00152\n", + " 158/1 1.02180 1.02615 +/- 0.00151\n", + " 159/1 1.01067 1.02604 +/- 0.00151\n", + " 160/1 1.02888 1.02606 +/- 0.00150\n", + " 161/1 1.01711 1.02600 +/- 0.00149\n", + " 162/1 1.01087 1.02590 +/- 0.00148\n", + " 163/1 1.01886 1.02586 +/- 0.00147\n", + " 164/1 1.02210 1.02583 +/- 0.00146\n", + " 165/1 1.04020 1.02593 +/- 0.00146\n", + " 166/1 1.03658 1.02600 +/- 0.00145\n", + " 167/1 1.03222 1.02603 +/- 0.00144\n", + " 168/1 1.03247 1.02608 +/- 0.00143\n", + " 169/1 0.99739 1.02590 +/- 0.00143\n", + " 170/1 1.02464 1.02589 +/- 0.00142\n", + " 171/1 1.04623 1.02601 +/- 0.00142\n", + " 172/1 1.04328 1.02612 +/- 0.00142\n", + " 173/1 1.00812 1.02601 +/- 0.00141\n", + " 174/1 1.01224 1.02593 +/- 0.00141\n", + " 175/1 1.00882 1.02582 +/- 0.00140\n", + " 176/1 1.01286 1.02574 +/- 0.00140\n", + " 177/1 1.02048 1.02571 +/- 0.00139\n", + " 178/1 1.04269 1.02581 +/- 0.00138\n", + " 179/1 1.05862 1.02601 +/- 0.00139\n", + " 180/1 1.02924 1.02603 +/- 0.00138\n", + " 181/1 1.01491 1.02596 +/- 0.00137\n", + " 182/1 1.04255 1.02606 +/- 0.00137\n", + " 183/1 0.99191 1.02586 +/- 0.00137\n", + " 184/1 1.00392 1.02573 +/- 0.00137\n", + " 185/1 1.02982 1.02576 +/- 0.00137\n", + " 186/1 1.02682 1.02576 +/- 0.00136\n", + " 187/1 1.01484 1.02570 +/- 0.00135\n", + " 188/1 1.02825 1.02572 +/- 0.00134\n", + " 189/1 0.98954 1.02551 +/- 0.00135\n", + " 190/1 1.00522 1.02540 +/- 0.00135\n", + " 191/1 1.03762 1.02547 +/- 0.00134\n", + " 192/1 1.02091 1.02544 +/- 0.00134\n", + " 193/1 1.04549 1.02555 +/- 0.00133\n", + " 194/1 1.05531 1.02572 +/- 0.00134\n", + " 195/1 1.01479 1.02566 +/- 0.00133\n", + " 196/1 1.01337 1.02559 +/- 0.00132\n", + " 197/1 0.99187 1.02541 +/- 0.00133\n", + " 198/1 1.01280 1.02534 +/- 0.00132\n", + " 199/1 1.00049 1.02521 +/- 0.00132\n", + " 200/1 1.01879 1.02518 +/- 0.00132\n", + " Creating state point statepoint.200.h5...\n", + "\n", + " ===========================================================================\n", + " ======================> SIMULATION FINISHED <======================\n", + " ===========================================================================\n", + "\n", + "\n", + " =======================> TIMING STATISTICS <=======================\n", + "\n", + " Total time for initialization = 6.3000E-02 seconds\n", + " Reading cross sections = 5.0000E-03 seconds\n", + " Total time in simulation = 7.3280E+01 seconds\n", + " Time in transport only = 7.3104E+01 seconds\n", + " Time in inactive batches = 1.1200E+00 seconds\n", + " Time in active batches = 7.2160E+01 seconds\n", + " Time synchronizing fission bank = 2.5000E-02 seconds\n", + " Sampling source sites = 1.8000E-02 seconds\n", + " SEND/RECV source sites = 7.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", + " Total time for finalization = 0.0000E+00 seconds\n", + " Total time elapsed = 7.3353E+01 seconds\n", + " Calculation Rate (inactive) = 44642.9 neutrons/second\n", + " Calculation Rate (active) = 13165.2 neutrons/second\n", + "\n", + " ============================> RESULTS <============================\n", + "\n", + " k-effective (Collision) = 1.02597 +/- 0.00117\n", + " k-effective (Track-length) = 1.02518 +/- 0.00132\n", + " k-effective (Absorption) = 1.02581 +/- 0.00070\n", + " Combined k-effective = 1.02562 +/- 0.00068\n", + " Leakage Fraction = 0.00000 +/- 0.00000\n", + "\n" + ] + }, + { + "data": { + "text/plain": [ + "0" + ] + }, + "execution_count": 37, + "metadata": {}, + "output_type": "execute_result" + } + ], + "source": [ + "# Close the StatePoint File\n", + "sp._f.close()\n", + "\n", + "# Run the Multi-Group OpenMC Simulation\n", + "openmc.run()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "# Results Comparison\n", + "Now we can compare the multi-group and continuous-energy results.\n", + "\n", + "We will begin by loading the multi-group statepoint file we just finished writing and extracting the calculated keff." + ] + }, + { + "cell_type": "code", + "execution_count": 38, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Load the last statepoint file and keff value\n", + "mgsp = openmc.StatePoint('statepoint.' + str(batches) + '.h5')\n", + "mgsu = openmc.Summary('summary.h5')\n", + "mgsp.link_with_summary(mgsu)\n", + "mg_keff = mgsp.k_combined" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Lets compare the two eigenvalues, including their bias" + ] + }, + { + "cell_type": "code", + "execution_count": 39, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "Continuous-Energy keff = 1.025440\n", + "Multi-Group keff = 1.025621\n", + "bias [pcm]: -18.1\n" + ] + } + ], + "source": [ + "bias = 1.0E5 * (ce_keff[0] - mg_keff[0])\n", + "\n", + "print('Continuous-Energy keff = {0:1.6f}'.format(ce_keff[0]))\n", + "print('Multi-Group keff = {0:1.6f}'.format(mg_keff[0]))\n", + "print('bias [pcm]: {0:1.1f}'.format(bias))" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "We see quite good agreement with only an 18pcm difference between the two." + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "# Flux and Pin Power Visualizations" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next we will visualize the mesh tally results obtained from both the Continuous-Energy and Multi-Group OpenMC calculations.\n", + "\n", + "First, we extract volume-integrated fission rates from the Multi-Group calculation's mesh fission rate tally for each pin cell in the fuel assembly." + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now we can do the same for the Multi-Group results." + ] + }, + { + "cell_type": "code", + "execution_count": 40, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Get the OpenMC fission rate mesh tally data\n", + "mg_mesh_tally = mgsp.get_tally(name='mesh tally')\n", + "mgopenmc_fission_rates = mg_mesh_tally.get_values(scores=['fission'])\n", + "\n", + "# Reshape array to 2D for plotting\n", + "mgopenmc_fission_rates.shape = (17,17)\n", + "\n", + "# Normalize to the average pin power\n", + "mgopenmc_fission_rates /= np.mean(mgopenmc_fission_rates)" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now we can easily use Matplotlib to visualize the two fission rates side-by-side." + ] + }, + { + "cell_type": "code", + "execution_count": 41, + "metadata": { + "collapsed": false + }, + "outputs": [ + { + "data": { + "text/plain": [ + "" + ] + }, + "execution_count": 41, + "metadata": {}, + "output_type": "execute_result" + }, + { + "data": { + "image/png": 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EpCSU0EVESuL/ASY96jLsHTMbAAAAAElFTkSuQmCC\n", + "text/plain": [ + "" + ] + }, + "metadata": {}, + "output_type": "display_data" + } + ], + "source": [ + "# Plot the CE fission rates in the left subplot\n", + "fig = plt.subplot(121)\n", + "plt.imshow(openmc_fission_rates, interpolation='none', cmap='jet')\n", + "plt.title('Continuous-Energy Fission Rates')\n", + "\n", + "# Plot the MG fission rates in the right subplot\n", + "fig2 = plt.subplot(122)\n", + "plt.imshow(mgopenmc_fission_rates, interpolation='none', cmap='jet')\n", + "plt.title('Multi-Group Fission Rates')\n" + ] + }, + { + "cell_type": "markdown", + "metadata": { + "collapsed": true + }, + "source": [ + "We also see very good agreement between the fission rate distributions." + ] + } + ], + "metadata": { + "kernelspec": { + "display_name": "Python 3", + "language": "python", + "name": "python3" + }, + "language_info": { + "codemirror_mode": { + "name": "ipython", + "version": 3 + }, + "file_extension": ".py", + "mimetype": "text/x-python", + "name": "python", + "nbconvert_exporter": "python", + "pygments_lexer": "ipython3", + "version": "3.5.1" + } + }, + "nbformat": 4, + "nbformat_minor": 0 +} diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.rst b/docs/source/pythonapi/examples/mgxs-part-iv.rst new file mode 100644 index 000000000..e24325521 --- /dev/null +++ b/docs/source/pythonapi/examples/mgxs-part-iv.rst @@ -0,0 +1,13 @@ +.. _notebook_mgxs_part_iv: + +==================================================== +MGXS Part IV: Multi-Group Mode Cross-Section Library +==================================================== + +.. only:: html + + .. notebook:: mgxs-part-iv.ipynb + +.. only:: latex + + IPython notebooks must be viewed in the online HTML documentation. diff --git a/docs/source/pythonapi/index.rst b/docs/source/pythonapi/index.rst index 1631976e6..3c4899cd2 100644 --- a/docs/source/pythonapi/index.rst +++ b/docs/source/pythonapi/index.rst @@ -26,6 +26,7 @@ Example Jupyter Notebooks examples/mgxs-part-i examples/mgxs-part-ii examples/mgxs-part-iii + examples/mgxs-part-iv ------------------------------------ :mod:`openmc` -- Basic Functionality diff --git a/openmc/summary.py b/openmc/summary.py index f33397d72..af164a12c 100644 --- a/openmc/summary.py +++ b/openmc/summary.py @@ -41,6 +41,7 @@ class Summary(object): self._read_nuclides() self._read_geometry() self._read_tallies() + self._f.close() @property def openmc_geometry(self): From 187d332dc38e41814f75b3c87024a5524b38e5b3 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 7 May 2016 14:40:57 -0400 Subject: [PATCH 083/147] Changed OPENMC_MG_MGXS_TYPES to use transport instead of total --- openmc/mgxs/library.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 34221f707..d74c8ced3 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -17,7 +17,7 @@ if sys.version_info[0] >= 3: # The following represent the most accurate MGXS generation strategy # for use in the MG mode of OpenMC. -OPENMC_MG_MGXS_TYPES = ['total', 'absorption', 'nu-fission', 'chi', +OPENMC_MG_MGXS_TYPES = ['transport', 'absorption', 'nu-fission', 'chi', 'scatter matrix', 'nu-scatter matrix'] From cf45388d6e0e207e814a378708189e0b19778780 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Sat, 7 May 2016 15:38:59 -0400 Subject: [PATCH 084/147] Fix universe assignment for openmc.HexLattice --- openmc/lattice.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/lattice.py b/openmc/lattice.py index f1e775920..f78ec8e90 100644 --- a/openmc/lattice.py +++ b/openmc/lattice.py @@ -649,7 +649,7 @@ class HexLattice(Lattice): # Set the number of rings and make sure this number is consistent for # all axial positions. if n_dims == 3: - self.num_rings = len(self._universes) + self.num_rings = len(self._universes[0]) for rings in self._universes: if len(rings) != self._num_rings: msg = 'HexLattice ID={0:d} has an inconsistent number of ' \ From 08995f74e2ad9f4a8954c92b110e4d07e85e440d Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 8 May 2016 11:40:29 -0400 Subject: [PATCH 085/147] Fixed issues with indentation for distribcell paths per comments by @paulromano --- openmc/filter.py | 16 ++++++++-------- openmc/mgxs/mgxs.py | 8 +++++--- openmc/tallies.py | 10 ---------- 3 files changed, 13 insertions(+), 21 deletions(-) diff --git a/openmc/filter.py b/openmc/filter.py index ff21f4e93..01f2ad201 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -516,7 +516,7 @@ class Filter(object): return filter_bin - def get_pandas_dataframe(self, data_size, distribcell_paths=False): + def get_pandas_dataframe(self, data_size, distribcell_paths=True): """Builds a Pandas DataFrame for the Filter's bins. This method constructs a Pandas DataFrame object for the filter with @@ -531,13 +531,13 @@ class Filter(object): ---------- data_size : Integral The total number of bins in the tally corresponding to this filter - distribcell_paths : bool - Construct columns for distribcell tally filters. The geometric - information in the Summary object is embedded into a Multi-index - column with a geometric "path" to each distribcell instance. - NOTE: This option assumes that all distribcell paths are of the same - length and do not have the same universes and cells but different - lattice cell indices. + distribcell_paths : bool, optional + Construct columns for distribcell tally filters (default is True). + The geometric information in the Summary object is embedded into a + Multi-index column with a geometric "path" to each distribcell + instance. NOTE: This option assumes that all distribcell paths are + of the same length and do not have the same universes and cells but + different lattice cell indices. Returns ------- diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index d7ba0117d..504ee51db 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1366,9 +1366,11 @@ class MGXS(object): xs_type: {'macro', 'micro'} Return macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - distribcell_paths : list of str - The paths traversed through the CSG tree to reach each distribcell - instance (for 'distribcell' filters only) + distribcell_paths : bool, optional + Construct columns for distribcell tally filters (default is True). + The geometric information in the Summary object is embedded into + a Multi-index column with a geometric "path" to each distribcell + instance. Returns ------- diff --git a/openmc/tallies.py b/openmc/tallies.py index 2cac33404..bea5bc3ff 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -1586,16 +1586,6 @@ class Tally(object): msg = 'The Tally ID="{0}" has no data to return'.format(self.id) raise KeyError(msg) - ''' - # If using Summary, ensure StatePoint.link_with_summary(...) was called - if distribcell_pathssummary and not self.with_summary: - msg = 'The Tally ID="{0}" has not been linked with the Summary. ' \ - 'Call the StatePoint.link_with_summary(...) method ' \ - 'before using Tally.get_pandas_dataframe(...) with ' \ - 'Summary info'.format(self.id) - raise KeyError(msg) - ''' - # Initialize a pandas dataframe for the tally data import pandas as pd df = pd.DataFrame() From 417b9a86a684f471ea938c083fddb21b7ce0a24a Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 8 May 2016 11:43:48 -0400 Subject: [PATCH 086/147] Made distribcell paths default to True for MGXS Pandas DataFrames --- openmc/mgxs/mgxs.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 504ee51db..a5c56034e 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1346,7 +1346,7 @@ class MGXS(object): modified.write('\n\\end{document}') def get_pandas_dataframe(self, groups='all', nuclides='all', - xs_type='macro', distribcell_paths=False): + xs_type='macro', distribcell_paths=True): """Build a Pandas DataFrame for the MGXS data. This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but From b01c0281cec94c1ee1e397617f8a42a36eb2dde7 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 8 May 2016 11:50:09 -0400 Subject: [PATCH 087/147] Fixed issue with dropping scores from MGXS Pandas DF with multi-indexed distribcell paths --- openmc/mgxs/mgxs.py | 5 +---- 1 file changed, 1 insertion(+), 4 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index a5c56034e..99a3d8bfe 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1415,10 +1415,7 @@ class MGXS(object): distribcell_paths=distribcell_paths) # Remove the score column since it is homogeneous and redundant - if distribcell_paths and 'distribcell' in self.domain_type: - df = df.drop('score', level=0, axis=1) - else: - df = df.drop('score', axis=1) + df = df.drop('score', axis=1) # Override energy groups bounds with indices all_groups = np.arange(self.num_groups, 0, -1, dtype=np.int) From 2ca61564e2c7fb5b514661f1ce00e0630725606a Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 8 May 2016 13:01:05 -0400 Subject: [PATCH 088/147] Made distribcell paths default to True for Tally Pandas DF --- .../examples/pandas-dataframes.ipynb | 283 +++--------------- openmc/tallies.py | 11 +- 2 files changed, 47 insertions(+), 247 deletions(-) diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index 87eb50f7b..50d66292c 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -370,7 +370,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -554,8 +554,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: cc27630f7db25b148efab11d182c6c7b34e40a5b\n", - " Date/Time: 2016-05-01 13:49:06\n", + " Git SHA1: 9bff2ab4747873a542a27cd7cfdf7341c23a4405\n", + " Date/Time: 2016-05-08 12:58:17\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -619,20 +619,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.9900E-01 seconds\n", - " Reading cross sections = 9.0000E-02 seconds\n", - " Total time in simulation = 4.8580E+00 seconds\n", - " Time in transport only = 4.8080E+00 seconds\n", - " Time in inactive batches = 7.9400E-01 seconds\n", - " Time in active batches = 4.0640E+00 seconds\n", - " Time synchronizing fission bank = 0.0000E+00 seconds\n", - " Sampling source sites = 0.0000E+00 seconds\n", + " Total time for initialization = 3.8600E-01 seconds\n", + " Reading cross sections = 9.1000E-02 seconds\n", + " Total time in simulation = 4.3500E+00 seconds\n", + " Time in transport only = 4.3200E+00 seconds\n", + " Time in inactive batches = 6.6700E-01 seconds\n", + " Time in active batches = 3.6830E+00 seconds\n", + " Time synchronizing fission bank = 2.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", " SEND/RECV source sites = 0.0000E+00 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 5.2710E+00 seconds\n", - " Calculation Rate (inactive) = 15743.1 neutrons/second\n", - " Calculation Rate (active) = 9227.36 neutrons/second\n", + " Total time elapsed = 4.7500E+00 seconds\n", + " Calculation Rate (inactive) = 18740.6 neutrons/second\n", + " Calculation Rate (active) = 10181.9 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1111,7 +1111,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1514,7 +1514,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Print the distribcell tally dataframe **without** distribcell paths" + "Print the distribcell tally dataframe with distribcell paths" ] }, { @@ -1523,216 +1523,6 @@ "metadata": { "collapsed": false }, - "outputs": [ - { - "data": { - "text/html": [ - "
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distribcellscoremeanstd. dev.
558279absorption8.19e-057.82e-06
559279scatter1.33e-026.19e-04
560280absorption1.00e-047.93e-06
561280scatter1.40e-025.61e-04
562281absorption9.52e-057.08e-06
563281scatter1.51e-026.50e-04
564282absorption9.85e-059.47e-06
565282scatter1.53e-024.63e-04
566283absorption1.08e-041.34e-05
567283scatter1.65e-027.04e-04
568284absorption1.13e-047.91e-06
569284scatter1.67e-025.51e-04
570285absorption1.23e-049.53e-06
571285scatter1.88e-027.25e-04
572286absorption1.44e-041.34e-05
573286scatter1.90e-027.07e-04
574287absorption1.26e-048.66e-06
575287scatter1.97e-027.23e-04
576288absorption1.25e-049.59e-06
577288scatter2.01e-026.75e-04
\n", - "
" - ], - "text/plain": [ - " distribcell score mean std. dev.\n", - "558 279 absorption 8.19e-05 7.82e-06\n", - "559 279 scatter 1.33e-02 6.19e-04\n", - "560 280 absorption 1.00e-04 7.93e-06\n", - "561 280 scatter 1.40e-02 5.61e-04\n", - "562 281 absorption 9.52e-05 7.08e-06\n", - "563 281 scatter 1.51e-02 6.50e-04\n", - "564 282 absorption 9.85e-05 9.47e-06\n", - "565 282 scatter 1.53e-02 4.63e-04\n", - "566 283 absorption 1.08e-04 1.34e-05\n", - "567 283 scatter 1.65e-02 7.04e-04\n", - "568 284 absorption 1.13e-04 7.91e-06\n", - "569 284 scatter 1.67e-02 5.51e-04\n", - "570 285 absorption 1.23e-04 9.53e-06\n", - "571 285 scatter 1.88e-02 7.25e-04\n", - "572 286 absorption 1.44e-04 1.34e-05\n", - "573 286 scatter 1.90e-02 7.07e-04\n", - "574 287 absorption 1.26e-04 8.66e-06\n", - "575 287 scatter 1.97e-02 7.23e-04\n", - "576 288 absorption 1.25e-04 9.59e-06\n", - "577 288 scatter 2.01e-02 6.75e-04" - ] - }, - "execution_count": 33, - "metadata": {}, - "output_type": "execute_result" - } - ], - "source": [ - "# Get a pandas dataframe for the distribcell tally data\n", - "df = tally.get_pandas_dataframe(nuclides=False)\n", - "\n", - "# Print the last twenty rows in the dataframe\n", - "df.tail(20)" - ] - }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "Print the distribcell tally dataframe **with** distribcell paths" - ] - }, - { - "cell_type": "code", - "execution_count": 34, - "metadata": { - "collapsed": false - }, "outputs": [ { "data": { @@ -2133,14 +1923,14 @@ "577 2.01e-02 6.75e-04 " ] }, - "execution_count": 34, + "execution_count": 33, "metadata": {}, "output_type": "execute_result" } ], "source": [ "# Get a pandas dataframe for the distribcell tally data\n", - "df = tally.get_pandas_dataframe(nuclides=False, distribcell_paths=True)\n", + "df = tally.get_pandas_dataframe(nuclides=False)\n", "\n", "# Print the last twenty rows in the dataframe\n", "df.tail(20)" @@ -2148,7 +1938,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { "collapsed": false }, @@ -2234,7 +2024,7 @@ "max 9.19e-04 4.95e-05" ] }, - "execution_count": 35, + "execution_count": 34, "metadata": {}, "output_type": "execute_result" } @@ -2257,7 +2047,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -2295,7 +2085,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -2331,7 +2121,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 37, "metadata": { "collapsed": false }, @@ -2350,10 +2140,10 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 38, + "execution_count": 37, "metadata": {}, "output_type": "execute_result" }, @@ -2361,7 +2151,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2380,7 +2170,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -2388,10 +2178,10 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 39, + "execution_count": 38, "metadata": {}, "output_type": "execute_result" }, @@ -2399,7 +2189,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2414,6 +2204,15 @@ "pylab.xlabel('Mean')\n", "pylab.legend(['KDE', 'Histogram'])" ] + }, + { + "cell_type": "code", + "execution_count": null, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [] } ], "metadata": { diff --git a/openmc/tallies.py b/openmc/tallies.py index bea5bc3ff..96323763a 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -1539,7 +1539,7 @@ class Tally(object): return data def get_pandas_dataframe(self, filters=True, nuclides=True, scores=True, - distribcell_paths=False, float_format='{:.2e}'): + distribcell_paths=True, float_format='{:.2e}'): """Build a Pandas DataFrame for the Tally data. This method constructs a Pandas DataFrame object for the Tally data @@ -1557,10 +1557,11 @@ class Tally(object): Include columns with nuclide bin information (default is True). scores : bool Include columns with score bin information (default is True). - distribcell_paths : bool - Construct columns for distribcell tally filters. The geometric - information in the Summary object is embedded into a Multi-index - column with a geometric "path" to each distribcell instance. + distribcell_paths : bool, optional + Construct columns for distribcell tally filters (default is True). + The geometric information in the Summary object is embedded into a + Multi-index column with a geometric "path" to each distribcell + instance. float_format : str All floats in the DataFrame will be formatted using the given format string before printing. From b390a2a53647f1775d1cf68cd2ef2500b528d72e Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 8 May 2016 13:17:43 -0400 Subject: [PATCH 089/147] Resolved comma comments from @paulromano as well as some additional instances I found. --- src/math.F90 | 27 -- src/mgxs_data.F90 | 6 +- src/mgxs_header.F90 | 530 ++++++++++++++++++++++------------------ src/nuclide_header.F90 | 2 +- src/particle_header.F90 | 2 +- src/tally.F90 | 80 +++--- 6 files changed, 337 insertions(+), 310 deletions(-) diff --git a/src/math.F90 b/src/math.F90 index f49220da7..c7ede8d2a 100644 --- a/src/math.F90 +++ b/src/math.F90 @@ -702,31 +702,4 @@ contains end function watt_spectrum - -!=============================================================================== -! find_angle finds the closest angle on the data grid and returns that index -!=============================================================================== - - pure subroutine find_angle(polar, azimuthal, uvw, i_azi, i_pol) - real(8), intent(in) :: polar(:) ! Polar angles [0,pi] - real(8), intent(in) :: azimuthal(:) ! Azi. angles [-pi,pi] - real(8), intent(in) :: uvw(3) ! Direction of motion - integer, intent(inout) :: i_pol ! Closest polar bin - integer, intent(inout) :: i_azi ! Closest azi bin - - real(8) :: my_pol, my_azi, dangle - - ! Convert uvw to polar and azi - - my_pol = acos(uvw(3)) - my_azi = atan2(uvw(2), uvw(1)) - - ! Search for equi-binned angles - dangle = PI / real(size(polar),8) - i_pol = floor(my_pol / dangle + ONE) - dangle = TWO * PI / real(size(azimuthal),8) - i_azi = floor((my_azi + PI) / dangle + ONE) - - end subroutine find_angle - end module math diff --git a/src/mgxs_data.F90 b/src/mgxs_data.F90 index 6cf730cfa..38d6ebc6c 100644 --- a/src/mgxs_data.F90 +++ b/src/mgxs_data.F90 @@ -125,7 +125,7 @@ contains ! Now read in the data specific to the type we just declared call nuclides_MG(i_nuclide) % obj % init_file(node_xsdata, & - energy_groups,get_kfiss,get_fiss,max_order,i_listing) + energy_groups, get_kfiss, get_fiss, max_order, i_listing) ! Add name and alias to dictionary call already_read % add(name) @@ -184,8 +184,8 @@ contains type is (MgxsAngle) allocate(MgxsAngle :: macro_xs(i_mat) % obj) end select - call macro_xs(i_mat) % obj % combine(mat,nuclides_MG,energy_groups, & - max_order,scatt_type,i_mat) + call macro_xs(i_mat) % obj % combine(mat, nuclides_MG, energy_groups, & + max_order, scatt_type, i_mat) end do end subroutine create_macro_xs diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 7d4ee275d..725aacffa 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -6,7 +6,7 @@ module mgxs_header use list_header, only: ListInt use material_header, only: material use math, only: calc_pn, calc_rn, expand_harmonic, & - evaluate_legendre, find_angle + evaluate_legendre use nuclide_header, only: MaterialMacroXS use random_lcg, only: prn use scattdata_header @@ -150,7 +150,7 @@ module mgxs_header real(8), allocatable :: nu_fission(:) ! fission matrix (Gout x Gin) real(8), allocatable :: k_fission(:) ! kappa-fission real(8), allocatable :: fission(:) ! neutron production - real(8), allocatable :: chi(:,:) ! Fission Spectra + real(8), allocatable :: chi(:, :) ! Fission Spectra contains procedure :: init_file => mgxsiso_init_file ! Initialize Nuclidic MGXS Data @@ -170,13 +170,13 @@ module mgxs_header type, extends(Mgxs) :: MgxsAngle ! Microscopic cross sections - real(8), allocatable :: total(:,:,:) ! total cross section - real(8), allocatable :: absorption(:,:,:) ! absorption cross section - type(ScattDataContainer), allocatable :: scatter(:,:) ! scattering information - real(8), allocatable :: nu_fission(:,:,:) ! fission matrix (Gout x Gin) - real(8), allocatable :: k_fission(:,:,:) ! kappa-fission - real(8), allocatable :: fission(:,:,:) ! neutron production - real(8), allocatable :: chi(:,:,:,:) ! Fission Spectra + real(8), allocatable :: total(:, :, :) ! total cross section + real(8), allocatable :: absorption(:, :, :) ! absorption cross section + type(ScattDataContainer), allocatable :: scatter(:, :) ! scattering information + real(8), allocatable :: nu_fission(:, :, :) ! fission matrix (Gout x Gin) + real(8), allocatable :: k_fission(:, :, :) ! kappa-fission + real(8), allocatable :: fission(:, :, :) ! neutron production + real(8), allocatable :: chi(:, :, :, :) ! Fission Spectra ! In all cases, right-most indices are theta, phi integer :: n_pol ! Number of polar angles integer :: n_azi ! Number of azimuthal angles @@ -272,11 +272,11 @@ module mgxs_header type(Node), pointer :: node_legendre_mu character(MAX_LINE_LEN) :: temp_str logical :: enable_leg_mu - real(8), allocatable :: temp_arr(:), temp_2d(:,:) - real(8), allocatable :: temp_mult(:,:) - real(8), allocatable :: scatt_coeffs(:,:,:) - real(8), allocatable :: input_scatt(:,:,:) - real(8), allocatable :: temp_scatt(:,:,:) + real(8), allocatable :: temp_arr(:), temp_2d(:, :) + real(8), allocatable :: temp_mult(:, :) + real(8), allocatable :: scatt_coeffs(:, :, :) + real(8), allocatable :: input_scatt(:, :, :) + real(8), allocatable :: temp_scatt(:, :, :) real(8) :: dmu, mu, norm integer :: order, order_dim, gin, gout, l, arr_len integer :: legendre_mu_points, imu @@ -288,24 +288,24 @@ module mgxs_header allocate(this % nu_fission(groups)) allocate(this % chi(groups,groups)) if (this % fissionable) then - if (check_for_node(node_xsdata,"chi")) then + if (check_for_node(node_xsdata, "chi")) then ! Chi was provided, that means they are giving chi and nu-fission ! vectors ! Get chi allocate(temp_arr(1 * groups)) - call get_node_array(node_xsdata,"chi",temp_arr) + call get_node_array(node_xsdata, "chi", temp_arr) do gin = 1, groups do gout = 1, groups - this % chi(gout,gin) = temp_arr(gout) + this % chi(gout, gin) = temp_arr(gout) end do ! Normalize chi so its CDF goes to 1 - this % chi(:,gin) = this % chi(:,gin) / sum(this % chi(:,gin)) + this % chi(:, gin) = this % chi(:, gin) / sum(this % chi(:, gin)) end do deallocate(temp_arr) ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata,"nu_fission")) then - call get_node_array(node_xsdata,"nu_fission",this % nu_fission) + if (check_for_node(node_xsdata, "nu_fission")) then + call get_node_array(node_xsdata, "nu_fission", this % nu_fission) else call fatal_error("If fissionable, must provide nu_fission!") end if @@ -313,11 +313,11 @@ module mgxs_header else ! chi isnt provided but is within nu_fission, existing as a matrix ! So, get nu_fission (as a matrix) - if (check_for_node(node_xsdata,"nu_fission")) then + if (check_for_node(node_xsdata, "nu_fission")) then allocate(temp_arr(groups*groups)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(temp_2d(groups,groups)) - temp_2d = reshape(temp_arr,(/groups,groups/)) + call get_node_array(node_xsdata, "nu_fission", temp_arr) + allocate(temp_2d(groups, groups)) + temp_2d = reshape(temp_arr, (/groups, groups/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -325,14 +325,14 @@ module mgxs_header ! Set the vector nu-fission from the matrix nu-fission do gin = 1, groups - this % nu_fission(gin) = sum(temp_2d(:,gin)) + this % nu_fission(gin) = sum(temp_2d(:, gin)) end do ! Now pull out information needed for chi this % chi = temp_2d ! Normalize chi so its CDF goes to 1 do gin = 1, groups - this % chi(:,gin) = this % chi(:,gin) / sum(this % chi(:,gin)) + this % chi(:, gin) = this % chi(:, gin) / sum(this % chi(:, gin)) end do deallocate(temp_2d) end if @@ -340,8 +340,8 @@ module mgxs_header ! (*Need is defined as will be using it to tally) if (get_fiss) then allocate(this % fission(groups)) - if (check_for_node(node_xsdata,"fission")) then - call get_node_array(node_xsdata,"fission",this % fission) + if (check_for_node(node_xsdata, "fission")) then + call get_node_array(node_xsdata, "fission", this % fission) else call fatal_error("Fission data missing, required due to fission& & tallies in tallies.xml file!") @@ -349,8 +349,8 @@ module mgxs_header end if if (get_kfiss) then allocate(this % k_fission(groups)) - if (check_for_node(node_xsdata,"kappa_fission")) then - call get_node_array(node_xsdata,"kappa_fission",this % k_fission) + if (check_for_node(node_xsdata, "kappa_fission")) then + call get_node_array(node_xsdata, "kappa_fission", this % k_fission) else call fatal_error("kappa_fission data missing, required due to & &kappa-fission tallies in tallies.xml file!") @@ -362,19 +362,19 @@ module mgxs_header end if allocate(this % absorption(groups)) - if (check_for_node(node_xsdata,"absorption")) then - call get_node_array(node_xsdata,"absorption",this % absorption) + if (check_for_node(node_xsdata, "absorption")) then + call get_node_array(node_xsdata, "absorption", this % absorption) else call fatal_error("Must provide absorption!") end if ! Get multiplication data if present allocate(temp_mult(groups, groups)) - if (check_for_node(node_xsdata,"multiplicity")) then - arr_len = get_arraysize_double(node_xsdata,"multiplicity") + if (check_for_node(node_xsdata, "multiplicity")) then + arr_len = get_arraysize_double(node_xsdata, "multiplicity") if (arr_len == groups * groups) then allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata,"multiplicity",temp_arr) + call get_node_array(node_xsdata, "multiplicity", temp_arr) temp_mult = reshape(temp_arr, (/groups, groups/)) deallocate(temp_arr) else @@ -392,24 +392,25 @@ module mgxs_header ! Set the default (leave as Legendre polynomials) enable_leg_mu = .false. - if (check_for_node(node_xsdata,"tabular_legendre")) then - call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) + if (check_for_node(node_xsdata, "tabular_legendre")) then + call get_node_ptr(node_xsdata, "tabular_legendre", node_legendre_mu) if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu,"enable",temp_str) + call get_node_value(node_legendre_mu, "enable", temp_str) temp_str = trim(to_lower(temp_str)) if (temp_str == 'true' .or. temp_str == '1') then enable_leg_mu = .true. elseif (temp_str == 'false' .or. temp_str == '0') then enable_leg_mu = .false. else - call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + call fatal_error("Unrecognized tabular_legendre/enable: " & + // temp_str) end if end if ! Ok, so if we need to convert to a tabular form, get the user provided ! number of points if (enable_leg_mu) then - if (check_for_node(node_legendre_mu,"num_points")) then - call get_node_value(node_legendre_mu,"num_points", & + if (check_for_node(node_legendre_mu, "num_points")) then + call get_node_value(node_legendre_mu, "num_points", & legendre_mu_points) if (legendre_mu_points <= 0) & call fatal_error("num_points element must be positive& @@ -422,8 +423,8 @@ module mgxs_header end if ! Get the library's value for the order - if (check_for_node(node_xsdata,"order")) then - call get_node_value(node_xsdata,"order",order) + if (check_for_node(node_xsdata, "order")) then + call get_node_value(node_xsdata, "order", order) else call fatal_error("Order Must Be Provided!") end if @@ -444,10 +445,10 @@ module mgxs_header ! but then need to convert it to a more useful ordering for processing ! (Order x Gout x Gin). allocate(input_scatt(groups, groups, order_dim)) - if (check_for_node(node_xsdata,"scatter")) then + if (check_for_node(node_xsdata, "scatter")) then allocate(temp_arr(groups * groups * order_dim)) - call get_node_array(node_xsdata,"scatter",temp_arr) - input_scatt = reshape(temp_arr,(/groups,groups,order_dim/)) + call get_node_array(node_xsdata, "scatter", temp_arr) + input_scatt = reshape(temp_arr, (/groups, groups, order_dim/)) deallocate(temp_arr) ! Compare the number of orders given with the maximum order of the @@ -456,8 +457,8 @@ module mgxs_header order = min(order_dim - 1, max_order) order_dim = order + 1 end if - allocate(temp_scatt(groups,groups,order_dim)) - temp_scatt(:,:,:) = input_scatt(:,:,1:order_dim) + allocate(temp_scatt(groups, groups, order_dim)) + temp_scatt(:, :, :) = input_scatt(:, :, 1:order_dim) ! Take input format (groups, groups, order) and convert to ! the more useful format needed for scattdata: (order, groups, groups) @@ -470,9 +471,9 @@ module mgxs_header this % scatt_type = ANGLE_TABULAR order_dim = legendre_mu_points order = order_dim - dmu = TWO / real(order - 1,8) + dmu = TWO / real(order - 1, 8) - allocate(scatt_coeffs(order_dim,groups,groups)) + allocate(scatt_coeffs(order_dim, groups, groups)) do gin = 1, groups do gout = 1, groups norm = ZERO @@ -482,35 +483,36 @@ module mgxs_header else if (imu == order_dim) then mu = ONE else - mu = -ONE + real(imu - 1,8) * dmu + mu = -ONE + real(imu - 1, 8) * dmu end if - scatt_coeffs(imu,gout,gin) = & - evaluate_legendre(temp_scatt(gout,gin,:),mu) + scatt_coeffs(imu, gout, gin) = & + evaluate_legendre(temp_scatt(gout, gin, :),mu) ! Ensure positivity of distribution - if (scatt_coeffs(imu,gout,gin) < ZERO) & - scatt_coeffs(imu,gout,gin) = ZERO + if (scatt_coeffs(imu, gout, gin) < ZERO) & + scatt_coeffs(imu, gout, gin) = ZERO ! And accrue the integral if (imu > 1) then - norm = norm + HALF * dmu * (scatt_coeffs(imu-1,gout,gin) + & - scatt_coeffs(imu,gout,gin)) + norm = norm + HALF * dmu * & + (scatt_coeffs(imu - 1, gout, gin) + & + scatt_coeffs(imu, gout, gin)) end if end do ! Now that we have the integral, lets ensure that the distribution ! is normalized such that it preserves the original scattering xs if (norm > ZERO) then - scatt_coeffs(:,gout,gin) = scatt_coeffs(:,gout,gin) * & - temp_scatt(gout,gin,1) / norm + scatt_coeffs(:, gout, gin) = scatt_coeffs(:, gout, gin) * & + temp_scatt(gout, gin, 1) / norm end if end do end do else ! Sticking with current representation, carry forward but change ! the array ordering - allocate(scatt_coeffs(order_dim,groups,groups)) + allocate(scatt_coeffs(order_dim, groups, groups)) do gin = 1, groups do gout = 1, groups do l = 1, order_dim - scatt_coeffs(l,gout,gin) = temp_scatt(gout,gin,l) + scatt_coeffs(l, gout, gin) = temp_scatt(gout, gin, l) end do end do end do @@ -541,8 +543,8 @@ module mgxs_header ! Get, or infer, total xs data. allocate(this % total(groups)) - if (check_for_node(node_xsdata,"total")) then - call get_node_array(node_xsdata,"total",this % total) + if (check_for_node(node_xsdata, "total")) then + call get_node_array(node_xsdata, "total", this % total) else this % total = this % absorption + this % scatter % scattxs end if @@ -572,11 +574,11 @@ module mgxs_header type(Node), pointer :: node_legendre_mu character(MAX_LINE_LEN) :: temp_str logical :: enable_leg_mu - real(8), allocatable :: temp_arr(:), temp_4d(:,:,:,:) - real(8), allocatable :: temp_mult(:,:,:,:) - real(8), allocatable :: scatt_coeffs(:,:,:,:,:) - real(8), allocatable :: input_scatt(:,:,:,:,:) - real(8), allocatable :: temp_scatt(:,:,:,:,:) + real(8), allocatable :: temp_arr(:), temp_4d(:, :, :, :) + real(8), allocatable :: temp_mult(:, :, :, :) + real(8), allocatable :: scatt_coeffs(:, :, :, :, :) + real(8), allocatable :: input_scatt(:, :, :, :, :) + real(8), allocatable :: temp_scatt(:, :, :, :, :) real(8) :: dmu, mu, norm, dangle integer :: order, order_dim, gin, gout, l, arr_len integer :: legendre_mu_points, imu, ipol, iazi @@ -604,9 +606,9 @@ module mgxs_header ! When this feature is supported, this line will be activated call get_node_array(node_xsdata, "polar", this % polar) else - dangle = PI / real(this % n_pol,8) + dangle = PI / real(this % n_pol, 8) do ipol = 1, this % n_pol - this % polar(ipol) = (real(ipol,8) - HALF) * dangle + this % polar(ipol) = (real(ipol, 8) - HALF) * dangle end do end if if (check_for_node(node_xsdata, "azimuthal")) then @@ -614,22 +616,22 @@ module mgxs_header ! When this feature is supported, this line will be activated call get_node_array(node_xsdata, "azimuthal", this % azimuthal) else - dangle = TWO * PI / real(this % n_azi,8) + dangle = TWO * PI / real(this % n_azi, 8) do iazi = 1, this % n_azi - this % azimuthal(iazi) = -PI + (real(iazi,8) - HALF) * dangle + this % azimuthal(iazi) = -PI + (real(iazi, 8) - HALF) * dangle end do end if ! Load the more specific data - allocate(this % nu_fission(groups,this % n_azi,this % n_pol)) - allocate(this % chi(groups,groups,this % n_azi,this % n_pol)) + allocate(this % nu_fission(groups, this % n_azi, this % n_pol)) + allocate(this % chi(groups, groups, this % n_azi, this % n_pol)) if (this % fissionable) then - if (check_for_node(node_xsdata,"chi")) then + if (check_for_node(node_xsdata, "chi")) then ! Chi was provided, that means they are giving chi and nu-fission ! vectors ! Get chi allocate(temp_arr(1 * groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"chi",temp_arr) + call get_node_array(node_xsdata, "chi", temp_arr) ! Initialize counter for temp_arr l = 0 gin = 1 @@ -637,11 +639,12 @@ module mgxs_header do iazi = 1, this % n_azi do gout = 1, groups l = l + 1 - this % chi(gout,gin,iazi,ipol) = temp_arr(l) + this % chi(gout, gin, iazi, ipol) = temp_arr(l) end do ! Normalize chi so its CDF goes to 1 - this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / & - sum(this % chi(:,gin,iazi,ipol)) + this % chi(:, gin, iazi, ipol) = & + this % chi(:, gin, iazi, ipol) / & + sum(this % chi(:, gin, iazi, ipol)) end do end do @@ -649,17 +652,19 @@ module mgxs_header do ipol = 1, this % n_pol do iazi = 1, this % n_azi do gin = 2, groups - this % chi(:,gin,iazi,ipol) = this % chi(:,1,iazi,ipol) + this % chi(:, gin, iazi, ipol) = & + this % chi(:, 1, iazi, ipol) end do end do end do deallocate(temp_arr) ! Get nu_fission (as a vector) - if (check_for_node(node_xsdata,"nu_fission")) then + if (check_for_node(node_xsdata, "nu_fission")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - this % nu_fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "nu_fission", temp_arr) + this % nu_fission = reshape(temp_arr,(/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -668,11 +673,12 @@ module mgxs_header else ! chi isnt provided but is within nu_fission, existing as a matrix ! So, get nu_fission (as a matrix) - if (check_for_node(node_xsdata,"nu_fission")) then + if (check_for_node(node_xsdata, "nu_fission")) then allocate(temp_arr(groups * groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"nu_fission",temp_arr) - allocate(temp_4d(groups,groups,this % n_azi,this % n_pol)) - temp_4d = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "nu_fission", temp_arr) + allocate(temp_4d(groups, groups, this % n_azi,this % n_pol)) + temp_4d = reshape(temp_arr, (/groups, groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -682,7 +688,8 @@ module mgxs_header do ipol = 1, this % n_pol do iazi = 1, this % n_azi do gin = 1, groups - this % nu_fission(gin,iazi,ipol) = sum(temp_4d(:,gin,iazi,ipol)) + this % nu_fission(gin, iazi, ipol) = & + sum(temp_4d(:, gin, iazi, ipol)) end do end do end do @@ -693,8 +700,9 @@ module mgxs_header do ipol = 1, this % n_pol do iazi = 1, this % n_azi do gin = 1, groups - this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / & - sum(this % chi(:,gin,iazi,ipol)) + this % chi(:, gin, iazi, ipol) = & + this % chi(:, gin, iazi, ipol) / & + sum(this % chi(:, gin, iazi, ipol)) end do end do end do @@ -704,11 +712,12 @@ module mgxs_header ! If we have a need* for the fission and kappa-fission x/s, get them ! (*Need is defined as will be using it to tally) if (get_fiss) then - if (check_for_node(node_xsdata,"fission")) then + if (check_for_node(node_xsdata, "fission")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"fission",temp_arr) - allocate(this % fission(groups,this % n_azi,this % n_pol)) - this % fission = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "fission", temp_arr) + allocate(this % fission(groups, this % n_azi, this % n_pol)) + this % fission = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("Fission data missing, required due to fission& @@ -716,11 +725,12 @@ module mgxs_header end if end if if (get_kfiss) then - if (check_for_node(node_xsdata,"kappa_fission")) then + if (check_for_node(node_xsdata, "kappa_fission")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"kappa_fission",temp_arr) - allocate(this % k_fission(groups,this % n_azi,this % n_pol)) - this % k_fission = reshape(temp_arr,(/groups, this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "kappa_fission", temp_arr) + allocate(this % k_fission(groups, this % n_azi, this % n_pol)) + this % k_fission = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("kappa_fission data missing, required due to & @@ -732,24 +742,26 @@ module mgxs_header this % chi = ZERO end if - if (check_for_node(node_xsdata,"absorption")) then + if (check_for_node(node_xsdata, "absorption")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"absorption",temp_arr) - allocate(this % absorption(groups,this % n_azi,this % n_pol)) - this % absorption = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "absorption", temp_arr) + allocate(this % absorption(groups, this % n_azi, this % n_pol)) + this % absorption = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("Must provide absorption!") end if ! Get multiplication data if present - allocate(temp_mult(groups,groups,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"multiplicity")) then - arr_len = get_arraysize_double(node_xsdata,"multiplicity") + allocate(temp_mult(groups,groups, this % n_azi, this % n_pol)) + if (check_for_node(node_xsdata, "multiplicity")) then + arr_len = get_arraysize_double(node_xsdata, "multiplicity") if (arr_len == groups * groups * this % n_azi * this % n_pol) then allocate(temp_arr(arr_len)) - call get_node_array(node_xsdata,"multiplicity",temp_arr) - temp_mult = reshape(temp_arr,(/groups,groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "multiplicity", temp_arr) + temp_mult = reshape(temp_arr, (/groups, groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("Multiplicity length not same as number of groups& @@ -766,24 +778,25 @@ module mgxs_header ! Set the default (leave as Legendre polynomials) enable_leg_mu = .false. - if (check_for_node(node_xsdata,"tabular_legendre")) then - call get_node_ptr(node_xsdata,"tabular_legendre",node_legendre_mu) + if (check_for_node(node_xsdata, "tabular_legendre")) then + call get_node_ptr(node_xsdata, "tabular_legendre", node_legendre_mu) if (check_for_node(node_legendre_mu, "enable")) then - call get_node_value(node_legendre_mu,"enable",temp_str) + call get_node_value(node_legendre_mu, "enable", temp_str) temp_str = trim(to_lower(temp_str)) if (temp_str == 'true' .or. temp_str == '1') then enable_leg_mu = .true. elseif (temp_str == 'false' .or. temp_str == '0') then enable_leg_mu = .false. else - call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str) + call fatal_error("Unrecognized tabular_legendre/enable: " & + // temp_str) end if end if ! Ok, so if we need to convert to a tabular form, get the user provided ! number of points if (enable_leg_mu) then - if (check_for_node(node_legendre_mu,"num_points")) then - call get_node_value(node_legendre_mu,"num_points", & + if (check_for_node(node_legendre_mu, "num_points")) then + call get_node_value(node_legendre_mu, "num_points", & legendre_mu_points) if (legendre_mu_points <= 0) & call fatal_error("num_points element must be positive& @@ -796,8 +809,8 @@ module mgxs_header end if ! Get the library's value for the order - if (check_for_node(node_xsdata,"order")) then - call get_node_value(node_xsdata,"order",order) + if (check_for_node(node_xsdata, "order")) then + call get_node_value(node_xsdata, "order", order) else call fatal_error("Order Must Be Provided!") end if @@ -817,13 +830,14 @@ module mgxs_header ! Gout x Gin x Order x Azi x Pol. We will get it in that format in ! input_scatt, but then need to convert it to a more useful ordering ! for processing (Order x Gout x Gin x Azi x Pol). - allocate(input_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"scatter")) then + allocate(input_scatt(groups, groups, order_dim, this % n_azi, & + this % n_pol)) + if (check_for_node(node_xsdata, "scatter")) then allocate(temp_arr(groups * groups * order_dim * this % n_azi * & this % n_pol)) - call get_node_array(node_xsdata,"scatter",temp_arr) - input_scatt = reshape(temp_arr,(/groups,groups,order_dim,this % n_azi, & - this % n_pol/)) + call get_node_array(node_xsdata, "scatter", temp_arr) + input_scatt = reshape(temp_arr, (/groups, groups, order_dim, & + this % n_azi, this % n_pol/)) deallocate(temp_arr) ! Compare the number of orders given with the maximum order of the @@ -833,8 +847,9 @@ module mgxs_header order_dim = order + 1 end if - allocate(temp_scatt(groups,groups,order_dim,this % n_azi,this % n_pol)) - temp_scatt(:,:,:,:,:) = input_scatt(:,:,1:order_dim,:,:) + allocate(temp_scatt(groups, groups, order_dim, this % n_azi, & + this % n_pol)) + temp_scatt(:, :, :, :, :) = input_scatt(:, :, 1:order_dim, :, :) ! Take input format (groups, groups, order) and convert to ! the more useful format needed for scattdata: (order, groups, groups) @@ -848,9 +863,10 @@ module mgxs_header this % scatt_type = ANGLE_TABULAR order_dim = legendre_mu_points order = order_dim - dmu = TWO / real(order - 1,8) + dmu = TWO / real(order - 1, 8) - allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + allocate(scatt_coeffs(order_dim, groups, groups, this % n_azi, & + this % n_pol)) do ipol = 1, this % n_pol do iazi = 1, this % n_azi do gin = 1, groups @@ -862,26 +878,26 @@ module mgxs_header else if (imu == order_dim) then mu = ONE else - mu = -ONE + real(imu - 1,8) * dmu + mu = -ONE + real(imu - 1, 8) * dmu end if - scatt_coeffs(imu,gout,gin,iazi,ipol) = & - evaluate_legendre(temp_scatt(gout,gin,:,iazi,ipol),mu) + scatt_coeffs(imu, gout, gin, iazi, ipol) = & + evaluate_legendre(temp_scatt(gout, gin, :, iazi, ipol), mu) ! Ensure positivity of distribution - if (scatt_coeffs(imu,gout,gin,iazi,ipol) < ZERO) & - scatt_coeffs(imu,gout,gin,iazi,ipol) = ZERO + if (scatt_coeffs(imu, gout, gin, iazi, ipol) < ZERO) & + scatt_coeffs(imu, gout, gin, iazi, ipol) = ZERO ! And accrue the integral if (imu > 1) then norm = norm + HALF * dmu * & - (scatt_coeffs(imu-1,gout,gin,iazi,ipol) + & - scatt_coeffs(imu,gout,gin,iazi,ipol)) + (scatt_coeffs(imu - 1, gout, gin, iazi, ipol) + & + scatt_coeffs(imu, gout, gin, iazi, ipol)) end if end do ! Now that we have the integral, lets ensure that the distribution ! is normalized such that it preserves the original scattering xs if (norm > ZERO) then - scatt_coeffs(:,gout,gin,iazi,ipol) = & - scatt_coeffs(:,gout,gin,iazi,ipol) * & - temp_scatt(gout,gin,1,iazi,ipol) / norm + scatt_coeffs(:, gout, gin, iazi, ipol) = & + scatt_coeffs(:, gout, gin, iazi, ipol) * & + temp_scatt(gout, gin, 1, iazi, ipol) / norm end if end do end do @@ -890,14 +906,15 @@ module mgxs_header else ! Sticking with current representation, carry forward but change ! the array ordering - allocate(scatt_coeffs(order_dim,groups,groups,this % n_azi,this % n_pol)) + allocate(scatt_coeffs(order_dim, groups, groups, this % n_azi, & + this % n_pol)) do ipol = 1, this % n_pol do iazi = 1, this % n_azi do gin = 1, groups do gout = 1, groups do l = 1, order_dim - scatt_coeffs(l,gout,gin,iazi,ipol) = & - temp_scatt(gout,gin,l,iazi,ipol) + scatt_coeffs(l, gout, gin, iazi, ipol) = & + temp_scatt(gout, gin, l, iazi, ipol) end do end do end do @@ -911,35 +928,37 @@ module mgxs_header allocate(this % scatter(this % n_azi, this % n_pol)) do ipol = 1, this % n_pol - do iazi = 1, this % n_azi + do iazi = 1, this % n_azi ! Allocate and initialize our ScattData Object. if (this % scatt_type == ANGLE_HISTOGRAM) then - allocate(ScattDataHistogram :: this % scatter(iazi,ipol) % obj) + allocate(ScattDataHistogram :: this % scatter(iazi, ipol) % obj) else if (this % scatt_type == ANGLE_TABULAR) then - allocate(ScattDataTabular :: this % scatter(iazi,ipol) % obj) + allocate(ScattDataTabular :: this % scatter(iazi, ipol) % obj) else if (this % scatt_type == ANGLE_LEGENDRE) then - allocate(ScattDataLegendre :: this % scatter(iazi,ipol) % obj) + allocate(ScattDataLegendre :: this % scatter(iazi, ipol) % obj) end if ! Initialize the ScattData Object - call this % scatter(iazi,ipol) % obj % init(& - temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) + call this % scatter(iazi, ipol) % obj % init(& + temp_mult(:, :, iazi, ipol), & + scatt_coeffs(:, :, :, iazi, ipol)) end do end do ! Deallocate temporaries for the next material - deallocate(input_scatt,scatt_coeffs,temp_mult) + deallocate(input_scatt, scatt_coeffs, temp_mult) - allocate(this % total(groups,this % n_azi,this % n_pol)) - if (check_for_node(node_xsdata,"total")) then + allocate(this % total(groups, this % n_azi, this % n_pol)) + if (check_for_node(node_xsdata, "total")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) - call get_node_array(node_xsdata,"total",temp_arr) - this % total = reshape(temp_arr,(/groups,this % n_azi,this % n_pol/)) + call get_node_array(node_xsdata, "total", temp_arr) + this % total = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else do ipol = 1, this % n_pol do iazi = 1, this % n_azi - this % total(:,iazi,ipol) = this % absorption(:,iazi,ipol) + & - this % scatter(iazi,ipol) % obj % scattxs(:) + this % total(:, iazi, ipol) = this % absorption(:, iazi, ipol) + & + this % scatter(iazi, ipol) % obj % scattxs(:) end do end do end if @@ -1074,13 +1093,13 @@ module mgxs_header size_scattmat = 0 do ipol = 1, this % n_pol do iazi = 1, this % n_azi - do gin = 1, size(this % scatter(iazi,ipol) % obj % energy) + do gin = 1, size(this % scatter(iazi, ipol) % obj % energy) size_scattmat = size_scattmat + & - 2 * size(this % scatter(iazi,ipol) % obj % energy(gin) % data) + & - size(this % scatter(iazi,ipol) % obj % dist(gin) % data) + 2 * size(this % scatter(iazi, ipol) % obj % energy(gin) % data) + & + size(this % scatter(iazi, ipol) % obj % dist(gin) % data) end do size_scattmat = size_scattmat + & - size(this % scatter(iazi,ipol) % obj % scattxs) + size(this % scatter(iazi, ipol) % obj % scattxs) end do end do size_scattmat = size_scattmat * 8 @@ -1141,7 +1160,7 @@ module mgxs_header xs = this % chi(gout,gin) else ! Not sure youd want a 1 or a 0, but here you go! - xs = sum(this % chi(:,gin)) + xs = sum(this % chi(:, gin)) end if case('scatter') if (present(gout)) then @@ -1211,68 +1230,69 @@ module mgxs_header call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) select case(xstype) case('total') - xs = this % total(gin,iazi,ipol) + xs = this % total(gin, iazi, ipol) case('absorption') - xs = this % absorption(gin,iazi,ipol) + xs = this % absorption(gin, iazi, ipol) case('fission') if (allocated(this % fission)) then - xs = this % fission(gin,iazi,ipol) + xs = this % fission(gin, iazi, ipol) else xs = ZERO end if case('kappa_fission') if (allocated(this % k_fission)) then - xs = this % k_fission(gin,iazi,ipol) + xs = this % k_fission(gin, iazi, ipol) else xs = ZERO end if case('nu_fission') - xs = this % nu_fission(gin,iazi,ipol) + xs = this % nu_fission(gin, iazi, ipol) case('chi') if (present(gout)) then - xs = this % chi(gout,gin,iazi,ipol) + xs = this % chi(gout, gin, iazi, ipol) else ! Not sure youd want a 1 or a 0, but here you go! - xs = sum(this % chi(:,gin,iazi,ipol)) + xs = sum(this % chi(:, gin, iazi, ipol)) end if case('scatter') if (present(gout)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + if (gout < this % scatter(iazi, ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi, ipol) % obj % gmax(gin)) then xs = ZERO else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) + xs = this % scatter(iazi, ipol) % obj % scattxs(gin) * & + this % scatter(iazi, ipol) % obj % energy(gin) % data(gout) end if else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) + xs = this % scatter(iazi, ipol) % obj % scattxs(gin) end if case('scatter/mult') if (present(gout)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + if (gout < this % scatter(iazi, ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi, ipol) % obj % gmax(gin)) then xs = ZERO else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) / & - this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + xs = this % scatter(iazi, ipol) % obj % scattxs(gin) * & + this % scatter(iazi, ipol) % obj % energy(gin) % data(gout) / & + this % scatter(iazi, ipol) % obj % mult(gin) % data(gout) end if else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) / & - (dot_product(this % scatter(iazi,ipol) % obj % mult(gin) % data, & - this % scatter(iazi,ipol) % obj % energy(gin) % data)) + xs = this % scatter(iazi, ipol) % obj % scattxs(gin) / & + (dot_product(this % scatter(iazi, ipol) % obj % mult(gin) % data, & + this % scatter(iazi, ipol) % obj % energy(gin) % data)) end if case('scatter*f_mu/mult','scatter*f_mu') if (present(gout)) then - if (gout < this % scatter(iazi,ipol) % obj % gmin(gin) .or. & - gout > this % scatter(iazi,ipol) % obj % gmax(gin)) then + if (gout < this % scatter(iazi, ipol) % obj % gmin(gin) .or. & + gout > this % scatter(iazi, ipol) % obj % gmax(gin)) then xs = ZERO else - xs = this % scatter(iazi,ipol) % obj % scattxs(gin) * & - this % scatter(iazi,ipol) % obj % energy(gin) % data(gout) - xs = xs * this % scatter(iazi,ipol) % obj % calc_f(gin, gout, mu) + xs = this % scatter(iazi, ipol) % obj % scattxs(gin) * & + this % scatter(iazi, ipol) % obj % energy(gin) % data(gout) + xs = xs * this % scatter(iazi, ipol) % obj % calc_f(gin, gout, mu) if (xstype == 'scatter*f_mu/mult') then - xs = xs / this % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + xs = xs / & + this % scatter(iazi, ipol) % obj % mult(gin) % data(gout) end if end if else @@ -1335,11 +1355,11 @@ module mgxs_header real(8) :: atom_density ! atom density of a nuclide real(8) :: norm, nuscatt integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:), mult_num(:,:), mult_denom(:,:) - real(8), allocatable :: scatt_coeffs(:,:,:) + real(8), allocatable :: temp_mult(:, :), mult_num(:, :), mult_denom(:, :) + real(8), allocatable :: scatt_coeffs(:, :, :) ! Set the meta-data - call mgxs_combine(this,mat,scatt_type,i_listing) + call mgxs_combine(this, mat, scatt_type, i_listing) ! Determine the scattering type of our data and ensure all scattering orders ! are the same. @@ -1350,7 +1370,6 @@ module mgxs_header ! If we have tabular only data, then make sure all datasets have same size if (scatt_type == ANGLE_HISTOGRAM) then ! Check all scattering data to ensure it is the same size - ! order = size(nuclides(mat % nuclide(1)) % obj % scatter % data,dim=1) do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) @@ -1370,7 +1389,7 @@ module mgxs_header do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) - if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & + if (order /= size(nuc % scatter % dist(1) % data, dim=1)) & call fatal_error("All Tabular Scattering Entries Must Be& & Same Length!") end select @@ -1388,7 +1407,7 @@ module mgxs_header select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) if (size(nuc % scatter % dist(1) % data,dim=1) > mat_max_order) & - mat_max_order = size(nuc % scatter % dist(1) % data,dim=1) + mat_max_order = size(nuc % scatter % dist(1) % data, dim=1) end select end do @@ -1444,7 +1463,8 @@ module mgxs_header this % fission = this % fission + atom_density * nuc % fission end if if (allocated(nuc % k_fission)) then - this % k_fission = this % k_fission + atom_density * nuc % k_fission + this % k_fission = this % k_fission + atom_density * & + nuc % k_fission end if end if @@ -1471,11 +1491,11 @@ module mgxs_header end do ! Get the complete scattering matrix - nuc_order_dim = size(nuc % scatter % dist(1) % data,dim=1) - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) = & - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:) + & + nuc_order_dim = size(nuc % scatter % dist(1) % data, dim=1) + scatt_coeffs(1:min(nuc_order_dim, order_dim), :, :) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim), :, :) + & atom_density * & - nuc % scatter % get_matrix(min(nuc_order_dim,order_dim)) + nuc % scatter % get_matrix(min(nuc_order_dim, order_dim)) type is (MgxsAngle) call fatal_error("Invalid Passing of MgxsAngle to MgxsIso Object") @@ -1494,14 +1514,14 @@ module mgxs_header end do ! Initialize the ScattData Object - call this % scatter % init(temp_mult,scatt_coeffs) + call this % scatter % init(temp_mult, scatt_coeffs) ! Now normalize chi if (mat % fissionable) then do gin = 1, groups - norm = sum(this % chi(:,gin)) + norm = sum(this % chi(:, gin)) if (norm > ZERO) then - this % chi(:,gin) = this % chi(:,gin) / norm + this % chi(:, gin) = this % chi(:, gin) / norm end if end do end if @@ -1527,8 +1547,8 @@ module mgxs_header integer :: ipol, iazi, n_pol, n_azi real(8) :: norm, nuscatt integer :: mat_max_order, order, order_dim, nuc_order_dim - real(8), allocatable :: temp_mult(:,:,:,:), mult_num(:,:,:,:), mult_denom(:,:,:,:) - real(8), allocatable :: scatt_coeffs(:,:,:,:,:) + real(8), allocatable :: temp_mult(:, :, :, :), mult_num(:, :, :, :) + real(8), allocatable :: mult_denom(:, :, :, :), scatt_coeffs(:, :, :, :, :) ! Set the meta-data call mgxs_combine(this,mat,scatt_type,i_listing) @@ -1568,7 +1588,7 @@ module mgxs_header do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsAngle) - if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1)) & call fatal_error("All Histogram Scattering Entries Must Be& & Same Length!") end select @@ -1589,7 +1609,7 @@ module mgxs_header do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsAngle) - if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1)) & + if (order /= size(nuc % scatter(1, 1) % obj % dist(1) % data,dim=1)) & call fatal_error("All Tabular Scattering Entries Must Be& & Same Length!") end select @@ -1611,8 +1631,8 @@ module mgxs_header do i = 1, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsAngle) - if (size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) > mat_max_order) & - mat_max_order = size(nuc % scatter(1,1) % obj% dist(1) % data,dim=1) + if (size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1) > mat_max_order) & + mat_max_order = size(nuc % scatter(1,1) % obj% dist(1) % data, dim=1) end select end do @@ -1632,25 +1652,25 @@ module mgxs_header end if ! Allocate and initialize data within macro_xs(i_mat) object - allocate(this % total(groups,n_azi,n_pol)) + allocate(this % total(groups, n_azi, n_pol)) this % total = ZERO - allocate(this % absorption(groups,n_azi,n_pol)) + allocate(this % absorption(groups, n_azi, n_pol)) this % absorption = ZERO - allocate(this % fission(groups,n_azi,n_pol)) + allocate(this % fission(groups, n_azi, n_pol)) this % fission = ZERO - allocate(this % k_fission(groups,n_azi,n_pol)) + allocate(this % k_fission(groups, n_azi, n_pol)) this % k_fission = ZERO - allocate(this % nu_fission(groups,n_azi,n_pol)) + allocate(this % nu_fission(groups, n_azi, n_pol)) this % nu_fission = ZERO - allocate(this % chi(groups,groups,n_azi,n_pol)) + allocate(this % chi(groups, groups, n_azi, n_pol)) this % chi = ZERO - allocate(temp_mult(groups,groups,n_azi,n_pol)) + allocate(temp_mult(groups, groups, n_azi, n_pol)) temp_mult = ZERO - allocate(mult_num(groups,groups,n_azi,n_pol)) + allocate(mult_num(groups, groups, n_azi, n_pol)) mult_num = ZERO - allocate(mult_denom(groups,groups,n_azi,n_pol)) + allocate(mult_denom(groups, groups, n_azi, n_pol)) mult_denom = ZERO - allocate(scatt_coeffs(order_dim,groups,groups,n_azi,n_pol)) + allocate(scatt_coeffs(order_dim, groups, groups, n_azi, n_pol)) scatt_coeffs = ZERO ! Add contribution from each nuclide in material @@ -1675,7 +1695,8 @@ module mgxs_header this % fission = this % fission + atom_density * nuc % fission end if if (allocated(nuc % k_fission)) then - this % k_fission = this % k_fission + atom_density * nuc % k_fission + this % k_fission = this % k_fission + atom_density * & + nuc % k_fission end if end if @@ -1693,15 +1714,16 @@ module mgxs_header do ipol = 1, n_pol do iazi = 1, n_azi do gin = 1, groups - do gout = nuc % scatter(iazi,ipol) % obj % gmin(gin), & - nuc % scatter(iazi,ipol) % obj % gmax(gin) - nuscatt = nuc % scatter(iazi,ipol) % obj % scattxs(gin) * & - nuc % scatter(iazi,ipol) % obj % energy(gin) % data(gout) - mult_num(gout,gin,iazi,ipol) = mult_num(gout,gin,iazi,ipol) + & + do gout = nuc % scatter(iazi, ipol) % obj % gmin(gin), & + nuc % scatter(iazi, ipol) % obj % gmax(gin) + nuscatt = nuc % scatter(iazi, ipol) % obj % scattxs(gin) * & + nuc % scatter(iazi, ipol) % obj % energy(gin) % data(gout) + mult_num(gout, gin, iazi, ipol) = mult_num(gout, gin, iazi, ipol) + & atom_density * nuscatt - mult_denom(gout,gin,iazi,ipol) = mult_denom(gout,gin,iazi,ipol) + & + mult_denom(gout, gin, iazi, ipol) = & + mult_denom(gout, gin, iazi, ipol) + & atom_density * nuscatt / & - nuc % scatter(iazi,ipol) % obj % mult(gin) % data(gout) + nuc % scatter(iazi, ipol) % obj % mult(gin) % data(gout) end do end do end do @@ -1711,11 +1733,10 @@ module mgxs_header nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) do ipol = 1, n_pol do iazi = 1, n_azi - scatt_coeffs(1:min(nuc_order_dim,order_dim),:,:,iazi,ipol) = & - scatt_coeffs(1:min(nuc_order_dim, order_dim),:,:,iazi,ipol) + & - atom_density * & - nuc % scatter(iazi,ipol) % obj % get_matrix(& - min(nuc_order_dim,order_dim)) + scatt_coeffs(1:min(nuc_order_dim, order_dim), :, :, iazi, ipol) = & + scatt_coeffs(1:min(nuc_order_dim, order_dim), :, :, iazi, ipol) + & + atom_density * nuc % scatter(iazi, ipol) % obj % get_matrix(& + min(nuc_order_dim, order_dim)) end do end do end select @@ -1726,10 +1747,12 @@ module mgxs_header do iazi = 1, n_azi do gin = 1, groups do gout = 1, groups - if (mult_denom(gout,gin,iazi,ipol) > ZERO) then - temp_mult(gout,gin,iazi,ipol) = mult_num(gout,gin,iazi,ipol) / mult_denom(gout,gin,iazi,ipol) + if (mult_denom(gout, gin, iazi, ipol) > ZERO) then + temp_mult(gout, gin, iazi, ipol) = & + mult_num(gout, gin, iazi, ipol) / & + mult_denom(gout, gin, iazi, ipol) else - temp_mult(gout,gin,iazi,ipol) = ONE + temp_mult(gout, gin, iazi, ipol) = ONE end if end do end do @@ -1739,8 +1762,8 @@ module mgxs_header ! Initialize the ScattData Object do ipol = 1, n_pol do iazi = 1, n_azi - call this % scatter(iazi,ipol) % obj % init( & - temp_mult(:,:,iazi,ipol), scatt_coeffs(:,:,:,iazi,ipol)) + call this % scatter(iazi, ipol) % obj % init( & + temp_mult(:, :, iazi, ipol), scatt_coeffs(:, :, :, iazi, ipol)) end do end do @@ -1749,9 +1772,9 @@ module mgxs_header do ipol = 1, n_pol do iazi = 1, n_azi do gin = 1, groups - norm = sum(this % chi(:,gin,iazi,ipol)) + norm = sum(this % chi(:, gin, iazi, ipol)) if (norm > ZERO) then - this % chi(:,gin,iazi,ipol) = this % chi(:,gin,iazi,ipol) / norm + this % chi(:, gin, iazi, ipol) = this % chi(:, gin, iazi, ipol) / norm end if end do end do @@ -1799,11 +1822,11 @@ module mgxs_header xi = prn() gout = 1 - prob = this % chi(gout,gin,iazi,ipol) + prob = this % chi(gout, gin, iazi, ipol) do while (prob < xi) gout = gout + 1 - prob = prob + this % chi(gout,gin,iazi,ipol) + prob = prob + this % chi(gout, gin, iazi, ipol) end do end function mgxsang_sample_fission_energy @@ -1835,7 +1858,7 @@ module mgxs_header integer :: iazi, ipol ! Angular indices call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - call this % scatter(iazi,ipol) % obj % sample(gin,gout,mu,wgt) + call this % scatter(iazi, ipol) % obj % sample(gin, gout, mu, wgt) end subroutine mgxsang_sample_scatter @@ -1867,15 +1890,38 @@ module mgxs_header integer :: iazi, ipol call find_angle(this % polar, this % azimuthal, uvw, iazi, ipol) - xs % total = this % total(gin,iazi,ipol) - xs % elastic = this % scatter(iazi,ipol) % obj % scattxs(gin) - xs % absorption = this % absorption(gin,iazi,ipol) - xs % fission = this % fission(gin,iazi,ipol) - xs % nu_fission = this % nu_fission(gin,iazi,ipol) + xs % total = this % total(gin, iazi, ipol) + xs % elastic = this % scatter(iazi, ipol) % obj % scattxs(gin) + xs % absorption = this % absorption(gin, iazi, ipol) + xs % fission = this % fission(gin, iazi, ipol) + xs % nu_fission = this % nu_fission(gin, iazi, ipol) end subroutine mgxsang_calculate_xs -!!!TODO: -! Move find_angle from math to here after we fully implement this and are ready -! to delete macroxs_header and relevant portions from nuclide_header. +!=============================================================================== +! find_angle finds the closest angle on the data grid and returns that index +!=============================================================================== + + pure subroutine find_angle(polar, azimuthal, uvw, i_azi, i_pol) + real(8), intent(in) :: polar(:) ! Polar angles [0,pi] + real(8), intent(in) :: azimuthal(:) ! Azi. angles [-pi,pi] + real(8), intent(in) :: uvw(3) ! Direction of motion + integer, intent(inout) :: i_pol ! Closest polar bin + integer, intent(inout) :: i_azi ! Closest azi bin + + real(8) :: my_pol, my_azi, dangle + + ! Convert uvw to polar and azi + + my_pol = acos(uvw(3)) + my_azi = atan2(uvw(2), uvw(1)) + + ! Search for equi-binned angles + dangle = PI / real(size(polar),8) + i_pol = floor(my_pol / dangle + ONE) + dangle = TWO * PI / real(size(azimuthal),8) + i_azi = floor((my_azi + PI) / dangle + ONE) + + end subroutine find_angle + end module mgxs_header \ No newline at end of file diff --git a/src/nuclide_header.F90 b/src/nuclide_header.F90 index ad7e4da32..92e2d7ba3 100644 --- a/src/nuclide_header.F90 +++ b/src/nuclide_header.F90 @@ -8,7 +8,7 @@ module nuclide_header use endf_header, only: Function1D use error, only: fatal_error, warning use list_header, only: ListInt - use math, only: evaluate_legendre, find_angle + use math, only: evaluate_legendre use product_header, only: AngleEnergyContainer use reaction_header, only: Reaction use stl_vector, only: VectorInt diff --git a/src/particle_header.F90 b/src/particle_header.F90 index 6b2972768..8544cb38b 100644 --- a/src/particle_header.F90 +++ b/src/particle_header.F90 @@ -232,7 +232,7 @@ contains this % n_secondary = n this % secondary_bank(this % n_secondary) % E = this % E if (.not. run_CE) then - this % secondary_bank(this % n_secondary) % E = real(this % g,8) + this % secondary_bank(this % n_secondary) % E = real(this % g, 8) end if end subroutine create_secondary diff --git a/src/tally.F90 b/src/tally.F90 index ed1d45c87..86e108c3d 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -903,13 +903,14 @@ contains end if if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('total',p_g,UVW=p_uvw) / & - matxs % get_xs('total',p_g,UVW=p_uvw) + nucxs % get_xs('total', p_g, UVW=p_uvw) / & + matxs % get_xs('total', p_g, UVW=p_uvw) end if else if (i_nuclide > 0) then - score = nucxs % get_xs('total',p_g,UVW=p_uvw) * atom_density * flux + score = nucxs % get_xs('total', p_g, UVW=p_uvw) * & + atom_density * flux else score = material_xs % total * flux end if @@ -959,20 +960,22 @@ contains ! adjust the score by the actual probability for that nuclide. if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('scatter*f_mu/mult',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & - matxs % get_xs('scatter*f_mu/mult',p % last_g,p % g,UVW=p_uvw,MU=p % mu) + nucxs % get_xs('scatter*f_mu/mult', p % last_g, p % g, & + UVW=p_uvw,MU=p % mu) / & + matxs % get_xs('scatter*f_mu/mult', p % last_g, p % g, & + UVW=p_uvw,MU=p % mu) end if else ! Note SCORE_SCATTER_*N not available for tracklength/collision. if (i_nuclide > 0) then score = atom_density * flux * & - nucxs % get_xs('scatter/mult',p_g,UVW=p_uvw) + nucxs % get_xs('scatter/mult', p_g, UVW=p_uvw) else ! Get the scattering x/s and take away ! the multiplication baked in to sigS score = flux * & - matxs % get_xs('scatter/mult',p_g,UVW=p_uvw) + matxs % get_xs('scatter/mult', p_g, UVW=p_uvw) end if end if @@ -1000,18 +1003,20 @@ contains ! adjust the score by the actual probability for that nuclide. if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('scatter*f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) / & - matxs % get_xs('scatter*f_mu',p % last_g,p % g,UVW=p_uvw,MU=p % mu) + nucxs % get_xs('scatter*f_mu', p % last_g, p % g, & + UVW=p_uvw, MU=p % mu) / & + matxs % get_xs('scatter*f_mu', p % last_g, p % g, & + UVW=p_uvw, MU=p % mu) end if else ! Note SCORE_NU_SCATTER_*N not available for tracklength/collision. if (i_nuclide > 0) then - score = nucxs % get_xs('scatter',p_g,UVW=p_uvw) * & + score = nucxs % get_xs('scatter', p_g, UVW=p_uvw) * & atom_density * flux else ! Get the scattering x/s, which includes multiplication - score = matxs % get_xs('scatter',p_g,UVW=p_uvw) * flux + score = matxs % get_xs('scatter', p_g, UVW=p_uvw) * flux end if end if @@ -1045,12 +1050,12 @@ contains end if if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('absorption',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) + nucxs % get_xs('absorption', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else if (i_nuclide > 0) then - score = nucxs % get_xs('absorption',p_g,UVW=p_uvw) * & + score = nucxs % get_xs('absorption', p_g, UVW=p_uvw) * & atom_density * flux else score = material_xs % absorption * flux @@ -1075,16 +1080,16 @@ contains end if if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('fission', p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) + nucxs % get_xs('fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) else score = score * & - matxs % get_xs('fission', p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) + matxs % get_xs('fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else if (i_nuclide > 0) then - score = nucxs % get_xs('fission',p_g,UVW=p_uvw) * & + score = nucxs % get_xs('fission', p_g, UVW=p_uvw) * & atom_density * flux else score = flux * material_xs % fission @@ -1102,7 +1107,8 @@ contains ! neutrons were emitted with different energies, multiple ! outgoing energy bins may have been scored to. The following ! logic treats this special case and results to multiple bins - call score_fission_eout_mg(p,t,score_index,i_nuclide,atom_density) + call score_fission_eout_mg(p, t, score_index, i_nuclide, & + atom_density) cycle SCORE_LOOP end if end if @@ -1113,12 +1119,12 @@ contains score = p % absorb_wgt if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) + nucxs % get_xs('nu_fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) else score = score * & - matxs % get_xs('nu_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption',p_g,UVW=p_uvw) + matxs % get_xs('nu_fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else ! Skip any non-fission events @@ -1131,14 +1137,14 @@ contains score = keff * p % wgt_bank if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('fission',p_g,UVW=p_uvw) / & - matxs % get_xs('fission',p_g,UVW=p_uvw) + nucxs % get_xs('fission', p_g, UVW=p_uvw) / & + matxs % get_xs('fission', p_g, UVW=p_uvw) end if end if else if (i_nuclide > 0) then - score = nucxs % get_xs('nu_fission',p_g,UVW=p_uvw) * & + score = nucxs % get_xs('nu_fission', p_g, UVW=p_uvw) * & atom_density * flux else score = material_xs % nu_fission * flux @@ -1163,19 +1169,19 @@ contains end if if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption', p_g,UVW=p_uvw) + nucxs % get_xs('kappa_fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) else score = score * & - matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) / & - matxs % get_xs('absorption', p_g,UVW=p_uvw) + matxs % get_xs('kappa_fission', p_g, UVW=p_uvw) / & + matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else if (i_nuclide > 0) then - score = flux * nucxs % get_xs('kappa_fission',p_g,UVW=p_uvw) * & - atom_density + score = flux * atom_density * & + nucxs % get_xs('kappa_fission', p_g, UVW=p_uvw) else - score = flux * matxs % get_xs('kappa_fission',p_g,UVW=p_uvw) + score = flux * matxs % get_xs('kappa_fission', p_g, UVW=p_uvw) end if end if @@ -1643,8 +1649,10 @@ contains gin = p % last_g end if score = score * atom_density * & - nuclides_MG(i_nuclide) % obj % get_xs('fission',gin,UVW=p % last_uvw) / & - macro_xs(p % material) % obj % get_xs('fission',gin,UVW=p % last_uvw) + nuclides_MG(i_nuclide) % obj % get_xs('fission', gin, & + UVW=p % last_uvw) / & + macro_xs(p % material) % obj % get_xs('fission', gin, & + UVW=p % last_uvw) end if if (t % energyout_matches_groups) then From 8aada0af2977c12940ecf37dbb2b2bdaaf5e117a Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sun, 8 May 2016 18:43:43 -0400 Subject: [PATCH 090/147] Added row_column parameter to Library.build_hdf5_store(...)` --- openmc/mgxs/library.py | 11 ++++++++--- openmc/mgxs/mgxs.py | 10 ++++++---- 2 files changed, 14 insertions(+), 7 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 8d5e9854e..c3529fc98 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -575,7 +575,8 @@ class Library(object): return subdomain_avg_library def build_hdf5_store(self, filename='mgxs.h5', directory='mgxs', - subdomains='all', nuclides='all', xs_type='macro'): + subdomains='all', nuclides='all', xs_type='macro', + row_column='inout'): """Export the multi-group cross section library to an HDF5 binary file. This method constructs an HDF5 file which stores the library's @@ -605,6 +606,10 @@ class Library(object): xs_type: {'macro', 'micro'} Store the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + row_column: {'inout', 'outin'} + Store scattering matrices indexed first by incoming group and + second by outgoing group ('inout'), or vice versa ('outin'). + Defaults to 'inout'. Raises ------ @@ -646,8 +651,8 @@ class Library(object): if subdomains == 'avg': mgxs = mgxs.get_subdomain_avg_xs() - mgxs.build_hdf5_store(filename, directory, - xs_type=xs_type, nuclides=nuclides) + mgxs.build_hdf5_store(filename, directory, xs_type=xs_type, + nuclides=nuclides, row_column=row_column) def dump_to_file(self, filename='mgxs', directory='mgxs'): """Store this Library object in a pickle binary file. diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 90b956b21..57f42c1ee 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1174,8 +1174,9 @@ class MGXS(object): Store the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. row_column: {'inout', 'outin'} - Store scattering matrices indexed first by incoming group and second - by outgoing group ('inout'), or vice versa ('outin'). + Store scattering matrices indexed first by incoming group and + second by outgoing group ('inout'), or vice versa ('outin'). + Defaults to 'inout'. append : bool If true, appends to an existing HDF5 file with the same filename directory (if one exists). Defaults to True. @@ -2005,8 +2006,9 @@ class ScatterMatrixXS(MGXS): decreasing energy groups (decreasing or increasing energies). Defaults to 'increasing'. row_column: {'inout', 'outin'} - Return the cross section indexed first by incoming group and second - by outgoing group ('inout'), or vice versa ('outin'). + Return the cross section indexed first by incoming group and + second by outgoing group ('inout'), or vice versa ('outin'). + Defaults to 'inout'. value : str A string for the type of value to return - 'mean', 'std_dev', or 'rel_err' are accepted. Defaults to the empty string. From dfe7a0026ab9b6e79e10798922de4d70f46f2d61 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 09:26:25 -0400 Subject: [PATCH 091/147] Fixed indentation and added error message for unlinked Summary file with distribcell paths in DataFrame --- openmc/filter.py | 6 ++++++ openmc/mgxs/mgxs.py | 8 +++++--- 2 files changed, 11 insertions(+), 3 deletions(-) diff --git a/openmc/filter.py b/openmc/filter.py index 01f2ad201..aab0fc081 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -629,6 +629,12 @@ class Filter(object): # Create Pandas Multi-index columns for each level in CSG tree if distribcell_paths: + # Distribcell paths require linked metadata from the Summary + if self.distribcell_paths is None: + msg = 'Unable to construct distribcell paths since ' + 'the Summary is not linked to the StatePoint' + raise ValueError(msg) + # Make copy of array of distribcell paths to use in # Pandas Multi-index column construction distribcell_paths = copy.deepcopy(self.distribcell_paths) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 99a3d8bfe..3133db047 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2576,9 +2576,11 @@ class Chi(MGXS): xs_type: {'macro', 'micro'} Return macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - distribcell_paths : list of str - The paths traversed through the CSG tree to reach each distribcell - instance (for 'distribcell' filters only) + distribcell_paths : bool, optional + Construct columns for distribcell tally filters (default is True). + The geometric information in the Summary object is embedded into + a Multi-index column with a geometric "path" to each distribcell + instance. Returns ------- From 838f84c963dbf5fe0f80b02bec2f056a3fd4036f Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 9 May 2016 08:33:18 -0500 Subject: [PATCH 092/147] Respond to @wbinventor comments on #642 --- openmc/statepoint.py | 6 +++--- openmc/universe.py | 4 ++-- 2 files changed, 5 insertions(+), 5 deletions(-) diff --git a/openmc/statepoint.py b/openmc/statepoint.py index 6c8af88a7..19aa3dbaf 100644 --- a/openmc/statepoint.py +++ b/openmc/statepoint.py @@ -622,8 +622,6 @@ class StatePoint(object): Raises ------ - RuntimeError - If a Summary object has already been linked. ValueError An error when the argument passed to the 'summary' parameter is not an openmc.Summary object. @@ -631,7 +629,9 @@ class StatePoint(object): """ if self.summary is not None: - raise RuntimeError('A Summary object has already been linked.') + warnings.warn('A Summary object has already been linked.', + RuntimeWarning) + return if not isinstance(summary, openmc.summary.Summary): msg = 'Unable to link statepoint with "{0}" which ' \ diff --git a/openmc/universe.py b/openmc/universe.py index 8834eaa52..770e789da 100644 --- a/openmc/universe.py +++ b/openmc/universe.py @@ -36,8 +36,8 @@ class Universe(object): automatically be assigned name : str, optional Name of the universe. If not specified, the name is the empty string. - cells : Iterable of openmc.Cell - Cells to add to the universe + cells : Iterable of openmc.Cell, optional + Cells to add to the universe. By default no cells are added. Attributes ---------- From 15fcf59d325b57acc4cb156e7bc5786b19641661 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 09:47:11 -0400 Subject: [PATCH 093/147] Fixed line continuation for error in Filter --- openmc/filter.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/filter.py b/openmc/filter.py index aab0fc081..52560a193 100644 --- a/openmc/filter.py +++ b/openmc/filter.py @@ -631,7 +631,7 @@ class Filter(object): # Distribcell paths require linked metadata from the Summary if self.distribcell_paths is None: - msg = 'Unable to construct distribcell paths since ' + msg = 'Unable to construct distribcell paths since ' \ 'the Summary is not linked to the StatePoint' raise ValueError(msg) From f5f26bada09bf910fcfab89348f4080d8c8ebafc Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 12:03:12 -0400 Subject: [PATCH 094/147] Initial implementation of scattering moments for ScatterMatrixXS --- openmc/mgxs/mgxs.py | 147 ++++++++++++++++++++++++++++++++------------ openmc/tallies.py | 2 +- src/input_xml.F90 | 21 ++----- src/state_point.F90 | 4 +- 4 files changed, 115 insertions(+), 59 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 33255de30..9c3b32657 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2,6 +2,7 @@ from __future__ import division from collections import Iterable, OrderedDict from numbers import Integral +import warnings import os import sys import copy @@ -1412,12 +1413,6 @@ class MGXS(object): else: df = self.xs_tally.get_pandas_dataframe(summary=summary) - # Remove the score column since it is homogeneous and redundant - if summary and 'distribcell' in self.domain_type: - df = df.drop('score', level=0, axis=1) - else: - df = df.drop('score', axis=1) - # Override energy groups bounds with indices all_groups = np.arange(self.num_groups, 0, -1, dtype=np.int) all_groups = np.repeat(all_groups, self.num_nuclides) @@ -1431,7 +1426,8 @@ class MGXS(object): df.rename(columns={'energyout low [MeV]': 'group out'}, inplace=True) - out_groups = np.tile(all_groups, df.shape[0] / all_groups.size) + out_groups = np.repeat(all_groups, self.xs_tally.num_scores) + out_groups = np.tile(out_groups, df.shape[0] / out_groups.size) df['group out'] = out_groups del df['energyout high [MeV]'] columns = ['group in', 'group out'] @@ -1843,6 +1839,8 @@ class ScatterMatrixXS(MGXS): ---------- correction : 'P0' or None Apply the P0 correction to scattering matrices if set to 'P0' + order : int + The highest order in the scattering matrix (default is 0) """ @@ -1852,6 +1850,7 @@ class ScatterMatrixXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'scatter matrix' self._correction = 'P0' + self._order = 0 def __deepcopy__(self, memo): clone = super(ScatterMatrixXS, self).__deepcopy__(memo) @@ -1862,6 +1861,10 @@ class ScatterMatrixXS(MGXS): def correction(self): return self._correction + @property + def order(self): + return self._order + @property def tallies(self): """Construct the OpenMC tallies needed to compute this cross section. @@ -1879,13 +1882,19 @@ class ScatterMatrixXS(MGXS): energy = openmc.Filter('energy', group_edges) energyout = openmc.Filter('energyout', group_edges) - # Create a list of scores for each Tally to be created - if self.correction == 'P0': - scores = ['flux', 'scatter', 'scatter-P1'] - filters = [[energy], [energy, energyout], [energyout]] - else: - scores = ['flux', 'scatter'] - filters = [[energy], [energy, energyout]] + # Create lists of scores, filters for each Tally to be created + scores = ['flux'] + filters = [[energy]] + + # Create separate tallies for each moment + for moment in range(self.order+1): + scores.append('scatter-{}'.format(moment)) + filters.append([energy, energyout]) + + # Append to the lists for the P0 approximation if needed + if self.correction == 'P0' and self.order == 0: + scores.append('scatter-1') + filters.append([energyout]) estimator = 'analog' keys = scores @@ -1899,16 +1908,25 @@ class ScatterMatrixXS(MGXS): def rxn_rate_tally(self): if self._rxn_rate_tally is None: + # If using P0 correction subtract scatter-P1 from the diagonal - if self.correction == 'P0': - scatter_p1 = self.tallies['scatter-P1'] - scatter_p1 = scatter_p1.get_slice(scores=['scatter-P1']) - energy_filter = self.tallies['scatter'].find_filter('energy') + if self.correction == 'P0' and self.order == 0: + scatter_p1 = self.tallies['scatter-1'] + scatter_p1 = scatter_p1.get_slice(scores=['scatter-1']) + energy_filter = self.tallies['scatter-0'].find_filter('energy') energy_filter = copy.deepcopy(energy_filter) scatter_p1 = scatter_p1.diagonalize_filter(energy_filter) - self._rxn_rate_tally = self.tallies['scatter'] - scatter_p1 + self._rxn_rate_tally = self.tallies['scatter-0'] - scatter_p1 + + # Merge all scattering moments into a single reaction rate Tally else: - self._rxn_rate_tally = self.tallies['scatter'] + rxn_rate_tally = self.tallies['scatter-0'] + for moment in range(1, self.order+1): + scatter_key = 'scatter-{}'.format(moment) + scatter_pn = self.tallies[scatter_key] + rxn_rate_tally = rxn_rate_tally.merge(scatter_pn) + + self._rxn_rate_tally = rxn_rate_tally self._rxn_rate_tally.sparse = self.sparse @@ -1917,8 +1935,27 @@ class ScatterMatrixXS(MGXS): @correction.setter def correction(self, correction): cv.check_value('correction', correction, ('P0', None)) + + if correction == 'P0' and self.order > 0: + msg = 'The P0 correction will be ignored since the scattering ' \ + 'order {} is greater than zero'.format(self.order) + warnings.warn(msg) + self._correction = correction + @order.setter + def order(self, order): + cv.check_type('order', order, Integral) + cv.check_greater_than('order', order, 0, equality=True) + + if self.correction == 'P0' and self.order > 0: + msg = 'The P0 correction will be ignored since the scattering ' \ + 'order {} is greater than zero'.format(self.order) + warnings.warn(msg, RuntimeWarning) + + self._order = order + + # FIXME: Add order param def get_slice(self, nuclides=[], in_groups=[], out_groups=[]): """Build a sliced ScatterMatrix for the specified nuclides and energy groups. @@ -1971,8 +2008,8 @@ class ScatterMatrixXS(MGXS): slice_xs.sparse = self.sparse return slice_xs - def get_xs(self, in_groups='all', out_groups='all', - subdomains='all', nuclides='all', xs_type='macro', + def get_xs(self, in_groups='all', out_groups='all', subdomains='all', + nuclides='all', moment='all', xs_type='macro', order_groups='increasing', value='mean'): """Returns an array of multi-group cross sections. @@ -1992,6 +2029,10 @@ class ScatterMatrixXS(MGXS): special string 'all' will return the cross sections for all nuclides in the spatial domain. The special string 'sum' will return the cross section summed over all nuclides. Defaults to 'all'. + moment : int or 'all' + The scattering matrix moment to return. All moments will be + returned if the moment is 'all' (default); otherwise, a specific + moment will be returned. xs_type: {'macro', 'micro'} Return the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. @@ -2044,6 +2085,15 @@ class ScatterMatrixXS(MGXS): filters.append('energyout') filter_bins.append((self.energy_groups.get_group_bounds(group),)) + # Construct CrossScore for requested scattering moment + if moment != 'all': + cv.check_type('moment', moment, Integral) + cv.check_greater_than('moment', moment, 0, equality=True) + cv.check_less_than('moment', moment, self.order, equality=True) + scores = [self.xs_tally.scores[moment]] + else: + scores = [] + # Construct a collection of the nuclides to retrieve from the xs tally if self.by_nuclide: if nuclides == 'all' or nuclides == 'sum' or nuclides == ['sum']: @@ -2056,10 +2106,10 @@ class ScatterMatrixXS(MGXS): # Use tally summation if user requested the sum for all nuclides if nuclides == 'sum' or nuclides == ['sum']: xs_tally = self.xs_tally.summation(nuclides=query_nuclides) - xs = xs_tally.get_values(filters=filters, + xs = xs_tally.get_values(scores=scores, filters=filters, filter_bins=filter_bins, value=value) else: - xs = self.xs_tally.get_values(filters=filters, + xs = self.xs_tally.get_values(scores=scores, filters=filters, filter_bins=filter_bins, nuclides=query_nuclides, value=value) @@ -2101,7 +2151,8 @@ class ScatterMatrixXS(MGXS): return xs - def print_xs(self, subdomains='all', nuclides='all', xs_type='macro'): + def print_xs(self, subdomains='all', nuclides='all', + xs_type='macro', moment=0): """Prints a string representation for the multi-group cross section. Parameters @@ -2118,6 +2169,8 @@ class ScatterMatrixXS(MGXS): xs_type: {'macro', 'micro'} Return the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + moment : int + The scattering moment to print (default is 0) """ @@ -2142,9 +2195,14 @@ class ScatterMatrixXS(MGXS): cv.check_value('xs_type', xs_type, ['macro', 'micro']) + if self.correction != 'P0': + rxn_type= '{0} (moment {1})'.format(self.rxn_type, moment) + else: + rxn_type = self.rxn_type + # Build header for string with type and domain info string = 'Multi-Group XS\n' - string += '{0: <16}=\t{1}\n'.format('\tReaction Type', self.rxn_type) + string += '{0: <16}=\t{1}\n'.format('\tReaction Type', rxn_type) string += '{0: <16}=\t{1}\n'.format('\tDomain Type', self.domain_type) string += '{0: <16}=\t{1}\n'.format('\tDomain ID', self.domain.id) @@ -2189,11 +2247,11 @@ class ScatterMatrixXS(MGXS): string += template.format('', in_group, out_group) average = \ self.get_xs([in_group], [out_group], - [subdomain], [nuclide], + [subdomain], [nuclide], moment=moment, xs_type=xs_type, value='mean') rel_err = \ self.get_xs([in_group], [out_group], - [subdomain], [nuclide], + [subdomain], [nuclide], moment=moment, xs_type=xs_type, value='rel_err') average = average.flatten()[0] rel_err = rel_err.flatten()[0] * 100. @@ -2206,6 +2264,8 @@ class ScatterMatrixXS(MGXS): print(string) +# FIXME: Add order property to Library + class NuScatterMatrixXS(ScatterMatrixXS): """A scattering production matrix multi-group cross section.""" @@ -2228,28 +2288,35 @@ class NuScatterMatrixXS(ScatterMatrixXS): # Instantiate tallies if they do not exist if self._tallies is None: - # Create the non-domain specific Filters for the Tallies group_edges = self.energy_groups.group_edges energy = openmc.Filter('energy', group_edges) energyout = openmc.Filter('energyout', group_edges) - # Create a list of scores for each Tally to be created - if self.correction == 'P0': - scores = ['flux', 'nu-scatter', 'scatter-P1'] - estimator = 'analog' - keys = ['flux', 'scatter', 'scatter-P1'] - filters = [[energy], [energy, energyout], [energyout]] - else: - scores = ['flux', 'nu-scatter'] - estimator = 'analog' - keys = ['flux', 'scatter'] - filters = [[energy], [energy, energyout]] + # Create lists of scores, filters for each Tally to be created + scores = ['flux'] + filters = [[energy]] + keys = ['flux'] + + # Create separate tallies for each moment + for moment in range(self.order+1): + scores.append('nu-scatter-{}'.format(moment)) + filters.append([energy, energyout]) + keys.append('scatter-{}'.format(moment)) + + # Append to the lists for the P0 approximation if needed + if self.correction == 'P0' and self.order == 0: + scores.append('scatter-1') + filters.append([energyout]) + keys.append('scatter-1') + + estimator = 'analog' # Intialize the Tallies self._create_tallies(scores, filters, keys, estimator) return self._tallies + class Chi(MGXS): """The fission spectrum.""" diff --git a/openmc/tallies.py b/openmc/tallies.py index 3a5a1f1e8..dc431ddf9 100644 --- a/openmc/tallies.py +++ b/openmc/tallies.py @@ -1637,7 +1637,7 @@ class Tally(object): for score in self.scores: if isinstance(score, (basestring, CrossScore)): - scores.append(score) + scores.append(str(score)) elif isinstance(score, AggregateScore): scores.append(score.name) column_name = '{0}(score)'.format(score.aggregate_op) diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 90c703d27..b69235690 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -3338,28 +3338,17 @@ contains case ('nu-scatter') t % score_bins(j) = SCORE_NU_SCATTER - - ! Set tally estimator to analog t % estimator = ESTIMATOR_ANALOG + case ('scatter-n') - if (n_order == 0) then - t % score_bins(j) = SCORE_SCATTER - else - t % score_bins(j) = SCORE_SCATTER_N - ! Set tally estimator to analog - t % estimator = ESTIMATOR_ANALOG - end if + t % score_bins(j) = SCORE_SCATTER_N t % moment_order(j) = n_order + t % estimator = ESTIMATOR_ANALOG case ('nu-scatter-n') - ! Set tally estimator to analog - t % estimator = ESTIMATOR_ANALOG - if (n_order == 0) then - t % score_bins(j) = SCORE_NU_SCATTER - else - t % score_bins(j) = SCORE_NU_SCATTER_N - end if + t % score_bins(j) = SCORE_NU_SCATTER_N t % moment_order(j) = n_order + t % estimator = ESTIMATOR_ANALOG case ('scatter-pn') t % estimator = ESTIMATOR_ANALOG diff --git a/src/state_point.F90 b/src/state_point.F90 index 4348ad331..10979ee9e 100644 --- a/src/state_point.F90 +++ b/src/state_point.F90 @@ -330,11 +330,11 @@ contains MOMENT_LOOP: do j = 1, tally % n_user_score_bins select case(tally % score_bins(k)) case (SCORE_SCATTER_N, SCORE_NU_SCATTER_N) - str_array(k) = 'P' // trim(to_str(tally % moment_order(k))) + str_array(k) = trim(to_str(tally % moment_order(k))) k = k + 1 case (SCORE_SCATTER_PN, SCORE_NU_SCATTER_PN) do n_order = 0, tally % moment_order(k) - str_array(k) = 'P' // trim(to_str(n_order)) + str_array(k) = trim(to_str(n_order)) k = k + 1 end do case (SCORE_SCATTER_YN, SCORE_NU_SCATTER_YN, SCORE_FLUX_YN, & From 2dae4f9a69bac6c6e34c610a6f5dc27992eb91e2 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 12:17:55 -0400 Subject: [PATCH 095/147] Added legendre moment parameter to Pandas DF construction for ScatterMatrixXS --- openmc/mgxs/mgxs.py | 67 +++++++++++++++++++++++++++++++++++++++++---- 1 file changed, 62 insertions(+), 5 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 9c3b32657..e5ba9b4ac 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1833,14 +1833,15 @@ class NuScatterXS(MGXS): class ScatterMatrixXS(MGXS): - """A scattering matrix multi-group cross section. + """A scattering matrix multi-group cross section for one or more Legendre + moments. Attributes ---------- correction : 'P0' or None Apply the P0 correction to scattering matrices if set to 'P0' order : int - The highest order in the scattering matrix (default is 0) + The highest legendre moment in the scattering matrix (default is 0) """ @@ -1869,8 +1870,8 @@ class ScatterMatrixXS(MGXS): def tallies(self): """Construct the OpenMC tallies needed to compute this cross section. - This method constructs three analog tallies to compute the 'flux', - 'scatter' and 'scatter-P1' reaction rates in the spatial domain and + This method constructs three analog tallies to compute the 'flux' + and Legendre scattering moment reaction rates in the spatial domain and energy groups of interest. """ @@ -1955,7 +1956,6 @@ class ScatterMatrixXS(MGXS): self._order = order - # FIXME: Add order param def get_slice(self, nuclides=[], in_groups=[], out_groups=[]): """Build a sliced ScatterMatrix for the specified nuclides and energy groups. @@ -2151,6 +2151,63 @@ class ScatterMatrixXS(MGXS): return xs + def get_pandas_dataframe(self, groups='all', nuclides='all', moment='all', + xs_type='macro', summary=None): + """Build a Pandas DataFrame for the MGXS data. + + This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but + renames the columns with terminology appropriate for cross section data. + + Parameters + ---------- + groups : Iterable of Integral or 'all' + Energy groups of interest. Defaults to 'all'. + nuclides : Iterable of str or 'all' or 'sum' + The nuclides of the cross-sections to include in the dataframe. This + may be a list of nuclide name strings (e.g., ['U-235', 'U-238']). + The special string 'all' will include the cross sections for all + nuclides in the spatial domain. The special string 'sum' will + include the cross sections summed over all nuclides. Defaults + to 'all'. + moment : int or 'all' + The scattering matrix moment to return. All moments will be + returned if the moment is 'all' (default); otherwise, a specific + moment will be returned. + xs_type: {'macro', 'micro'} + Return macro or micro cross section in units of cm^-1 or barns. + Defaults to 'macro'. + summary : None or openmc.Summary + An optional Summary object to be used to construct columns for + distribcell tally filters (default is None). The geometric + information in the Summary object is embedded into a multi-index + column with a geometric "path" to each distribcell intance. + NOTE: This option requires the OpenCG Python package. + + Returns + ------- + pandas.DataFrame + A Pandas DataFrame for the cross section data. + + Raises + ------ + ValueError + When this method is called before the multi-group cross section is + computed from tally data. + + """ + + df = super(ScatterMatrixXS, self).get_pandas_dataframe( + groups, nuclides, xs_type, summary) + + # Select rows corresponding to requested scattering moment + if moment != 'all': + cv.check_type('moment', moment, Integral) + cv.check_greater_than('moment', moment, 0, equality=True) + cv.check_less_than('moment', moment, self.order, equality=True) + df = df[df['score'] == str(self.xs_tally.scores[moment])] + + return df + def print_xs(self, subdomains='all', nuclides='all', xs_type='macro', moment=0): """Prints a string representation for the multi-group cross section. From 8f6961fec514e1c8bacd1d5f6834f3c8e25f618e Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 12:48:43 -0400 Subject: [PATCH 096/147] Added legendre moment order to get_slice method for ScatterMatrixXS --- openmc/mgxs/library.py | 30 ++++++++++++++----- openmc/mgxs/mgxs.py | 66 ++++++++++++++++++++++++++---------------- 2 files changed, 64 insertions(+), 32 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index f3bf2018d..a7defba5d 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -2,6 +2,7 @@ import sys import os import copy import pickle +import warnings from numbers import Integral from collections import OrderedDict @@ -57,6 +58,8 @@ class Library(object): The spatial domain(s) for which MGXS in the Library are computed correction : {'P0', None} Apply the P0 correction to scattering matrices if set to 'P0' + legendre_order : int + The highest legendre moments in the scattering matrices (default is 0) energy_groups : openmc.mgxs.EnergyGroups Energy group structure for energy condensation tally_trigger : openmc.Trigger @@ -89,8 +92,9 @@ class Library(object): self._mgxs_types = [] self._domain_type = None self._domains = 'all' - self._correction = 'P0' self._energy_groups = None + self._correction = 'P0' + self._legendre_order = 0 self._tally_trigger = None self._all_mgxs = OrderedDict() self._sp_filename = None @@ -118,6 +122,7 @@ class Library(object): clone._domain_type = self.domain_type clone._domains = copy.deepcopy(self.domains) clone._correction = self.correction + clone._legendre_order = self.legendre_order clone._energy_groups = copy.deepcopy(self.energy_groups, memo) clone._tally_trigger = copy.deepcopy(self.tally_trigger, memo) clone._all_mgxs = copy.deepcopy(self.all_mgxs) @@ -185,13 +190,17 @@ class Library(object): else: return self._domains + @property + def energy_groups(self): + return self._energy_groups + @property def correction(self): return self._correction @property - def energy_groups(self): - return self._energy_groups + def legendre_order(self): + return self._legendre_order @property def tally_trigger(self): @@ -280,15 +289,21 @@ class Library(object): self._domains = domains + @energy_groups.setter + def energy_groups(self, energy_groups): + cv.check_type('energy groups', energy_groups, openmc.mgxs.EnergyGroups) + self._energy_groups = energy_groups + @correction.setter def correction(self, correction): cv.check_value('correction', correction, ('P0', None)) self._correction = correction - @energy_groups.setter - def energy_groups(self, energy_groups): - cv.check_type('energy groups', energy_groups, openmc.mgxs.EnergyGroups) - self._energy_groups = energy_groups + @legendre_order.setter + def legendre_order(self, legendre_order): + cv.check_type('legendre_order', legendre_order, Integral) + cv.check_greater_than('legendre_order', legendre_order, 0, equality=True) + self._legendre_order = legendre_order @tally_trigger.setter def tally_trigger(self, tally_trigger): @@ -344,6 +359,7 @@ class Library(object): # Specify whether to use a transport ('P0') correction if isinstance(mgxs, openmc.mgxs.ScatterMatrixXS): mgxs.correction = self.correction + mgxs.legendre_order = self.legendre_order self.all_mgxs[domain.id][mgxs_type] = mgxs diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index e5ba9b4ac..9a60d2493 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1840,7 +1840,7 @@ class ScatterMatrixXS(MGXS): ---------- correction : 'P0' or None Apply the P0 correction to scattering matrices if set to 'P0' - order : int + legendre_order : int The highest legendre moment in the scattering matrix (default is 0) """ @@ -1851,11 +1851,12 @@ class ScatterMatrixXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'scatter matrix' self._correction = 'P0' - self._order = 0 + self._legendre_order = 0 def __deepcopy__(self, memo): clone = super(ScatterMatrixXS, self).__deepcopy__(memo) clone._correction = self.correction + clone._legendre_order = self.legendre_order return clone @property @@ -1863,8 +1864,8 @@ class ScatterMatrixXS(MGXS): return self._correction @property - def order(self): - return self._order + def legendre_order(self): + return self._legendre_order @property def tallies(self): @@ -1888,12 +1889,12 @@ class ScatterMatrixXS(MGXS): filters = [[energy]] # Create separate tallies for each moment - for moment in range(self.order+1): + for moment in range(self.legendre_order+1): scores.append('scatter-{}'.format(moment)) filters.append([energy, energyout]) # Append to the lists for the P0 approximation if needed - if self.correction == 'P0' and self.order == 0: + if self.correction == 'P0' and self.legendre_order == 0: scores.append('scatter-1') filters.append([energyout]) @@ -1911,7 +1912,7 @@ class ScatterMatrixXS(MGXS): if self._rxn_rate_tally is None: # If using P0 correction subtract scatter-P1 from the diagonal - if self.correction == 'P0' and self.order == 0: + if self.correction == 'P0' and self.legendre_order == 0: scatter_p1 = self.tallies['scatter-1'] scatter_p1 = scatter_p1.get_slice(scores=['scatter-1']) energy_filter = self.tallies['scatter-0'].find_filter('energy') @@ -1922,7 +1923,7 @@ class ScatterMatrixXS(MGXS): # Merge all scattering moments into a single reaction rate Tally else: rxn_rate_tally = self.tallies['scatter-0'] - for moment in range(1, self.order+1): + for moment in range(1, self.legendre_order+1): scatter_key = 'scatter-{}'.format(moment) scatter_pn = self.tallies[scatter_key] rxn_rate_tally = rxn_rate_tally.merge(scatter_pn) @@ -1937,26 +1938,27 @@ class ScatterMatrixXS(MGXS): def correction(self, correction): cv.check_value('correction', correction, ('P0', None)) - if correction == 'P0' and self.order > 0: + if correction == 'P0' and self.legendre_order > 0: msg = 'The P0 correction will be ignored since the scattering ' \ - 'order {} is greater than zero'.format(self.order) + 'order {} is greater than zero'.format(self.legendre_order) warnings.warn(msg) self._correction = correction - @order.setter - def order(self, order): - cv.check_type('order', order, Integral) - cv.check_greater_than('order', order, 0, equality=True) + @legendre_order.setter + def legendre_order(self, legendre_order): + cv.check_type('legendre_order', legendre_order, Integral) + cv.check_greater_than('legendre_order', legendre_order, 0, equality=True) - if self.correction == 'P0' and self.order > 0: + if self.correction == 'P0' and legendre_order > 0: msg = 'The P0 correction will be ignored since the scattering ' \ - 'order {} is greater than zero'.format(self.order) + 'order {} is greater than zero'.format(self.legendre_order) warnings.warn(msg, RuntimeWarning) - self._order = order + self._legendre_order = legendre_order - def get_slice(self, nuclides=[], in_groups=[], out_groups=[]): + def get_slice(self, nuclides=[], in_groups=[], out_groups=[], + legendre_order='same'): """Build a sliced ScatterMatrix for the specified nuclides and energy groups. @@ -1976,6 +1978,12 @@ class ScatterMatrixXS(MGXS): out_groups : list of int A list of outgoing energy group indices starting at 1 for the high energies (e.g., [1, 2, 3]; default is []) + legendre_order : int or 'same' + The highest Legendre moment in the sliced MGXS. If order is 'same' + then the sliced MGXS will have the same Legendre moments as the + original MGXS (default). If order is an integer less than the + original MGXS' order, then only those Legendre moments up to that + order will be included in the sliced MGXS. Returns ------- @@ -1990,6 +1998,16 @@ class ScatterMatrixXS(MGXS): slice_xs._rxn_rate_tally = None slice_xs._xs_tally = None + # Slice the Legendre order if needed + if legendre_order != 'same': + cv.check_type('legendre_order', legendre_order, Integral) + cv.check_less_than('legendre_order', legendre_order, + self.legendre_order, equality=True) + slice_xs.legendre_order = legendre_order + + for moment in range(legendre_order+1, self.legendre_order+1): + del slice_xs.tallies['scatter-{}'.format(moment)] + # Slice outgoing energy groups if needed if len(out_groups) != 0: filter_bins = [] @@ -2089,7 +2107,7 @@ class ScatterMatrixXS(MGXS): if moment != 'all': cv.check_type('moment', moment, Integral) cv.check_greater_than('moment', moment, 0, equality=True) - cv.check_less_than('moment', moment, self.order, equality=True) + cv.check_less_than('moment', moment, 10, equality=True) scores = [self.xs_tally.scores[moment]] else: scores = [] @@ -2203,7 +2221,7 @@ class ScatterMatrixXS(MGXS): if moment != 'all': cv.check_type('moment', moment, Integral) cv.check_greater_than('moment', moment, 0, equality=True) - cv.check_less_than('moment', moment, self.order, equality=True) + cv.check_less_than('moment', moment, 10, equality=True) df = df[df['score'] == str(self.xs_tally.scores[moment])] return df @@ -2253,7 +2271,7 @@ class ScatterMatrixXS(MGXS): cv.check_value('xs_type', xs_type, ['macro', 'micro']) if self.correction != 'P0': - rxn_type= '{0} (moment {1})'.format(self.rxn_type, moment) + rxn_type= '{0} (P{1})'.format(self.rxn_type, moment) else: rxn_type = self.rxn_type @@ -2321,8 +2339,6 @@ class ScatterMatrixXS(MGXS): print(string) -# FIXME: Add order property to Library - class NuScatterMatrixXS(ScatterMatrixXS): """A scattering production matrix multi-group cross section.""" @@ -2355,13 +2371,13 @@ class NuScatterMatrixXS(ScatterMatrixXS): keys = ['flux'] # Create separate tallies for each moment - for moment in range(self.order+1): + for moment in range(self.legendre_order+1): scores.append('nu-scatter-{}'.format(moment)) filters.append([energy, energyout]) keys.append('scatter-{}'.format(moment)) # Append to the lists for the P0 approximation if needed - if self.correction == 'P0' and self.order == 0: + if self.correction == 'P0' and self.legendre_order == 0: scores.append('scatter-1') filters.append([energyout]) keys.append('scatter-1') From 41e8f83c603d5a20d735da3e09212bec94666a8d Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 13:17:57 -0400 Subject: [PATCH 097/147] Hard over-ride of ScatterMatrixXS correction with higher order legendre moments --- openmc/mgxs/mgxs.py | 1 + 1 file changed, 1 insertion(+) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 7405b71fd..d8b80cc43 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1959,6 +1959,7 @@ class ScatterMatrixXS(MGXS): msg = 'The P0 correction will be ignored since the scattering ' \ 'order {} is greater than zero'.format(self.legendre_order) warnings.warn(msg, RuntimeWarning) + self.correction = None self._legendre_order = legendre_order From 9e5460321ffe1f4dd0966c41ee8f21b27857a0e6 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 13:26:42 -0400 Subject: [PATCH 098/147] Updated MGXS test results to include Pandas DF column for scores --- openmc/mgxs/mgxs.py | 16 +- .../inputs_true.dat | 2 +- .../results_true.dat | 98 +- .../inputs_true.dat | 2 +- .../results_true.dat | 10 +- tests/test_mgxs_library_hdf5/inputs_true.dat | 2 +- .../inputs_true.dat | 2 +- .../results_true.dat | 242 +- .../inputs_true.dat | 2 +- .../results_true.dat | 3942 ++++++++--------- 10 files changed, 2156 insertions(+), 2162 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index d8b80cc43..051dd3cf1 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1534,7 +1534,7 @@ class TransportXS(MGXS): """Construct the OpenMC tallies needed to compute this cross section. This method constructs three analog tallies to compute the 'flux', - 'total' and 'scatter-P1' reaction rates in the spatial domain and + 'total' and 'scatter-1' reaction rates in the spatial domain and energy groups of interest. """ @@ -1543,7 +1543,7 @@ class TransportXS(MGXS): if self._tallies is None: # Create a list of scores for each Tally to be created - scores = ['flux', 'total', 'scatter-P1'] + scores = ['flux', 'total', 'scatter-1'] estimator = 'analog' keys = scores @@ -1561,15 +1561,9 @@ class TransportXS(MGXS): @property def rxn_rate_tally(self): if self._rxn_rate_tally is None: - scatter_p1 = copy.deepcopy(self.tallies['scatter-P1']) - - # Use tally slicing to remove scatter-P0 data from scatter-P1 tally - self.tallies['scatter-P1'] = \ - scatter_p1.get_slice(scores=['scatter-P1']) - - self.tallies['scatter-P1'].filters[-1].type = 'energy' + self.tallies['scatter-1'].filters[-1].type = 'energy' self._rxn_rate_tally = \ - self.tallies['total'] - self.tallies['scatter-P1'] + self.tallies['total'] - self.tallies['scatter-1'] self._rxn_rate_tally.sparse = self.sparse return self._rxn_rate_tally @@ -1916,7 +1910,7 @@ class ScatterMatrixXS(MGXS): if self._rxn_rate_tally is None: - # If using P0 correction subtract scatter-P1 from the diagonal + # If using P0 correction subtract scatter-1 from the diagonal if self.correction == 'P0' and self.legendre_order == 0: scatter_p1 = self.tallies['scatter-1'] scatter_p1 = scatter_p1.get_slice(scores=['scatter-1']) diff --git a/tests/test_mgxs_library_condense/inputs_true.dat b/tests/test_mgxs_library_condense/inputs_true.dat index 51fc95c60..708ec114e 100644 --- a/tests/test_mgxs_library_condense/inputs_true.dat +++ b/tests/test_mgxs_library_condense/inputs_true.dat @@ -1 +1 @@ -3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file +e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 438215372..7e8a49673 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,49 +1,49 @@ - material group in nuclide mean std. dev. -0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. -0 1 1 total 0.076425 0.003691 material group in group out nuclide mean std. dev. -0 1 1 1 total 0.345643 0.021487 material group out nuclide mean std. dev. -0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. -0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 2 1 1 total 0.241262 0.00841 material group out nuclide mean std. dev. -0 2 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 3 1 1 total 0.393462 0.033646 material group out nuclide mean std. dev. -0 3 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 4 1 1 total 0.371473 0.071226 material group out nuclide mean std. dev. -0 4 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 5 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 6 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 7 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 8 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 9 1 1 total 0.600536 0.748875 material group out nuclide mean std. dev. -0 9 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 10 1 1 total 0.235515 0.613974 material group out nuclide mean std. dev. -0 10 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 11 1 1 total 0.491857 0.715554 material group out nuclide mean std. dev. -0 11 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 12 1 1 total 0.723265 0.808231 material group out nuclide mean std. dev. -0 12 1 total 0.0 0.0 \ No newline at end of file + material group in nuclide score mean std. dev. +0 1 1 total ((total - scatter-1) / flux) 4.12e-01 2.36e-02 material group in nuclide score mean std. dev. +0 1 1 total (nu-fission / flux) 7.64e-02 3.69e-03 material group in group out nuclide score mean std. dev. +0 1 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.46e-01 2.15e-02 material group out nuclide score mean std. dev. +0 1 1 total nu-fission 1.00e+00 5.53e-02 material group in nuclide score mean std. dev. +0 2 1 total ((total - scatter-1) / flux) 2.41e-01 8.41e-03 material group in nuclide score mean std. dev. +0 2 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 2 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.41e-01 8.41e-03 material group out nuclide score mean std. dev. +0 2 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 3 1 total ((total - scatter-1) / flux) 4.00e-01 3.47e-02 material group in nuclide score mean std. dev. +0 3 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 3 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.93e-01 3.36e-02 material group out nuclide score mean std. dev. +0 3 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 4 1 total ((total - scatter-1) / flux) 3.77e-01 7.29e-02 material group in nuclide score mean std. dev. +0 4 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 4 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.71e-01 7.12e-02 material group out nuclide score mean std. dev. +0 4 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 5 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 5 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 5 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +0 5 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 6 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 6 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 6 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +0 6 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 7 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 7 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 7 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +0 7 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 8 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 8 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 8 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +0 8 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 9 1 total ((total - scatter-1) / flux) 6.01e-01 7.49e-01 material group in nuclide score mean std. dev. +0 9 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 9 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.01e-01 7.49e-01 material group out nuclide score mean std. dev. +0 9 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 10 1 total ((total - scatter-1) / flux) 2.36e-01 6.14e-01 material group in nuclide score mean std. dev. +0 10 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 10 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.36e-01 6.14e-01 material group out nuclide score mean std. dev. +0 10 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 11 1 total ((total - scatter-1) / flux) 5.10e-01 7.42e-01 material group in nuclide score mean std. dev. +0 11 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 11 1 1 total ((nu-scatter-0 - scatter-1) / flux) 4.92e-01 7.16e-01 material group out nuclide score mean std. dev. +0 11 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +0 12 1 total ((total - scatter-1) / flux) 7.38e-01 8.26e-01 material group in nuclide score mean std. dev. +0 12 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +0 12 1 1 total ((nu-scatter-0 - scatter-1) / flux) 7.23e-01 8.08e-01 material group out nuclide score mean std. dev. +0 12 1 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/inputs_true.dat b/tests/test_mgxs_library_distribcell/inputs_true.dat index 78ffa3faf..4ab730274 100644 --- a/tests/test_mgxs_library_distribcell/inputs_true.dat +++ b/tests/test_mgxs_library_distribcell/inputs_true.dat @@ -1 +1 @@ -2c078f650fed5fc241f42b2d7404fb7fae59d782102fad66b4cd2c8a4b1f266d64e8ce1ec0556117c2a2b1fe49aa583f340dc43df3ddc9320557aa97bb554c05 \ No newline at end of file +aadb1e94492741c091bff4b5e17634ee327c718fc9fd1f27aa22fe8406fb70f732750dfdceb30eb40b5e4f406061bea6bd5235ba613c3c81009f5857a9051728 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index 0d5c7c7b4..a23417d92 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,5 +1,5 @@ - avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.695166 0.510606 avg(distribcell) group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 \ No newline at end of file + avg(distribcell) group in nuclide score mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total ((total - scatter-1) / flux) 7.19e-01 5.21e-01 avg(distribcell) group in nuclide score mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total (nu-fission / flux) 0.00e+00 0.00e+00 avg(distribcell) group in group out nuclide score mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.95e-01 5.11e-01 avg(distribcell) group out nuclide score mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file diff --git a/tests/test_mgxs_library_hdf5/inputs_true.dat b/tests/test_mgxs_library_hdf5/inputs_true.dat index 51fc95c60..708ec114e 100644 --- a/tests/test_mgxs_library_hdf5/inputs_true.dat +++ b/tests/test_mgxs_library_hdf5/inputs_true.dat @@ -1 +1 @@ -3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file +e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/inputs_true.dat b/tests/test_mgxs_library_no_nuclides/inputs_true.dat index 51fc95c60..708ec114e 100644 --- a/tests/test_mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_no_nuclides/inputs_true.dat @@ -1 +1 @@ -3e7b4ee62e0a53b92d4241f33493786532934f20ebcf47d92825bb1ee2f67c52aa8e7832cf28a9911221f802da205fba2b23c7228899780089da69e21042743c \ No newline at end of file +e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 442b8ac7b..c279653e5 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -1,121 +1,121 @@ - material group in nuclide mean std. dev. -1 1 1 total 0.372745 0.024269 -0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. -1 1 1 total 0.021789 0.001182 -0 1 2 total 0.714077 0.040552 material group in group out nuclide mean std. dev. -3 1 1 1 total 0.337397 0.023039 -2 1 1 2 total 0.001559 0.000510 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.422051 0.021617 material group out nuclide mean std. dev. -1 1 1 total 1.0 0.055333 -0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev. -1 2 1 total 0.237254 0.008184 -0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 2 1 1 total 0.237254 0.008184 -2 2 1 2 total 0.000000 0.000000 -1 2 2 1 total 0.000000 0.000000 -0 2 2 2 total 0.285930 0.048796 material group out nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 3 1 total 0.286906 0.027401 -0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 3 1 1 total 0.259937 0.026115 -2 3 1 2 total 0.026187 0.001665 -1 3 2 1 total 0.000000 0.000000 -0 3 2 2 total 1.359521 0.258505 material group out nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 4 1 total 0.242447 0.061031 -0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. -1 4 1 total 0.0 0.0 -0 4 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 4 1 1 total 0.217930 0.058565 -2 4 1 2 total 0.023662 0.003083 -1 4 2 1 total 0.000000 0.000000 -0 4 2 2 total 1.215074 0.381025 material group out nuclide mean std. dev. -1 4 1 total 0.0 0.0 -0 4 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 5 1 1 total 0.0 0.0 -2 5 1 2 total 0.0 0.0 -1 5 2 1 total 0.0 0.0 -0 5 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 6 1 1 total 0.0 0.0 -2 6 1 2 total 0.0 0.0 -1 6 2 1 total 0.0 0.0 -0 6 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 7 1 1 total 0.0 0.0 -2 7 1 2 total 0.0 0.0 -1 7 2 1 total 0.0 0.0 -0 7 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 8 1 1 total 0.0 0.0 -2 8 1 2 total 0.0 0.0 -1 8 2 1 total 0.0 0.0 -0 8 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 9 1 total 0.600536 0.748875 -0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 9 1 total 0.0 0.0 -0 9 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 9 1 1 total 0.600536 0.748875 -2 9 1 2 total 0.000000 0.000000 -1 9 2 1 total 0.000000 0.000000 -0 9 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. -1 9 1 total 0.0 0.0 -0 9 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 10 1 total 0.235515 0.613974 -0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 10 1 total 0.0 0.0 -0 10 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 10 1 1 total 0.235515 0.613974 -2 10 1 2 total 0.000000 0.000000 -1 10 2 1 total 0.000000 0.000000 -0 10 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. -1 10 1 total 0.0 0.0 -0 10 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 11 1 total 0.186324 0.632129 -0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. -1 11 1 total 0.0 0.0 -0 11 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 11 1 1 total 0.154449 0.597686 -2 11 1 2 total 0.031875 0.045078 -1 11 2 1 total 0.000000 0.000000 -0 11 2 2 total 0.903085 1.532144 material group out nuclide mean std. dev. -1 11 1 total 0.0 0.0 -0 11 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 12 1 total 0.213292 0.271444 -0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. -1 12 1 total 0.0 0.0 -0 12 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 12 1 1 total 0.186052 0.257633 -2 12 1 2 total 0.027240 0.029555 -1 12 2 1 total 0.000000 0.000000 -0 12 2 2 total 1.357118 2.089846 material group out nuclide mean std. dev. -1 12 1 total 0.0 0.0 -0 12 2 total 0.0 0.0 \ No newline at end of file + material group in nuclide score mean std. dev. +1 1 1 total ((total - scatter-1) / flux) 3.73e-01 2.43e-02 +0 1 2 total ((total - scatter-1) / flux) 8.62e-01 3.23e-02 material group in nuclide score mean std. dev. +1 1 1 total (nu-fission / flux) 2.18e-02 1.18e-03 +0 1 2 total (nu-fission / flux) 7.14e-01 4.06e-02 material group in group out nuclide score mean std. dev. +3 1 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.37e-01 2.30e-02 +2 1 1 2 total ((nu-scatter-0 - scatter-1) / flux) 1.56e-03 5.10e-04 +1 1 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 1 2 2 total ((nu-scatter-0 - scatter-1) / flux) 4.22e-01 2.16e-02 material group out nuclide score mean std. dev. +1 1 1 total nu-fission 1.00e+00 5.53e-02 +0 1 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 2 1 total ((total - scatter-1) / flux) 2.37e-01 8.18e-03 +0 2 2 total ((total - scatter-1) / flux) 2.86e-01 4.88e-02 material group in nuclide score mean std. dev. +1 2 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 2 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 2 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.37e-01 8.18e-03 +2 2 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 2 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 2 2 2 total ((nu-scatter-0 - scatter-1) / flux) 2.86e-01 4.88e-02 material group out nuclide score mean std. dev. +1 2 1 total nu-fission 0.00e+00 0.00e+00 +0 2 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 3 1 total ((total - scatter-1) / flux) 2.87e-01 2.74e-02 +0 3 2 total ((total - scatter-1) / flux) 1.42e+00 2.65e-01 material group in nuclide score mean std. dev. +1 3 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 3 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 3 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.60e-01 2.61e-02 +2 3 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.62e-02 1.66e-03 +1 3 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 3 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.36e+00 2.59e-01 material group out nuclide score mean std. dev. +1 3 1 total nu-fission 0.00e+00 0.00e+00 +0 3 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 4 1 total ((total - scatter-1) / flux) 2.42e-01 6.10e-02 +0 4 2 total ((total - scatter-1) / flux) 1.25e+00 3.88e-01 material group in nuclide score mean std. dev. +1 4 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 4 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 4 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.18e-01 5.86e-02 +2 4 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.37e-02 3.08e-03 +1 4 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 4 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.22e+00 3.81e-01 material group out nuclide score mean std. dev. +1 4 1 total nu-fission 0.00e+00 0.00e+00 +0 4 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 5 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 5 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 5 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 5 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 5 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 5 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 5 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 5 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 5 1 total nu-fission 0.00e+00 0.00e+00 +0 5 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 6 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 6 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 6 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 6 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 6 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 6 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 6 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 6 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 6 1 total nu-fission 0.00e+00 0.00e+00 +0 6 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 7 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 7 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 7 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 7 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 7 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 7 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 7 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 7 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 7 1 total nu-fission 0.00e+00 0.00e+00 +0 7 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 8 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 8 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 8 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 8 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 8 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 8 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 8 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 8 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 8 1 total nu-fission 0.00e+00 0.00e+00 +0 8 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 9 1 total ((total - scatter-1) / flux) 6.01e-01 7.49e-01 +0 9 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 9 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 9 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 9 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.01e-01 7.49e-01 +2 9 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 9 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 9 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 9 1 total nu-fission 0.00e+00 0.00e+00 +0 9 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 10 1 total ((total - scatter-1) / flux) 2.36e-01 6.14e-01 +0 10 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 10 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 10 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 10 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.36e-01 6.14e-01 +2 10 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 10 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 10 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +1 10 1 total nu-fission 0.00e+00 0.00e+00 +0 10 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 11 1 total ((total - scatter-1) / flux) 1.86e-01 6.32e-01 +0 11 2 total ((total - scatter-1) / flux) 9.46e-01 1.59e+00 material group in nuclide score mean std. dev. +1 11 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 11 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 11 1 1 total ((nu-scatter-0 - scatter-1) / flux) 1.54e-01 5.98e-01 +2 11 1 2 total ((nu-scatter-0 - scatter-1) / flux) 3.19e-02 4.51e-02 +1 11 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 11 2 2 total ((nu-scatter-0 - scatter-1) / flux) 9.03e-01 1.53e+00 material group out nuclide score mean std. dev. +1 11 1 total nu-fission 0.00e+00 0.00e+00 +0 11 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +1 12 1 total ((total - scatter-1) / flux) 2.13e-01 2.71e-01 +0 12 2 total ((total - scatter-1) / flux) 1.39e+00 2.14e+00 material group in nuclide score mean std. dev. +1 12 1 total (nu-fission / flux) 0.00e+00 0.00e+00 +0 12 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +3 12 1 1 total ((nu-scatter-0 - scatter-1) / flux) 1.86e-01 2.58e-01 +2 12 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.72e-02 2.96e-02 +1 12 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 12 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.36e+00 2.09e+00 material group out nuclide score mean std. dev. +1 12 1 total nu-fission 0.00e+00 0.00e+00 +0 12 2 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/inputs_true.dat b/tests/test_mgxs_library_nuclides/inputs_true.dat index 9436f03a0..5b7a83037 100644 --- a/tests/test_mgxs_library_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_nuclides/inputs_true.dat @@ -1 +1 @@ -b035f783fa75ada619b0a58675913e318fef94e519c85cae6982f650d7655cb130f625572fde2058e005b490359180cb9d1e1095f5d35d41c9a0f8ff6e0dc3c1 \ No newline at end of file +f1c203fb7f0b141ee608d7bb9223aa5f7ab84966b6a80525879df730d19179f6c6a1a4bc7038d84e6b366b360f43a1ca17a0af8d02f96eb23e53b93a2445380e \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index 145521964..99582fa7d 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -1,1971 +1,1971 @@ - material group in nuclide mean std. dev. -34 1 1 U-234 0.000173 0.000173 -35 1 1 U-235 0.010677 0.001889 -36 1 1 U-236 0.002390 0.001055 -37 1 1 U-238 0.213680 0.013272 -38 1 1 Np-237 0.000000 0.000000 -39 1 1 Pu-238 0.000000 0.000000 -40 1 1 Pu-239 0.002911 0.000639 -41 1 1 Pu-240 0.004426 0.000806 -42 1 1 Pu-241 0.000690 0.000387 -43 1 1 Pu-242 0.000000 0.000000 -44 1 1 Am-241 0.000173 0.000173 -45 1 1 Am-242m 0.000000 0.000000 -46 1 1 Am-243 0.000000 0.000000 -47 1 1 Cm-242 0.000000 0.000000 -48 1 1 Cm-243 0.000000 0.000000 -49 1 1 Cm-244 0.000000 0.000000 -50 1 1 Cm-245 0.000000 0.000000 -51 1 1 Mo-95 0.000000 0.000000 -52 1 1 Tc-99 0.000173 0.000173 -53 1 1 Ru-101 0.000238 0.000254 -54 1 1 Ru-103 0.000002 0.000243 -55 1 1 Ag-109 0.000000 0.000000 -56 1 1 Xe-135 0.000000 0.000000 -57 1 1 Cs-133 0.000347 0.000213 -58 1 1 Nd-143 0.000447 0.000292 -59 1 1 Nd-145 0.000564 0.000294 -60 1 1 Sm-147 0.000000 0.000000 -61 1 1 Sm-149 0.000000 0.000000 -62 1 1 Sm-150 0.000472 0.000239 -63 1 1 Sm-151 0.000000 0.000000 -64 1 1 Sm-152 0.000492 0.000352 -65 1 1 Eu-153 0.000173 0.000173 -66 1 1 Gd-155 0.000000 0.000000 -67 1 1 O-16 0.134715 0.009801 -0 1 2 U-234 0.000000 0.000000 -1 1 2 U-235 0.199907 0.007776 -2 1 2 U-236 0.001501 0.002037 -3 1 2 U-238 0.255355 0.029743 -4 1 2 Np-237 0.000000 0.000000 -5 1 2 Pu-238 0.000000 0.000000 -6 1 2 Pu-239 0.160378 0.011366 -7 1 2 Pu-240 0.007920 0.003710 -8 1 2 Pu-241 0.017820 0.003733 -9 1 2 Pu-242 0.000000 0.000000 -10 1 2 Am-241 0.000000 0.000000 -11 1 2 Am-242m 0.000000 0.000000 -12 1 2 Am-243 0.000000 0.000000 -13 1 2 Cm-242 0.000000 0.000000 -14 1 2 Cm-243 0.000000 0.000000 -15 1 2 Cm-244 0.000000 0.000000 -16 1 2 Cm-245 0.000000 0.000000 -17 1 2 Mo-95 0.000000 0.000000 -18 1 2 Tc-99 0.000000 0.000000 -19 1 2 Ru-101 0.000000 0.000000 -20 1 2 Ru-103 0.000000 0.000000 -21 1 2 Ag-109 0.000000 0.000000 -22 1 2 Xe-135 0.013860 0.003976 -23 1 2 Cs-133 0.000000 0.000000 -24 1 2 Nd-143 0.003960 0.002427 -25 1 2 Nd-145 0.000000 0.000000 -26 1 2 Sm-147 0.000000 0.000000 -27 1 2 Sm-149 0.001980 0.001981 -28 1 2 Sm-150 0.000000 0.000000 -29 1 2 Sm-151 0.001980 0.001981 -30 1 2 Sm-152 0.000000 0.000000 -31 1 2 Eu-153 0.000000 0.000000 -32 1 2 Gd-155 0.000000 0.000000 -33 1 2 O-16 0.196946 0.014729 material group in nuclide mean std. dev. -34 1 1 U-234 7.274440e-06 4.419477e-07 -35 1 1 U-235 9.587803e-03 5.936922e-04 -36 1 1 U-236 7.566099e-05 7.523935e-06 -37 1 1 U-238 7.178367e-03 6.505680e-04 -38 1 1 Np-237 1.315682e-05 8.036501e-07 -39 1 1 Pu-238 7.746151e-06 3.992835e-07 -40 1 1 Pu-239 3.805294e-03 3.637600e-04 -41 1 1 Pu-240 6.941319e-05 4.729737e-06 -42 1 1 Pu-241 1.033844e-03 9.083913e-05 -43 1 1 Pu-242 5.995332e-06 3.821721e-07 -44 1 1 Am-241 1.148585e-06 8.271648e-08 -45 1 1 Am-242m 1.100215e-06 6.159956e-08 -46 1 1 Am-243 8.323826e-07 5.841792e-08 -47 1 1 Cm-242 5.088970e-07 5.258007e-08 -48 1 1 Cm-243 2.245435e-07 1.459025e-08 -49 1 1 Cm-244 2.993206e-07 2.746129e-08 -50 1 1 Cm-245 3.063611e-07 3.057751e-08 -51 1 1 Mo-95 0.000000e+00 0.000000e+00 -52 1 1 Tc-99 0.000000e+00 0.000000e+00 -53 1 1 Ru-101 0.000000e+00 0.000000e+00 -54 1 1 Ru-103 0.000000e+00 0.000000e+00 -55 1 1 Ag-109 0.000000e+00 0.000000e+00 -56 1 1 Xe-135 0.000000e+00 0.000000e+00 -57 1 1 Cs-133 0.000000e+00 0.000000e+00 -58 1 1 Nd-143 0.000000e+00 0.000000e+00 -59 1 1 Nd-145 0.000000e+00 0.000000e+00 -60 1 1 Sm-147 0.000000e+00 0.000000e+00 -61 1 1 Sm-149 0.000000e+00 0.000000e+00 -62 1 1 Sm-150 0.000000e+00 0.000000e+00 -63 1 1 Sm-151 0.000000e+00 0.000000e+00 -64 1 1 Sm-152 0.000000e+00 0.000000e+00 -65 1 1 Eu-153 0.000000e+00 0.000000e+00 -66 1 1 Gd-155 0.000000e+00 0.000000e+00 -67 1 1 O-16 0.000000e+00 0.000000e+00 -0 1 2 U-234 4.408576e-07 2.828309e-08 -1 1 2 U-235 3.768094e-01 2.445671e-02 -2 1 2 U-236 6.097538e-06 3.733038e-07 -3 1 2 U-238 5.353074e-07 3.310544e-08 -4 1 2 Np-237 2.702971e-07 2.098939e-08 -5 1 2 Pu-238 3.463109e-05 2.638394e-06 -6 1 2 Pu-239 2.889643e-01 1.376004e-02 -7 1 2 Pu-240 4.533642e-06 2.544289e-07 -8 1 2 Pu-241 4.809366e-02 2.778345e-03 -9 1 2 Pu-242 8.715325e-08 5.460893e-09 -10 1 2 Am-241 4.611736e-06 2.155039e-07 -11 1 2 Am-242m 1.428047e-04 8.436437e-06 -12 1 2 Am-243 7.883895e-08 4.734503e-09 -13 1 2 Cm-242 9.731025e-07 6.143750e-08 -14 1 2 Cm-243 1.825830e-06 1.074849e-07 -15 1 2 Cm-244 1.581823e-07 9.938064e-09 -16 1 2 Cm-245 1.213386e-05 8.812019e-07 -17 1 2 Mo-95 0.000000e+00 0.000000e+00 -18 1 2 Tc-99 0.000000e+00 0.000000e+00 -19 1 2 Ru-101 0.000000e+00 0.000000e+00 -20 1 2 Ru-103 0.000000e+00 0.000000e+00 -21 1 2 Ag-109 0.000000e+00 0.000000e+00 -22 1 2 Xe-135 0.000000e+00 0.000000e+00 -23 1 2 Cs-133 0.000000e+00 0.000000e+00 -24 1 2 Nd-143 0.000000e+00 0.000000e+00 -25 1 2 Nd-145 0.000000e+00 0.000000e+00 -26 1 2 Sm-147 0.000000e+00 0.000000e+00 -27 1 2 Sm-149 0.000000e+00 0.000000e+00 -28 1 2 Sm-150 0.000000e+00 0.000000e+00 -29 1 2 Sm-151 0.000000e+00 0.000000e+00 -30 1 2 Sm-152 0.000000e+00 0.000000e+00 -31 1 2 Eu-153 0.000000e+00 0.000000e+00 -32 1 2 Gd-155 0.000000e+00 0.000000e+00 -33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide mean std. dev. -102 1 1 1 U-234 0.000000 0.000000 -103 1 1 1 U-235 0.003226 0.001139 -104 1 1 1 U-236 0.001697 0.000923 -105 1 1 1 U-238 0.194620 0.013297 -106 1 1 1 Np-237 0.000000 0.000000 -107 1 1 1 Pu-238 0.000000 0.000000 -108 1 1 1 Pu-239 0.001005 0.000477 -109 1 1 1 Pu-240 0.001307 0.000295 -110 1 1 1 Pu-241 0.000344 0.000244 -111 1 1 1 Pu-242 0.000000 0.000000 -112 1 1 1 Am-241 0.000000 0.000000 -113 1 1 1 Am-242m 0.000000 0.000000 -114 1 1 1 Am-243 0.000000 0.000000 -115 1 1 1 Cm-242 0.000000 0.000000 -116 1 1 1 Cm-243 0.000000 0.000000 -117 1 1 1 Cm-244 0.000000 0.000000 -118 1 1 1 Cm-245 0.000000 0.000000 -119 1 1 1 Mo-95 0.000000 0.000000 -120 1 1 1 Tc-99 0.000000 0.000000 -121 1 1 1 Ru-101 0.000238 0.000254 -122 1 1 1 Ru-103 0.000002 0.000243 -123 1 1 1 Ag-109 0.000000 0.000000 -124 1 1 1 Xe-135 0.000000 0.000000 -125 1 1 1 Cs-133 0.000000 0.000000 -126 1 1 1 Nd-143 0.000447 0.000292 -127 1 1 1 Nd-145 0.000564 0.000294 -128 1 1 1 Sm-147 0.000000 0.000000 -129 1 1 1 Sm-149 0.000000 0.000000 -130 1 1 1 Sm-150 0.000299 0.000238 -131 1 1 1 Sm-151 0.000000 0.000000 -132 1 1 1 Sm-152 0.000492 0.000352 -133 1 1 1 Eu-153 0.000000 0.000000 -134 1 1 1 Gd-155 0.000000 0.000000 -135 1 1 1 O-16 0.133156 0.009821 -68 1 1 2 U-234 0.000000 0.000000 -69 1 1 2 U-235 0.000000 0.000000 -70 1 1 2 U-236 0.000000 0.000000 -71 1 1 2 U-238 0.000173 0.000173 -72 1 1 2 Np-237 0.000000 0.000000 -73 1 1 2 Pu-238 0.000000 0.000000 -74 1 1 2 Pu-239 0.000000 0.000000 -75 1 1 2 Pu-240 0.000000 0.000000 -76 1 1 2 Pu-241 0.000000 0.000000 -77 1 1 2 Pu-242 0.000000 0.000000 -78 1 1 2 Am-241 0.000000 0.000000 -79 1 1 2 Am-242m 0.000000 0.000000 -80 1 1 2 Am-243 0.000000 0.000000 -81 1 1 2 Cm-242 0.000000 0.000000 -82 1 1 2 Cm-243 0.000000 0.000000 -83 1 1 2 Cm-244 0.000000 0.000000 -84 1 1 2 Cm-245 0.000000 0.000000 -85 1 1 2 Mo-95 0.000000 0.000000 -86 1 1 2 Tc-99 0.000000 0.000000 -87 1 1 2 Ru-101 0.000000 0.000000 -88 1 1 2 Ru-103 0.000000 0.000000 -89 1 1 2 Ag-109 0.000000 0.000000 -90 1 1 2 Xe-135 0.000000 0.000000 -91 1 1 2 Cs-133 0.000000 0.000000 -92 1 1 2 Nd-143 0.000000 0.000000 -93 1 1 2 Nd-145 0.000000 0.000000 -94 1 1 2 Sm-147 0.000000 0.000000 -95 1 1 2 Sm-149 0.000000 0.000000 -96 1 1 2 Sm-150 0.000000 0.000000 -97 1 1 2 Sm-151 0.000000 0.000000 -98 1 1 2 Sm-152 0.000000 0.000000 -99 1 1 2 Eu-153 0.000000 0.000000 -100 1 1 2 Gd-155 0.000000 0.000000 -101 1 1 2 O-16 0.001386 0.000446 -34 1 2 1 U-234 0.000000 0.000000 -35 1 2 1 U-235 0.000000 0.000000 -36 1 2 1 U-236 0.000000 0.000000 -37 1 2 1 U-238 0.000000 0.000000 -38 1 2 1 Np-237 0.000000 0.000000 -39 1 2 1 Pu-238 0.000000 0.000000 -40 1 2 1 Pu-239 0.000000 0.000000 -41 1 2 1 Pu-240 0.000000 0.000000 -42 1 2 1 Pu-241 0.000000 0.000000 -43 1 2 1 Pu-242 0.000000 0.000000 -44 1 2 1 Am-241 0.000000 0.000000 -45 1 2 1 Am-242m 0.000000 0.000000 -46 1 2 1 Am-243 0.000000 0.000000 -47 1 2 1 Cm-242 0.000000 0.000000 -48 1 2 1 Cm-243 0.000000 0.000000 -49 1 2 1 Cm-244 0.000000 0.000000 -50 1 2 1 Cm-245 0.000000 0.000000 -51 1 2 1 Mo-95 0.000000 0.000000 -52 1 2 1 Tc-99 0.000000 0.000000 -53 1 2 1 Ru-101 0.000000 0.000000 -54 1 2 1 Ru-103 0.000000 0.000000 -55 1 2 1 Ag-109 0.000000 0.000000 -56 1 2 1 Xe-135 0.000000 0.000000 -57 1 2 1 Cs-133 0.000000 0.000000 -58 1 2 1 Nd-143 0.000000 0.000000 -59 1 2 1 Nd-145 0.000000 0.000000 -60 1 2 1 Sm-147 0.000000 0.000000 -61 1 2 1 Sm-149 0.000000 0.000000 -62 1 2 1 Sm-150 0.000000 0.000000 -63 1 2 1 Sm-151 0.000000 0.000000 -64 1 2 1 Sm-152 0.000000 0.000000 -65 1 2 1 Eu-153 0.000000 0.000000 -66 1 2 1 Gd-155 0.000000 0.000000 -67 1 2 1 O-16 0.000000 0.000000 -0 1 2 2 U-234 0.000000 0.000000 -1 1 2 2 U-235 0.003889 0.003962 -2 1 2 2 U-236 0.001501 0.002037 -3 1 2 2 U-238 0.219715 0.025984 -4 1 2 2 Np-237 0.000000 0.000000 -5 1 2 2 Pu-238 0.000000 0.000000 -6 1 2 2 Pu-239 0.000000 0.000000 -7 1 2 2 Pu-240 0.000000 0.000000 -8 1 2 2 Pu-241 0.000000 0.000000 -9 1 2 2 Pu-242 0.000000 0.000000 -10 1 2 2 Am-241 0.000000 0.000000 -11 1 2 2 Am-242m 0.000000 0.000000 -12 1 2 2 Am-243 0.000000 0.000000 -13 1 2 2 Cm-242 0.000000 0.000000 -14 1 2 2 Cm-243 0.000000 0.000000 -15 1 2 2 Cm-244 0.000000 0.000000 -16 1 2 2 Cm-245 0.000000 0.000000 -17 1 2 2 Mo-95 0.000000 0.000000 -18 1 2 2 Tc-99 0.000000 0.000000 -19 1 2 2 Ru-101 0.000000 0.000000 -20 1 2 2 Ru-103 0.000000 0.000000 -21 1 2 2 Ag-109 0.000000 0.000000 -22 1 2 2 Xe-135 0.000000 0.000000 -23 1 2 2 Cs-133 0.000000 0.000000 -24 1 2 2 Nd-143 0.000000 0.000000 -25 1 2 2 Nd-145 0.000000 0.000000 -26 1 2 2 Sm-147 0.000000 0.000000 -27 1 2 2 Sm-149 0.000000 0.000000 -28 1 2 2 Sm-150 0.000000 0.000000 -29 1 2 2 Sm-151 0.000000 0.000000 -30 1 2 2 Sm-152 0.000000 0.000000 -31 1 2 2 Eu-153 0.000000 0.000000 -32 1 2 2 Gd-155 0.000000 0.000000 -33 1 2 2 O-16 0.196946 0.014729 material group out nuclide mean std. dev. -34 1 1 U-234 0.0 0.000000 -35 1 1 U-235 1.0 0.066362 -36 1 1 U-236 0.0 0.000000 -37 1 1 U-238 1.0 0.093082 -38 1 1 Np-237 0.0 0.000000 -39 1 1 Pu-238 0.0 0.000000 -40 1 1 Pu-239 1.0 0.104567 -41 1 1 Pu-240 0.0 0.000000 -42 1 1 Pu-241 1.0 0.263696 -43 1 1 Pu-242 0.0 0.000000 -44 1 1 Am-241 0.0 0.000000 -45 1 1 Am-242m 0.0 0.000000 -46 1 1 Am-243 0.0 0.000000 -47 1 1 Cm-242 0.0 0.000000 -48 1 1 Cm-243 0.0 0.000000 -49 1 1 Cm-244 0.0 0.000000 -50 1 1 Cm-245 0.0 0.000000 -51 1 1 Mo-95 0.0 0.000000 -52 1 1 Tc-99 0.0 0.000000 -53 1 1 Ru-101 0.0 0.000000 -54 1 1 Ru-103 0.0 0.000000 -55 1 1 Ag-109 0.0 0.000000 -56 1 1 Xe-135 0.0 0.000000 -57 1 1 Cs-133 0.0 0.000000 -58 1 1 Nd-143 0.0 0.000000 -59 1 1 Nd-145 0.0 0.000000 -60 1 1 Sm-147 0.0 0.000000 -61 1 1 Sm-149 0.0 0.000000 -62 1 1 Sm-150 0.0 0.000000 -63 1 1 Sm-151 0.0 0.000000 -64 1 1 Sm-152 0.0 0.000000 -65 1 1 Eu-153 0.0 0.000000 -66 1 1 Gd-155 0.0 0.000000 -67 1 1 O-16 0.0 0.000000 -0 1 2 U-234 0.0 0.000000 -1 1 2 U-235 0.0 0.000000 -2 1 2 U-236 0.0 0.000000 -3 1 2 U-238 0.0 0.000000 -4 1 2 Np-237 0.0 0.000000 -5 1 2 Pu-238 0.0 0.000000 -6 1 2 Pu-239 0.0 0.000000 -7 1 2 Pu-240 0.0 0.000000 -8 1 2 Pu-241 0.0 0.000000 -9 1 2 Pu-242 0.0 0.000000 -10 1 2 Am-241 0.0 0.000000 -11 1 2 Am-242m 0.0 0.000000 -12 1 2 Am-243 0.0 0.000000 -13 1 2 Cm-242 0.0 0.000000 -14 1 2 Cm-243 0.0 0.000000 -15 1 2 Cm-244 0.0 0.000000 -16 1 2 Cm-245 0.0 0.000000 -17 1 2 Mo-95 0.0 0.000000 -18 1 2 Tc-99 0.0 0.000000 -19 1 2 Ru-101 0.0 0.000000 -20 1 2 Ru-103 0.0 0.000000 -21 1 2 Ag-109 0.0 0.000000 -22 1 2 Xe-135 0.0 0.000000 -23 1 2 Cs-133 0.0 0.000000 -24 1 2 Nd-143 0.0 0.000000 -25 1 2 Nd-145 0.0 0.000000 -26 1 2 Sm-147 0.0 0.000000 -27 1 2 Sm-149 0.0 0.000000 -28 1 2 Sm-150 0.0 0.000000 -29 1 2 Sm-151 0.0 0.000000 -30 1 2 Sm-152 0.0 0.000000 -31 1 2 Eu-153 0.0 0.000000 -32 1 2 Gd-155 0.0 0.000000 -33 1 2 O-16 0.0 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0.104734 0.008915 -6 2 1 Zr-91 0.036155 0.003735 -7 2 1 Zr-92 0.042422 0.003029 -8 2 1 Zr-94 0.046148 0.006251 -9 2 1 Zr-96 0.007794 0.001536 -0 2 2 Zr-90 0.121688 0.034934 -1 2 2 Zr-91 0.061792 0.024317 -2 2 2 Zr-92 0.041633 0.016323 -3 2 2 Zr-94 0.060818 0.021483 -4 2 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0.0 0.0 -6 2 1 Zr-91 0.0 0.0 -7 2 1 Zr-92 0.0 0.0 -8 2 1 Zr-94 0.0 0.0 -9 2 1 Zr-96 0.0 0.0 -0 2 2 Zr-90 0.0 0.0 -1 2 2 Zr-91 0.0 0.0 -2 2 2 Zr-92 0.0 0.0 -3 2 2 Zr-94 0.0 0.0 -4 2 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -15 2 1 1 Zr-90 0.104734 0.008915 -16 2 1 1 Zr-91 0.036155 0.003735 -17 2 1 1 Zr-92 0.042422 0.003029 -18 2 1 1 Zr-94 0.046148 0.006251 -19 2 1 1 Zr-96 0.007794 0.001536 -10 2 1 2 Zr-90 0.000000 0.000000 -11 2 1 2 Zr-91 0.000000 0.000000 -12 2 1 2 Zr-92 0.000000 0.000000 -13 2 1 2 Zr-94 0.000000 0.000000 -14 2 1 2 Zr-96 0.000000 0.000000 -5 2 2 1 Zr-90 0.000000 0.000000 -6 2 2 1 Zr-91 0.000000 0.000000 -7 2 2 1 Zr-92 0.000000 0.000000 -8 2 2 1 Zr-94 0.000000 0.000000 -9 2 2 1 Zr-96 0.000000 0.000000 -0 2 2 2 Zr-90 0.121688 0.034934 -1 2 2 2 Zr-91 0.061792 0.024317 -2 2 2 2 Zr-92 0.041633 0.016323 -3 2 2 2 Zr-94 0.060818 0.021483 -4 2 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -5 2 1 Zr-90 0.0 0.0 -6 2 1 Zr-91 0.0 0.0 -7 2 1 Zr-92 0.0 0.0 -8 2 1 Zr-94 0.0 0.0 -9 2 1 Zr-96 0.0 0.0 -0 2 2 Zr-90 0.0 0.0 -1 2 2 Zr-91 0.0 0.0 -2 2 2 Zr-92 0.0 0.0 -3 2 2 Zr-94 0.0 0.0 -4 2 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. -4 3 1 H-1 0.207103 0.023028 -5 3 1 O-16 0.079282 0.005197 -6 3 1 B-10 0.000521 0.000244 -7 3 1 B-11 0.000000 0.000000 -0 3 2 H-1 1.283344 0.250946 -1 3 2 O-16 0.085363 0.014001 -2 3 2 B-10 0.049249 0.008232 -3 3 2 B-11 0.000195 0.001527 material group in nuclide mean std. dev. -4 3 1 H-1 0.0 0.0 -5 3 1 O-16 0.0 0.0 -6 3 1 B-10 0.0 0.0 -7 3 1 B-11 0.0 0.0 -0 3 2 H-1 0.0 0.0 -1 3 2 O-16 0.0 0.0 -2 3 2 B-10 0.0 0.0 -3 3 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. -12 3 1 1 H-1 0.181306 0.022102 -13 3 1 1 O-16 0.078631 0.005044 -14 3 1 1 B-10 0.000000 0.000000 -15 3 1 1 B-11 0.000000 0.000000 -8 3 1 2 H-1 0.025666 0.001582 -9 3 1 2 O-16 0.000521 0.000131 -10 3 1 2 B-10 0.000000 0.000000 -11 3 1 2 B-11 0.000000 0.000000 -4 3 2 1 H-1 0.000000 0.000000 -5 3 2 1 O-16 0.000000 0.000000 -6 3 2 1 B-10 0.000000 0.000000 -7 3 2 1 B-11 0.000000 0.000000 -0 3 2 2 H-1 1.273963 0.250623 -1 3 2 2 O-16 0.085363 0.014001 -2 3 2 2 B-10 0.000000 0.000000 -3 3 2 2 B-11 0.000195 0.001527 material group out nuclide mean std. dev. -4 3 1 H-1 0.0 0.0 -5 3 1 O-16 0.0 0.0 -6 3 1 B-10 0.0 0.0 -7 3 1 B-11 0.0 0.0 -0 3 2 H-1 0.0 0.0 -1 3 2 O-16 0.0 0.0 -2 3 2 B-10 0.0 0.0 -3 3 2 B-11 0.0 0.0 material group in nuclide mean std. dev. -4 4 1 H-1 0.175242 0.053715 -5 4 1 O-16 0.066545 0.010083 -6 4 1 B-10 0.000570 0.000352 -7 4 1 B-11 0.000089 0.000346 -0 4 2 H-1 1.142895 0.365140 -1 4 2 O-16 0.085141 0.028073 -2 4 2 B-10 0.025923 0.007276 -3 4 2 B-11 0.000000 0.000000 material group in nuclide mean std. dev. -4 4 1 H-1 0.0 0.0 -5 4 1 O-16 0.0 0.0 -6 4 1 B-10 0.0 0.0 -7 4 1 B-11 0.0 0.0 -0 4 2 H-1 0.0 0.0 -1 4 2 O-16 0.0 0.0 -2 4 2 B-10 0.0 0.0 -3 4 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. -12 4 1 1 H-1 0.151295 0.051491 -13 4 1 1 O-16 0.066545 0.010083 -14 4 1 1 B-10 0.000000 0.000000 -15 4 1 1 B-11 0.000089 0.000346 -8 4 1 2 H-1 0.023662 0.003083 -9 4 1 2 O-16 0.000000 0.000000 -10 4 1 2 B-10 0.000000 0.000000 -11 4 1 2 B-11 0.000000 0.000000 -4 4 2 1 H-1 0.000000 0.000000 -5 4 2 1 O-16 0.000000 0.000000 -6 4 2 1 B-10 0.000000 0.000000 -7 4 2 1 B-11 0.000000 0.000000 -0 4 2 2 H-1 1.129933 0.361681 -1 4 2 2 O-16 0.085141 0.028073 -2 4 2 2 B-10 0.000000 0.000000 -3 4 2 2 B-11 0.000000 0.000000 material group out nuclide mean std. dev. -4 4 1 H-1 0.0 0.0 -5 4 1 O-16 0.0 0.0 -6 4 1 B-10 0.0 0.0 -7 4 1 B-11 0.0 0.0 -0 4 2 H-1 0.0 0.0 -1 4 2 O-16 0.0 0.0 -2 4 2 B-10 0.0 0.0 -3 4 2 B-11 0.0 0.0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in group out nuclide mean std. dev. -81 5 1 1 Fe-54 0.0 0.0 -82 5 1 1 Fe-56 0.0 0.0 -83 5 1 1 Fe-57 0.0 0.0 -84 5 1 1 Fe-58 0.0 0.0 -85 5 1 1 Ni-58 0.0 0.0 -86 5 1 1 Ni-60 0.0 0.0 -87 5 1 1 Ni-61 0.0 0.0 -88 5 1 1 Ni-62 0.0 0.0 -89 5 1 1 Ni-64 0.0 0.0 -90 5 1 1 Mn-55 0.0 0.0 -91 5 1 1 Mo-92 0.0 0.0 -92 5 1 1 Mo-94 0.0 0.0 -93 5 1 1 Mo-95 0.0 0.0 -94 5 1 1 Mo-96 0.0 0.0 -95 5 1 1 Mo-97 0.0 0.0 -96 5 1 1 Mo-98 0.0 0.0 -97 5 1 1 Mo-100 0.0 0.0 -98 5 1 1 Si-28 0.0 0.0 -99 5 1 1 Si-29 0.0 0.0 -100 5 1 1 Si-30 0.0 0.0 -101 5 1 1 Cr-50 0.0 0.0 -102 5 1 1 Cr-52 0.0 0.0 -103 5 1 1 Cr-53 0.0 0.0 -104 5 1 1 Cr-54 0.0 0.0 -105 5 1 1 C-Nat 0.0 0.0 -106 5 1 1 Cu-63 0.0 0.0 -107 5 1 1 Cu-65 0.0 0.0 -54 5 1 2 Fe-54 0.0 0.0 -55 5 1 2 Fe-56 0.0 0.0 -56 5 1 2 Fe-57 0.0 0.0 -57 5 1 2 Fe-58 0.0 0.0 -58 5 1 2 Ni-58 0.0 0.0 -59 5 1 2 Ni-60 0.0 0.0 -60 5 1 2 Ni-61 0.0 0.0 -61 5 1 2 Ni-62 0.0 0.0 -62 5 1 2 Ni-64 0.0 0.0 -63 5 1 2 Mn-55 0.0 0.0 -64 5 1 2 Mo-92 0.0 0.0 -65 5 1 2 Mo-94 0.0 0.0 -66 5 1 2 Mo-95 0.0 0.0 -67 5 1 2 Mo-96 0.0 0.0 -68 5 1 2 Mo-97 0.0 0.0 -69 5 1 2 Mo-98 0.0 0.0 -70 5 1 2 Mo-100 0.0 0.0 -71 5 1 2 Si-28 0.0 0.0 -72 5 1 2 Si-29 0.0 0.0 -73 5 1 2 Si-30 0.0 0.0 -74 5 1 2 Cr-50 0.0 0.0 -75 5 1 2 Cr-52 0.0 0.0 -76 5 1 2 Cr-53 0.0 0.0 -77 5 1 2 Cr-54 0.0 0.0 -78 5 1 2 C-Nat 0.0 0.0 -79 5 1 2 Cu-63 0.0 0.0 -80 5 1 2 Cu-65 0.0 0.0 -27 5 2 1 Fe-54 0.0 0.0 -28 5 2 1 Fe-56 0.0 0.0 -29 5 2 1 Fe-57 0.0 0.0 -30 5 2 1 Fe-58 0.0 0.0 -31 5 2 1 Ni-58 0.0 0.0 -32 5 2 1 Ni-60 0.0 0.0 -33 5 2 1 Ni-61 0.0 0.0 -34 5 2 1 Ni-62 0.0 0.0 -35 5 2 1 Ni-64 0.0 0.0 -36 5 2 1 Mn-55 0.0 0.0 -37 5 2 1 Mo-92 0.0 0.0 -38 5 2 1 Mo-94 0.0 0.0 -39 5 2 1 Mo-95 0.0 0.0 -40 5 2 1 Mo-96 0.0 0.0 -41 5 2 1 Mo-97 0.0 0.0 -42 5 2 1 Mo-98 0.0 0.0 -43 5 2 1 Mo-100 0.0 0.0 -44 5 2 1 Si-28 0.0 0.0 -45 5 2 1 Si-29 0.0 0.0 -46 5 2 1 Si-30 0.0 0.0 -47 5 2 1 Cr-50 0.0 0.0 -48 5 2 1 Cr-52 0.0 0.0 -49 5 2 1 Cr-53 0.0 0.0 -50 5 2 1 Cr-54 0.0 0.0 -51 5 2 1 C-Nat 0.0 0.0 -52 5 2 1 Cu-63 0.0 0.0 -53 5 2 1 Cu-65 0.0 0.0 -0 5 2 2 Fe-54 0.0 0.0 -1 5 2 2 Fe-56 0.0 0.0 -2 5 2 2 Fe-57 0.0 0.0 -3 5 2 2 Fe-58 0.0 0.0 -4 5 2 2 Ni-58 0.0 0.0 -5 5 2 2 Ni-60 0.0 0.0 -6 5 2 2 Ni-61 0.0 0.0 -7 5 2 2 Ni-62 0.0 0.0 -8 5 2 2 Ni-64 0.0 0.0 -9 5 2 2 Mn-55 0.0 0.0 -10 5 2 2 Mo-92 0.0 0.0 -11 5 2 2 Mo-94 0.0 0.0 -12 5 2 2 Mo-95 0.0 0.0 -13 5 2 2 Mo-96 0.0 0.0 -14 5 2 2 Mo-97 0.0 0.0 -15 5 2 2 Mo-98 0.0 0.0 -16 5 2 2 Mo-100 0.0 0.0 -17 5 2 2 Si-28 0.0 0.0 -18 5 2 2 Si-29 0.0 0.0 -19 5 2 2 Si-30 0.0 0.0 -20 5 2 2 Cr-50 0.0 0.0 -21 5 2 2 Cr-52 0.0 0.0 -22 5 2 2 Cr-53 0.0 0.0 -23 5 2 2 Cr-54 0.0 0.0 -24 5 2 2 C-Nat 0.0 0.0 -25 5 2 2 Cu-63 0.0 0.0 -26 5 2 2 Cu-65 0.0 0.0 material group out nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 6 1 1 H-1 0.0 0.0 -64 6 1 1 O-16 0.0 0.0 -65 6 1 1 B-10 0.0 0.0 -66 6 1 1 B-11 0.0 0.0 -67 6 1 1 Fe-54 0.0 0.0 -68 6 1 1 Fe-56 0.0 0.0 -69 6 1 1 Fe-57 0.0 0.0 -70 6 1 1 Fe-58 0.0 0.0 -71 6 1 1 Ni-58 0.0 0.0 -72 6 1 1 Ni-60 0.0 0.0 -73 6 1 1 Ni-61 0.0 0.0 -74 6 1 1 Ni-62 0.0 0.0 -75 6 1 1 Ni-64 0.0 0.0 -76 6 1 1 Mn-55 0.0 0.0 -77 6 1 1 Si-28 0.0 0.0 -78 6 1 1 Si-29 0.0 0.0 -79 6 1 1 Si-30 0.0 0.0 -80 6 1 1 Cr-50 0.0 0.0 -81 6 1 1 Cr-52 0.0 0.0 -82 6 1 1 Cr-53 0.0 0.0 -83 6 1 1 Cr-54 0.0 0.0 -42 6 1 2 H-1 0.0 0.0 -43 6 1 2 O-16 0.0 0.0 -44 6 1 2 B-10 0.0 0.0 -45 6 1 2 B-11 0.0 0.0 -46 6 1 2 Fe-54 0.0 0.0 -47 6 1 2 Fe-56 0.0 0.0 -48 6 1 2 Fe-57 0.0 0.0 -49 6 1 2 Fe-58 0.0 0.0 -50 6 1 2 Ni-58 0.0 0.0 -51 6 1 2 Ni-60 0.0 0.0 -52 6 1 2 Ni-61 0.0 0.0 -53 6 1 2 Ni-62 0.0 0.0 -54 6 1 2 Ni-64 0.0 0.0 -55 6 1 2 Mn-55 0.0 0.0 -56 6 1 2 Si-28 0.0 0.0 -57 6 1 2 Si-29 0.0 0.0 -58 6 1 2 Si-30 0.0 0.0 -59 6 1 2 Cr-50 0.0 0.0 -60 6 1 2 Cr-52 0.0 0.0 -61 6 1 2 Cr-53 0.0 0.0 -62 6 1 2 Cr-54 0.0 0.0 -21 6 2 1 H-1 0.0 0.0 -22 6 2 1 O-16 0.0 0.0 -23 6 2 1 B-10 0.0 0.0 -24 6 2 1 B-11 0.0 0.0 -25 6 2 1 Fe-54 0.0 0.0 -26 6 2 1 Fe-56 0.0 0.0 -27 6 2 1 Fe-57 0.0 0.0 -28 6 2 1 Fe-58 0.0 0.0 -29 6 2 1 Ni-58 0.0 0.0 -30 6 2 1 Ni-60 0.0 0.0 -31 6 2 1 Ni-61 0.0 0.0 -32 6 2 1 Ni-62 0.0 0.0 -33 6 2 1 Ni-64 0.0 0.0 -34 6 2 1 Mn-55 0.0 0.0 -35 6 2 1 Si-28 0.0 0.0 -36 6 2 1 Si-29 0.0 0.0 -37 6 2 1 Si-30 0.0 0.0 -38 6 2 1 Cr-50 0.0 0.0 -39 6 2 1 Cr-52 0.0 0.0 -40 6 2 1 Cr-53 0.0 0.0 -41 6 2 1 Cr-54 0.0 0.0 -0 6 2 2 H-1 0.0 0.0 -1 6 2 2 O-16 0.0 0.0 -2 6 2 2 B-10 0.0 0.0 -3 6 2 2 B-11 0.0 0.0 -4 6 2 2 Fe-54 0.0 0.0 -5 6 2 2 Fe-56 0.0 0.0 -6 6 2 2 Fe-57 0.0 0.0 -7 6 2 2 Fe-58 0.0 0.0 -8 6 2 2 Ni-58 0.0 0.0 -9 6 2 2 Ni-60 0.0 0.0 -10 6 2 2 Ni-61 0.0 0.0 -11 6 2 2 Ni-62 0.0 0.0 -12 6 2 2 Ni-64 0.0 0.0 -13 6 2 2 Mn-55 0.0 0.0 -14 6 2 2 Si-28 0.0 0.0 -15 6 2 2 Si-29 0.0 0.0 -16 6 2 2 Si-30 0.0 0.0 -17 6 2 2 Cr-50 0.0 0.0 -18 6 2 2 Cr-52 0.0 0.0 -19 6 2 2 Cr-53 0.0 0.0 -20 6 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 7 1 1 H-1 0.0 0.0 -64 7 1 1 O-16 0.0 0.0 -65 7 1 1 B-10 0.0 0.0 -66 7 1 1 B-11 0.0 0.0 -67 7 1 1 Fe-54 0.0 0.0 -68 7 1 1 Fe-56 0.0 0.0 -69 7 1 1 Fe-57 0.0 0.0 -70 7 1 1 Fe-58 0.0 0.0 -71 7 1 1 Ni-58 0.0 0.0 -72 7 1 1 Ni-60 0.0 0.0 -73 7 1 1 Ni-61 0.0 0.0 -74 7 1 1 Ni-62 0.0 0.0 -75 7 1 1 Ni-64 0.0 0.0 -76 7 1 1 Mn-55 0.0 0.0 -77 7 1 1 Si-28 0.0 0.0 -78 7 1 1 Si-29 0.0 0.0 -79 7 1 1 Si-30 0.0 0.0 -80 7 1 1 Cr-50 0.0 0.0 -81 7 1 1 Cr-52 0.0 0.0 -82 7 1 1 Cr-53 0.0 0.0 -83 7 1 1 Cr-54 0.0 0.0 -42 7 1 2 H-1 0.0 0.0 -43 7 1 2 O-16 0.0 0.0 -44 7 1 2 B-10 0.0 0.0 -45 7 1 2 B-11 0.0 0.0 -46 7 1 2 Fe-54 0.0 0.0 -47 7 1 2 Fe-56 0.0 0.0 -48 7 1 2 Fe-57 0.0 0.0 -49 7 1 2 Fe-58 0.0 0.0 -50 7 1 2 Ni-58 0.0 0.0 -51 7 1 2 Ni-60 0.0 0.0 -52 7 1 2 Ni-61 0.0 0.0 -53 7 1 2 Ni-62 0.0 0.0 -54 7 1 2 Ni-64 0.0 0.0 -55 7 1 2 Mn-55 0.0 0.0 -56 7 1 2 Si-28 0.0 0.0 -57 7 1 2 Si-29 0.0 0.0 -58 7 1 2 Si-30 0.0 0.0 -59 7 1 2 Cr-50 0.0 0.0 -60 7 1 2 Cr-52 0.0 0.0 -61 7 1 2 Cr-53 0.0 0.0 -62 7 1 2 Cr-54 0.0 0.0 -21 7 2 1 H-1 0.0 0.0 -22 7 2 1 O-16 0.0 0.0 -23 7 2 1 B-10 0.0 0.0 -24 7 2 1 B-11 0.0 0.0 -25 7 2 1 Fe-54 0.0 0.0 -26 7 2 1 Fe-56 0.0 0.0 -27 7 2 1 Fe-57 0.0 0.0 -28 7 2 1 Fe-58 0.0 0.0 -29 7 2 1 Ni-58 0.0 0.0 -30 7 2 1 Ni-60 0.0 0.0 -31 7 2 1 Ni-61 0.0 0.0 -32 7 2 1 Ni-62 0.0 0.0 -33 7 2 1 Ni-64 0.0 0.0 -34 7 2 1 Mn-55 0.0 0.0 -35 7 2 1 Si-28 0.0 0.0 -36 7 2 1 Si-29 0.0 0.0 -37 7 2 1 Si-30 0.0 0.0 -38 7 2 1 Cr-50 0.0 0.0 -39 7 2 1 Cr-52 0.0 0.0 -40 7 2 1 Cr-53 0.0 0.0 -41 7 2 1 Cr-54 0.0 0.0 -0 7 2 2 H-1 0.0 0.0 -1 7 2 2 O-16 0.0 0.0 -2 7 2 2 B-10 0.0 0.0 -3 7 2 2 B-11 0.0 0.0 -4 7 2 2 Fe-54 0.0 0.0 -5 7 2 2 Fe-56 0.0 0.0 -6 7 2 2 Fe-57 0.0 0.0 -7 7 2 2 Fe-58 0.0 0.0 -8 7 2 2 Ni-58 0.0 0.0 -9 7 2 2 Ni-60 0.0 0.0 -10 7 2 2 Ni-61 0.0 0.0 -11 7 2 2 Ni-62 0.0 0.0 -12 7 2 2 Ni-64 0.0 0.0 -13 7 2 2 Mn-55 0.0 0.0 -14 7 2 2 Si-28 0.0 0.0 -15 7 2 2 Si-29 0.0 0.0 -16 7 2 2 Si-30 0.0 0.0 -17 7 2 2 Cr-50 0.0 0.0 -18 7 2 2 Cr-52 0.0 0.0 -19 7 2 2 Cr-53 0.0 0.0 -20 7 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 8 1 1 H-1 0.0 0.0 -64 8 1 1 O-16 0.0 0.0 -65 8 1 1 B-10 0.0 0.0 -66 8 1 1 B-11 0.0 0.0 -67 8 1 1 Fe-54 0.0 0.0 -68 8 1 1 Fe-56 0.0 0.0 -69 8 1 1 Fe-57 0.0 0.0 -70 8 1 1 Fe-58 0.0 0.0 -71 8 1 1 Ni-58 0.0 0.0 -72 8 1 1 Ni-60 0.0 0.0 -73 8 1 1 Ni-61 0.0 0.0 -74 8 1 1 Ni-62 0.0 0.0 -75 8 1 1 Ni-64 0.0 0.0 -76 8 1 1 Mn-55 0.0 0.0 -77 8 1 1 Si-28 0.0 0.0 -78 8 1 1 Si-29 0.0 0.0 -79 8 1 1 Si-30 0.0 0.0 -80 8 1 1 Cr-50 0.0 0.0 -81 8 1 1 Cr-52 0.0 0.0 -82 8 1 1 Cr-53 0.0 0.0 -83 8 1 1 Cr-54 0.0 0.0 -42 8 1 2 H-1 0.0 0.0 -43 8 1 2 O-16 0.0 0.0 -44 8 1 2 B-10 0.0 0.0 -45 8 1 2 B-11 0.0 0.0 -46 8 1 2 Fe-54 0.0 0.0 -47 8 1 2 Fe-56 0.0 0.0 -48 8 1 2 Fe-57 0.0 0.0 -49 8 1 2 Fe-58 0.0 0.0 -50 8 1 2 Ni-58 0.0 0.0 -51 8 1 2 Ni-60 0.0 0.0 -52 8 1 2 Ni-61 0.0 0.0 -53 8 1 2 Ni-62 0.0 0.0 -54 8 1 2 Ni-64 0.0 0.0 -55 8 1 2 Mn-55 0.0 0.0 -56 8 1 2 Si-28 0.0 0.0 -57 8 1 2 Si-29 0.0 0.0 -58 8 1 2 Si-30 0.0 0.0 -59 8 1 2 Cr-50 0.0 0.0 -60 8 1 2 Cr-52 0.0 0.0 -61 8 1 2 Cr-53 0.0 0.0 -62 8 1 2 Cr-54 0.0 0.0 -21 8 2 1 H-1 0.0 0.0 -22 8 2 1 O-16 0.0 0.0 -23 8 2 1 B-10 0.0 0.0 -24 8 2 1 B-11 0.0 0.0 -25 8 2 1 Fe-54 0.0 0.0 -26 8 2 1 Fe-56 0.0 0.0 -27 8 2 1 Fe-57 0.0 0.0 -28 8 2 1 Fe-58 0.0 0.0 -29 8 2 1 Ni-58 0.0 0.0 -30 8 2 1 Ni-60 0.0 0.0 -31 8 2 1 Ni-61 0.0 0.0 -32 8 2 1 Ni-62 0.0 0.0 -33 8 2 1 Ni-64 0.0 0.0 -34 8 2 1 Mn-55 0.0 0.0 -35 8 2 1 Si-28 0.0 0.0 -36 8 2 1 Si-29 0.0 0.0 -37 8 2 1 Si-30 0.0 0.0 -38 8 2 1 Cr-50 0.0 0.0 -39 8 2 1 Cr-52 0.0 0.0 -40 8 2 1 Cr-53 0.0 0.0 -41 8 2 1 Cr-54 0.0 0.0 -0 8 2 2 H-1 0.0 0.0 -1 8 2 2 O-16 0.0 0.0 -2 8 2 2 B-10 0.0 0.0 -3 8 2 2 B-11 0.0 0.0 -4 8 2 2 Fe-54 0.0 0.0 -5 8 2 2 Fe-56 0.0 0.0 -6 8 2 2 Fe-57 0.0 0.0 -7 8 2 2 Fe-58 0.0 0.0 -8 8 2 2 Ni-58 0.0 0.0 -9 8 2 2 Ni-60 0.0 0.0 -10 8 2 2 Ni-61 0.0 0.0 -11 8 2 2 Ni-62 0.0 0.0 -12 8 2 2 Ni-64 0.0 0.0 -13 8 2 2 Mn-55 0.0 0.0 -14 8 2 2 Si-28 0.0 0.0 -15 8 2 2 Si-29 0.0 0.0 -16 8 2 2 Si-30 0.0 0.0 -17 8 2 2 Cr-50 0.0 0.0 -18 8 2 2 Cr-52 0.0 0.0 -19 8 2 2 Cr-53 0.0 0.0 -20 8 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 9 1 H-1 0.150655 0.480993 -22 9 1 O-16 0.116221 0.114089 -23 9 1 B-10 0.000000 0.000000 -24 9 1 B-11 0.000000 0.000000 -25 9 1 Fe-54 0.000000 0.000000 -26 9 1 Fe-56 0.186217 0.199795 -27 9 1 Fe-57 0.000000 0.000000 -28 9 1 Fe-58 0.000000 0.000000 -29 9 1 Ni-58 0.000000 0.000000 -30 9 1 Ni-60 0.000000 0.000000 -31 9 1 Ni-61 0.000000 0.000000 -32 9 1 Ni-62 0.000000 0.000000 -33 9 1 Ni-64 0.000000 0.000000 -34 9 1 Mn-55 0.000000 0.000000 -35 9 1 Si-28 0.000000 0.000000 -36 9 1 Si-29 0.000000 0.000000 -37 9 1 Si-30 0.000000 0.000000 -38 9 1 Cr-50 0.000000 0.000000 -39 9 1 Cr-52 0.000000 0.000000 -40 9 1 Cr-53 0.147443 0.139574 -41 9 1 Cr-54 0.000000 0.000000 -0 9 2 H-1 0.000000 0.000000 -1 9 2 O-16 0.000000 0.000000 -2 9 2 B-10 0.000000 0.000000 -3 9 2 B-11 0.000000 0.000000 -4 9 2 Fe-54 0.000000 0.000000 -5 9 2 Fe-56 0.000000 0.000000 -6 9 2 Fe-57 0.000000 0.000000 -7 9 2 Fe-58 0.000000 0.000000 -8 9 2 Ni-58 0.000000 0.000000 -9 9 2 Ni-60 0.000000 0.000000 -10 9 2 Ni-61 0.000000 0.000000 -11 9 2 Ni-62 0.000000 0.000000 -12 9 2 Ni-64 0.000000 0.000000 -13 9 2 Mn-55 0.000000 0.000000 -14 9 2 Si-28 0.000000 0.000000 -15 9 2 Si-29 0.000000 0.000000 -16 9 2 Si-30 0.000000 0.000000 -17 9 2 Cr-50 0.000000 0.000000 -18 9 2 Cr-52 0.000000 0.000000 -19 9 2 Cr-53 0.000000 0.000000 -20 9 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 9 1 H-1 0.0 0.0 -22 9 1 O-16 0.0 0.0 -23 9 1 B-10 0.0 0.0 -24 9 1 B-11 0.0 0.0 -25 9 1 Fe-54 0.0 0.0 -26 9 1 Fe-56 0.0 0.0 -27 9 1 Fe-57 0.0 0.0 -28 9 1 Fe-58 0.0 0.0 -29 9 1 Ni-58 0.0 0.0 -30 9 1 Ni-60 0.0 0.0 -31 9 1 Ni-61 0.0 0.0 -32 9 1 Ni-62 0.0 0.0 -33 9 1 Ni-64 0.0 0.0 -34 9 1 Mn-55 0.0 0.0 -35 9 1 Si-28 0.0 0.0 -36 9 1 Si-29 0.0 0.0 -37 9 1 Si-30 0.0 0.0 -38 9 1 Cr-50 0.0 0.0 -39 9 1 Cr-52 0.0 0.0 -40 9 1 Cr-53 0.0 0.0 -41 9 1 Cr-54 0.0 0.0 -0 9 2 H-1 0.0 0.0 -1 9 2 O-16 0.0 0.0 -2 9 2 B-10 0.0 0.0 -3 9 2 B-11 0.0 0.0 -4 9 2 Fe-54 0.0 0.0 -5 9 2 Fe-56 0.0 0.0 -6 9 2 Fe-57 0.0 0.0 -7 9 2 Fe-58 0.0 0.0 -8 9 2 Ni-58 0.0 0.0 -9 9 2 Ni-60 0.0 0.0 -10 9 2 Ni-61 0.0 0.0 -11 9 2 Ni-62 0.0 0.0 -12 9 2 Ni-64 0.0 0.0 -13 9 2 Mn-55 0.0 0.0 -14 9 2 Si-28 0.0 0.0 -15 9 2 Si-29 0.0 0.0 -16 9 2 Si-30 0.0 0.0 -17 9 2 Cr-50 0.0 0.0 -18 9 2 Cr-52 0.0 0.0 -19 9 2 Cr-53 0.0 0.0 -20 9 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 9 1 1 H-1 0.150655 0.480993 -64 9 1 1 O-16 0.116221 0.114089 -65 9 1 1 B-10 0.000000 0.000000 -66 9 1 1 B-11 0.000000 0.000000 -67 9 1 1 Fe-54 0.000000 0.000000 -68 9 1 1 Fe-56 0.186217 0.199795 -69 9 1 1 Fe-57 0.000000 0.000000 -70 9 1 1 Fe-58 0.000000 0.000000 -71 9 1 1 Ni-58 0.000000 0.000000 -72 9 1 1 Ni-60 0.000000 0.000000 -73 9 1 1 Ni-61 0.000000 0.000000 -74 9 1 1 Ni-62 0.000000 0.000000 -75 9 1 1 Ni-64 0.000000 0.000000 -76 9 1 1 Mn-55 0.000000 0.000000 -77 9 1 1 Si-28 0.000000 0.000000 -78 9 1 1 Si-29 0.000000 0.000000 -79 9 1 1 Si-30 0.000000 0.000000 -80 9 1 1 Cr-50 0.000000 0.000000 -81 9 1 1 Cr-52 0.000000 0.000000 -82 9 1 1 Cr-53 0.147443 0.139574 -83 9 1 1 Cr-54 0.000000 0.000000 -42 9 1 2 H-1 0.000000 0.000000 -43 9 1 2 O-16 0.000000 0.000000 -44 9 1 2 B-10 0.000000 0.000000 -45 9 1 2 B-11 0.000000 0.000000 -46 9 1 2 Fe-54 0.000000 0.000000 -47 9 1 2 Fe-56 0.000000 0.000000 -48 9 1 2 Fe-57 0.000000 0.000000 -49 9 1 2 Fe-58 0.000000 0.000000 -50 9 1 2 Ni-58 0.000000 0.000000 -51 9 1 2 Ni-60 0.000000 0.000000 -52 9 1 2 Ni-61 0.000000 0.000000 -53 9 1 2 Ni-62 0.000000 0.000000 -54 9 1 2 Ni-64 0.000000 0.000000 -55 9 1 2 Mn-55 0.000000 0.000000 -56 9 1 2 Si-28 0.000000 0.000000 -57 9 1 2 Si-29 0.000000 0.000000 -58 9 1 2 Si-30 0.000000 0.000000 -59 9 1 2 Cr-50 0.000000 0.000000 -60 9 1 2 Cr-52 0.000000 0.000000 -61 9 1 2 Cr-53 0.000000 0.000000 -62 9 1 2 Cr-54 0.000000 0.000000 -21 9 2 1 H-1 0.000000 0.000000 -22 9 2 1 O-16 0.000000 0.000000 -23 9 2 1 B-10 0.000000 0.000000 -24 9 2 1 B-11 0.000000 0.000000 -25 9 2 1 Fe-54 0.000000 0.000000 -26 9 2 1 Fe-56 0.000000 0.000000 -27 9 2 1 Fe-57 0.000000 0.000000 -28 9 2 1 Fe-58 0.000000 0.000000 -29 9 2 1 Ni-58 0.000000 0.000000 -30 9 2 1 Ni-60 0.000000 0.000000 -31 9 2 1 Ni-61 0.000000 0.000000 -32 9 2 1 Ni-62 0.000000 0.000000 -33 9 2 1 Ni-64 0.000000 0.000000 -34 9 2 1 Mn-55 0.000000 0.000000 -35 9 2 1 Si-28 0.000000 0.000000 -36 9 2 1 Si-29 0.000000 0.000000 -37 9 2 1 Si-30 0.000000 0.000000 -38 9 2 1 Cr-50 0.000000 0.000000 -39 9 2 1 Cr-52 0.000000 0.000000 -40 9 2 1 Cr-53 0.000000 0.000000 -41 9 2 1 Cr-54 0.000000 0.000000 -0 9 2 2 H-1 0.000000 0.000000 -1 9 2 2 O-16 0.000000 0.000000 -2 9 2 2 B-10 0.000000 0.000000 -3 9 2 2 B-11 0.000000 0.000000 -4 9 2 2 Fe-54 0.000000 0.000000 -5 9 2 2 Fe-56 0.000000 0.000000 -6 9 2 2 Fe-57 0.000000 0.000000 -7 9 2 2 Fe-58 0.000000 0.000000 -8 9 2 2 Ni-58 0.000000 0.000000 -9 9 2 2 Ni-60 0.000000 0.000000 -10 9 2 2 Ni-61 0.000000 0.000000 -11 9 2 2 Ni-62 0.000000 0.000000 -12 9 2 2 Ni-64 0.000000 0.000000 -13 9 2 2 Mn-55 0.000000 0.000000 -14 9 2 2 Si-28 0.000000 0.000000 -15 9 2 2 Si-29 0.000000 0.000000 -16 9 2 2 Si-30 0.000000 0.000000 -17 9 2 2 Cr-50 0.000000 0.000000 -18 9 2 2 Cr-52 0.000000 0.000000 -19 9 2 2 Cr-53 0.000000 0.000000 -20 9 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. -21 9 1 H-1 0.0 0.0 -22 9 1 O-16 0.0 0.0 -23 9 1 B-10 0.0 0.0 -24 9 1 B-11 0.0 0.0 -25 9 1 Fe-54 0.0 0.0 -26 9 1 Fe-56 0.0 0.0 -27 9 1 Fe-57 0.0 0.0 -28 9 1 Fe-58 0.0 0.0 -29 9 1 Ni-58 0.0 0.0 -30 9 1 Ni-60 0.0 0.0 -31 9 1 Ni-61 0.0 0.0 -32 9 1 Ni-62 0.0 0.0 -33 9 1 Ni-64 0.0 0.0 -34 9 1 Mn-55 0.0 0.0 -35 9 1 Si-28 0.0 0.0 -36 9 1 Si-29 0.0 0.0 -37 9 1 Si-30 0.0 0.0 -38 9 1 Cr-50 0.0 0.0 -39 9 1 Cr-52 0.0 0.0 -40 9 1 Cr-53 0.0 0.0 -41 9 1 Cr-54 0.0 0.0 -0 9 2 H-1 0.0 0.0 -1 9 2 O-16 0.0 0.0 -2 9 2 B-10 0.0 0.0 -3 9 2 B-11 0.0 0.0 -4 9 2 Fe-54 0.0 0.0 -5 9 2 Fe-56 0.0 0.0 -6 9 2 Fe-57 0.0 0.0 -7 9 2 Fe-58 0.0 0.0 -8 9 2 Ni-58 0.0 0.0 -9 9 2 Ni-60 0.0 0.0 -10 9 2 Ni-61 0.0 0.0 -11 9 2 Ni-62 0.0 0.0 -12 9 2 Ni-64 0.0 0.0 -13 9 2 Mn-55 0.0 0.0 -14 9 2 Si-28 0.0 0.0 -15 9 2 Si-29 0.0 0.0 -16 9 2 Si-30 0.0 0.0 -17 9 2 Cr-50 0.0 0.0 -18 9 2 Cr-52 0.0 0.0 -19 9 2 Cr-53 0.0 0.0 -20 9 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 10 1 H-1 0.123944 0.541390 -22 10 1 O-16 0.000000 0.000000 -23 10 1 B-10 0.000000 0.000000 -24 10 1 B-11 0.000000 0.000000 -25 10 1 Fe-54 0.000000 0.000000 -26 10 1 Fe-56 0.000000 0.000000 -27 10 1 Fe-57 0.000000 0.000000 -28 10 1 Fe-58 0.000000 0.000000 -29 10 1 Ni-58 0.000000 0.000000 -30 10 1 Ni-60 0.000000 0.000000 -31 10 1 Ni-61 0.000000 0.000000 -32 10 1 Ni-62 0.000000 0.000000 -33 10 1 Ni-64 0.000000 0.000000 -34 10 1 Mn-55 0.000000 0.000000 -35 10 1 Si-28 0.000000 0.000000 -36 10 1 Si-29 0.000000 0.000000 -37 10 1 Si-30 0.000000 0.000000 -38 10 1 Cr-50 0.111571 0.138458 -39 10 1 Cr-52 0.000000 0.000000 -40 10 1 Cr-53 0.000000 0.000000 -41 10 1 Cr-54 0.000000 0.000000 -0 10 2 H-1 0.000000 0.000000 -1 10 2 O-16 0.000000 0.000000 -2 10 2 B-10 0.000000 0.000000 -3 10 2 B-11 0.000000 0.000000 -4 10 2 Fe-54 0.000000 0.000000 -5 10 2 Fe-56 0.000000 0.000000 -6 10 2 Fe-57 0.000000 0.000000 -7 10 2 Fe-58 0.000000 0.000000 -8 10 2 Ni-58 0.000000 0.000000 -9 10 2 Ni-60 0.000000 0.000000 -10 10 2 Ni-61 0.000000 0.000000 -11 10 2 Ni-62 0.000000 0.000000 -12 10 2 Ni-64 0.000000 0.000000 -13 10 2 Mn-55 0.000000 0.000000 -14 10 2 Si-28 0.000000 0.000000 -15 10 2 Si-29 0.000000 0.000000 -16 10 2 Si-30 0.000000 0.000000 -17 10 2 Cr-50 0.000000 0.000000 -18 10 2 Cr-52 0.000000 0.000000 -19 10 2 Cr-53 0.000000 0.000000 -20 10 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 10 1 H-1 0.0 0.0 -22 10 1 O-16 0.0 0.0 -23 10 1 B-10 0.0 0.0 -24 10 1 B-11 0.0 0.0 -25 10 1 Fe-54 0.0 0.0 -26 10 1 Fe-56 0.0 0.0 -27 10 1 Fe-57 0.0 0.0 -28 10 1 Fe-58 0.0 0.0 -29 10 1 Ni-58 0.0 0.0 -30 10 1 Ni-60 0.0 0.0 -31 10 1 Ni-61 0.0 0.0 -32 10 1 Ni-62 0.0 0.0 -33 10 1 Ni-64 0.0 0.0 -34 10 1 Mn-55 0.0 0.0 -35 10 1 Si-28 0.0 0.0 -36 10 1 Si-29 0.0 0.0 -37 10 1 Si-30 0.0 0.0 -38 10 1 Cr-50 0.0 0.0 -39 10 1 Cr-52 0.0 0.0 -40 10 1 Cr-53 0.0 0.0 -41 10 1 Cr-54 0.0 0.0 -0 10 2 H-1 0.0 0.0 -1 10 2 O-16 0.0 0.0 -2 10 2 B-10 0.0 0.0 -3 10 2 B-11 0.0 0.0 -4 10 2 Fe-54 0.0 0.0 -5 10 2 Fe-56 0.0 0.0 -6 10 2 Fe-57 0.0 0.0 -7 10 2 Fe-58 0.0 0.0 -8 10 2 Ni-58 0.0 0.0 -9 10 2 Ni-60 0.0 0.0 -10 10 2 Ni-61 0.0 0.0 -11 10 2 Ni-62 0.0 0.0 -12 10 2 Ni-64 0.0 0.0 -13 10 2 Mn-55 0.0 0.0 -14 10 2 Si-28 0.0 0.0 -15 10 2 Si-29 0.0 0.0 -16 10 2 Si-30 0.0 0.0 -17 10 2 Cr-50 0.0 0.0 -18 10 2 Cr-52 0.0 0.0 -19 10 2 Cr-53 0.0 0.0 -20 10 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 10 1 1 H-1 0.123944 0.541390 -64 10 1 1 O-16 0.000000 0.000000 -65 10 1 1 B-10 0.000000 0.000000 -66 10 1 1 B-11 0.000000 0.000000 -67 10 1 1 Fe-54 0.000000 0.000000 -68 10 1 1 Fe-56 0.000000 0.000000 -69 10 1 1 Fe-57 0.000000 0.000000 -70 10 1 1 Fe-58 0.000000 0.000000 -71 10 1 1 Ni-58 0.000000 0.000000 -72 10 1 1 Ni-60 0.000000 0.000000 -73 10 1 1 Ni-61 0.000000 0.000000 -74 10 1 1 Ni-62 0.000000 0.000000 -75 10 1 1 Ni-64 0.000000 0.000000 -76 10 1 1 Mn-55 0.000000 0.000000 -77 10 1 1 Si-28 0.000000 0.000000 -78 10 1 1 Si-29 0.000000 0.000000 -79 10 1 1 Si-30 0.000000 0.000000 -80 10 1 1 Cr-50 0.111571 0.138458 -81 10 1 1 Cr-52 0.000000 0.000000 -82 10 1 1 Cr-53 0.000000 0.000000 -83 10 1 1 Cr-54 0.000000 0.000000 -42 10 1 2 H-1 0.000000 0.000000 -43 10 1 2 O-16 0.000000 0.000000 -44 10 1 2 B-10 0.000000 0.000000 -45 10 1 2 B-11 0.000000 0.000000 -46 10 1 2 Fe-54 0.000000 0.000000 -47 10 1 2 Fe-56 0.000000 0.000000 -48 10 1 2 Fe-57 0.000000 0.000000 -49 10 1 2 Fe-58 0.000000 0.000000 -50 10 1 2 Ni-58 0.000000 0.000000 -51 10 1 2 Ni-60 0.000000 0.000000 -52 10 1 2 Ni-61 0.000000 0.000000 -53 10 1 2 Ni-62 0.000000 0.000000 -54 10 1 2 Ni-64 0.000000 0.000000 -55 10 1 2 Mn-55 0.000000 0.000000 -56 10 1 2 Si-28 0.000000 0.000000 -57 10 1 2 Si-29 0.000000 0.000000 -58 10 1 2 Si-30 0.000000 0.000000 -59 10 1 2 Cr-50 0.000000 0.000000 -60 10 1 2 Cr-52 0.000000 0.000000 -61 10 1 2 Cr-53 0.000000 0.000000 -62 10 1 2 Cr-54 0.000000 0.000000 -21 10 2 1 H-1 0.000000 0.000000 -22 10 2 1 O-16 0.000000 0.000000 -23 10 2 1 B-10 0.000000 0.000000 -24 10 2 1 B-11 0.000000 0.000000 -25 10 2 1 Fe-54 0.000000 0.000000 -26 10 2 1 Fe-56 0.000000 0.000000 -27 10 2 1 Fe-57 0.000000 0.000000 -28 10 2 1 Fe-58 0.000000 0.000000 -29 10 2 1 Ni-58 0.000000 0.000000 -30 10 2 1 Ni-60 0.000000 0.000000 -31 10 2 1 Ni-61 0.000000 0.000000 -32 10 2 1 Ni-62 0.000000 0.000000 -33 10 2 1 Ni-64 0.000000 0.000000 -34 10 2 1 Mn-55 0.000000 0.000000 -35 10 2 1 Si-28 0.000000 0.000000 -36 10 2 1 Si-29 0.000000 0.000000 -37 10 2 1 Si-30 0.000000 0.000000 -38 10 2 1 Cr-50 0.000000 0.000000 -39 10 2 1 Cr-52 0.000000 0.000000 -40 10 2 1 Cr-53 0.000000 0.000000 -41 10 2 1 Cr-54 0.000000 0.000000 -0 10 2 2 H-1 0.000000 0.000000 -1 10 2 2 O-16 0.000000 0.000000 -2 10 2 2 B-10 0.000000 0.000000 -3 10 2 2 B-11 0.000000 0.000000 -4 10 2 2 Fe-54 0.000000 0.000000 -5 10 2 2 Fe-56 0.000000 0.000000 -6 10 2 2 Fe-57 0.000000 0.000000 -7 10 2 2 Fe-58 0.000000 0.000000 -8 10 2 2 Ni-58 0.000000 0.000000 -9 10 2 2 Ni-60 0.000000 0.000000 -10 10 2 2 Ni-61 0.000000 0.000000 -11 10 2 2 Ni-62 0.000000 0.000000 -12 10 2 2 Ni-64 0.000000 0.000000 -13 10 2 2 Mn-55 0.000000 0.000000 -14 10 2 2 Si-28 0.000000 0.000000 -15 10 2 2 Si-29 0.000000 0.000000 -16 10 2 2 Si-30 0.000000 0.000000 -17 10 2 2 Cr-50 0.000000 0.000000 -18 10 2 2 Cr-52 0.000000 0.000000 -19 10 2 2 Cr-53 0.000000 0.000000 -20 10 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. -21 10 1 H-1 0.0 0.0 -22 10 1 O-16 0.0 0.0 -23 10 1 B-10 0.0 0.0 -24 10 1 B-11 0.0 0.0 -25 10 1 Fe-54 0.0 0.0 -26 10 1 Fe-56 0.0 0.0 -27 10 1 Fe-57 0.0 0.0 -28 10 1 Fe-58 0.0 0.0 -29 10 1 Ni-58 0.0 0.0 -30 10 1 Ni-60 0.0 0.0 -31 10 1 Ni-61 0.0 0.0 -32 10 1 Ni-62 0.0 0.0 -33 10 1 Ni-64 0.0 0.0 -34 10 1 Mn-55 0.0 0.0 -35 10 1 Si-28 0.0 0.0 -36 10 1 Si-29 0.0 0.0 -37 10 1 Si-30 0.0 0.0 -38 10 1 Cr-50 0.0 0.0 -39 10 1 Cr-52 0.0 0.0 -40 10 1 Cr-53 0.0 0.0 -41 10 1 Cr-54 0.0 0.0 -0 10 2 H-1 0.0 0.0 -1 10 2 O-16 0.0 0.0 -2 10 2 B-10 0.0 0.0 -3 10 2 B-11 0.0 0.0 -4 10 2 Fe-54 0.0 0.0 -5 10 2 Fe-56 0.0 0.0 -6 10 2 Fe-57 0.0 0.0 -7 10 2 Fe-58 0.0 0.0 -8 10 2 Ni-58 0.0 0.0 -9 10 2 Ni-60 0.0 0.0 -10 10 2 Ni-61 0.0 0.0 -11 10 2 Ni-62 0.0 0.0 -12 10 2 Ni-64 0.0 0.0 -13 10 2 Mn-55 0.0 0.0 -14 10 2 Si-28 0.0 0.0 -15 10 2 Si-29 0.0 0.0 -16 10 2 Si-30 0.0 0.0 -17 10 2 Cr-50 0.0 0.0 -18 10 2 Cr-52 0.0 0.0 -19 10 2 Cr-53 0.0 0.0 -20 10 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -9 11 1 H-1 0.131470 0.476035 -10 11 1 O-16 0.028684 0.043000 -11 11 1 B-10 0.000000 0.000000 -12 11 1 B-11 0.000000 0.000000 -13 11 1 Zr-90 0.021980 0.039963 -14 11 1 Zr-91 0.000000 0.000000 -15 11 1 Zr-92 0.000000 0.000000 -16 11 1 Zr-94 0.004191 0.087344 -17 11 1 Zr-96 0.000000 0.000000 -0 11 2 H-1 0.687243 1.239217 -1 11 2 O-16 0.000000 0.000000 -2 11 2 B-10 0.042902 0.060672 -3 11 2 B-11 0.000000 0.000000 -4 11 2 Zr-90 0.039576 0.105193 -5 11 2 Zr-91 0.000000 0.000000 -6 11 2 Zr-92 0.084226 0.103161 -7 11 2 Zr-94 0.092039 0.125985 -8 11 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 11 1 H-1 0.0 0.0 -10 11 1 O-16 0.0 0.0 -11 11 1 B-10 0.0 0.0 -12 11 1 B-11 0.0 0.0 -13 11 1 Zr-90 0.0 0.0 -14 11 1 Zr-91 0.0 0.0 -15 11 1 Zr-92 0.0 0.0 -16 11 1 Zr-94 0.0 0.0 -17 11 1 Zr-96 0.0 0.0 -0 11 2 H-1 0.0 0.0 -1 11 2 O-16 0.0 0.0 -2 11 2 B-10 0.0 0.0 -3 11 2 B-11 0.0 0.0 -4 11 2 Zr-90 0.0 0.0 -5 11 2 Zr-91 0.0 0.0 -6 11 2 Zr-92 0.0 0.0 -7 11 2 Zr-94 0.0 0.0 -8 11 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -27 11 1 1 H-1 0.099594 0.442578 -28 11 1 1 O-16 0.028684 0.043000 -29 11 1 1 B-10 0.000000 0.000000 -30 11 1 1 B-11 0.000000 0.000000 -31 11 1 1 Zr-90 0.021980 0.039963 -32 11 1 1 Zr-91 0.000000 0.000000 -33 11 1 1 Zr-92 0.000000 0.000000 -34 11 1 1 Zr-94 0.004191 0.087344 -35 11 1 1 Zr-96 0.000000 0.000000 -18 11 1 2 H-1 0.031875 0.045078 -19 11 1 2 O-16 0.000000 0.000000 -20 11 1 2 B-10 0.000000 0.000000 -21 11 1 2 B-11 0.000000 0.000000 -22 11 1 2 Zr-90 0.000000 0.000000 -23 11 1 2 Zr-91 0.000000 0.000000 -24 11 1 2 Zr-92 0.000000 0.000000 -25 11 1 2 Zr-94 0.000000 0.000000 -26 11 1 2 Zr-96 0.000000 0.000000 -9 11 2 1 H-1 0.000000 0.000000 -10 11 2 1 O-16 0.000000 0.000000 -11 11 2 1 B-10 0.000000 0.000000 -12 11 2 1 B-11 0.000000 0.000000 -13 11 2 1 Zr-90 0.000000 0.000000 -14 11 2 1 Zr-91 0.000000 0.000000 -15 11 2 1 Zr-92 0.000000 0.000000 -16 11 2 1 Zr-94 0.000000 0.000000 -17 11 2 1 Zr-96 0.000000 0.000000 -0 11 2 2 H-1 0.687243 1.239217 -1 11 2 2 O-16 0.000000 0.000000 -2 11 2 2 B-10 0.000000 0.000000 -3 11 2 2 B-11 0.000000 0.000000 -4 11 2 2 Zr-90 0.039576 0.105193 -5 11 2 2 Zr-91 0.000000 0.000000 -6 11 2 2 Zr-92 0.084226 0.103161 -7 11 2 2 Zr-94 0.092039 0.125985 -8 11 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -9 11 1 H-1 0.0 0.0 -10 11 1 O-16 0.0 0.0 -11 11 1 B-10 0.0 0.0 -12 11 1 B-11 0.0 0.0 -13 11 1 Zr-90 0.0 0.0 -14 11 1 Zr-91 0.0 0.0 -15 11 1 Zr-92 0.0 0.0 -16 11 1 Zr-94 0.0 0.0 -17 11 1 Zr-96 0.0 0.0 -0 11 2 H-1 0.0 0.0 -1 11 2 O-16 0.0 0.0 -2 11 2 B-10 0.0 0.0 -3 11 2 B-11 0.0 0.0 -4 11 2 Zr-90 0.0 0.0 -5 11 2 Zr-91 0.0 0.0 -6 11 2 Zr-92 0.0 0.0 -7 11 2 Zr-94 0.0 0.0 -8 11 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. -9 12 1 H-1 0.098944 0.178543 -10 12 1 O-16 0.013270 0.020403 -11 12 1 B-10 0.000000 0.000000 -12 12 1 B-11 0.000000 0.000000 -13 12 1 Zr-90 0.089997 0.075538 -14 12 1 Zr-91 0.000000 0.000000 -15 12 1 Zr-92 0.003501 0.017031 -16 12 1 Zr-94 0.004850 0.016327 -17 12 1 Zr-96 0.002730 0.017476 -0 12 2 H-1 1.261686 1.980336 -1 12 2 O-16 0.079159 0.104796 -2 12 2 B-10 0.016928 0.023940 -3 12 2 B-11 0.000000 0.000000 -4 12 2 Zr-90 0.000000 0.000000 -5 12 2 Zr-91 0.033201 0.040665 -6 12 2 Zr-92 0.000000 0.000000 -7 12 2 Zr-94 0.000000 0.000000 -8 12 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 12 1 H-1 0.0 0.0 -10 12 1 O-16 0.0 0.0 -11 12 1 B-10 0.0 0.0 -12 12 1 B-11 0.0 0.0 -13 12 1 Zr-90 0.0 0.0 -14 12 1 Zr-91 0.0 0.0 -15 12 1 Zr-92 0.0 0.0 -16 12 1 Zr-94 0.0 0.0 -17 12 1 Zr-96 0.0 0.0 -0 12 2 H-1 0.0 0.0 -1 12 2 O-16 0.0 0.0 -2 12 2 B-10 0.0 0.0 -3 12 2 B-11 0.0 0.0 -4 12 2 Zr-90 0.0 0.0 -5 12 2 Zr-91 0.0 0.0 -6 12 2 Zr-92 0.0 0.0 -7 12 2 Zr-94 0.0 0.0 -8 12 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -27 12 1 1 H-1 0.071704 0.167588 -28 12 1 1 O-16 0.013270 0.020403 -29 12 1 1 B-10 0.000000 0.000000 -30 12 1 1 B-11 0.000000 0.000000 -31 12 1 1 Zr-90 0.089997 0.075538 -32 12 1 1 Zr-91 0.000000 0.000000 -33 12 1 1 Zr-92 0.003501 0.017031 -34 12 1 1 Zr-94 0.004850 0.016327 -35 12 1 1 Zr-96 0.002730 0.017476 -18 12 1 2 H-1 0.027240 0.029555 -19 12 1 2 O-16 0.000000 0.000000 -20 12 1 2 B-10 0.000000 0.000000 -21 12 1 2 B-11 0.000000 0.000000 -22 12 1 2 Zr-90 0.000000 0.000000 -23 12 1 2 Zr-91 0.000000 0.000000 -24 12 1 2 Zr-92 0.000000 0.000000 -25 12 1 2 Zr-94 0.000000 0.000000 -26 12 1 2 Zr-96 0.000000 0.000000 -9 12 2 1 H-1 0.000000 0.000000 -10 12 2 1 O-16 0.000000 0.000000 -11 12 2 1 B-10 0.000000 0.000000 -12 12 2 1 B-11 0.000000 0.000000 -13 12 2 1 Zr-90 0.000000 0.000000 -14 12 2 1 Zr-91 0.000000 0.000000 -15 12 2 1 Zr-92 0.000000 0.000000 -16 12 2 1 Zr-94 0.000000 0.000000 -17 12 2 1 Zr-96 0.000000 0.000000 -0 12 2 2 H-1 1.244758 1.956675 -1 12 2 2 O-16 0.079159 0.104796 -2 12 2 2 B-10 0.000000 0.000000 -3 12 2 2 B-11 0.000000 0.000000 -4 12 2 2 Zr-90 0.000000 0.000000 -5 12 2 2 Zr-91 0.033201 0.040665 -6 12 2 2 Zr-92 0.000000 0.000000 -7 12 2 2 Zr-94 0.000000 0.000000 -8 12 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -9 12 1 H-1 0.0 0.0 -10 12 1 O-16 0.0 0.0 -11 12 1 B-10 0.0 0.0 -12 12 1 B-11 0.0 0.0 -13 12 1 Zr-90 0.0 0.0 -14 12 1 Zr-91 0.0 0.0 -15 12 1 Zr-92 0.0 0.0 -16 12 1 Zr-94 0.0 0.0 -17 12 1 Zr-96 0.0 0.0 -0 12 2 H-1 0.0 0.0 -1 12 2 O-16 0.0 0.0 -2 12 2 B-10 0.0 0.0 -3 12 2 B-11 0.0 0.0 -4 12 2 Zr-90 0.0 0.0 -5 12 2 Zr-91 0.0 0.0 -6 12 2 Zr-92 0.0 0.0 -7 12 2 Zr-94 0.0 0.0 -8 12 2 Zr-96 0.0 0.0 \ No newline at end of file + material group in nuclide score mean std. dev. +34 1 1 U-234 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 +35 1 1 U-235 ((total - scatter-1) / flux) 1.07e-02 1.89e-03 +36 1 1 U-236 ((total - scatter-1) / flux) 2.39e-03 1.06e-03 +37 1 1 U-238 ((total - scatter-1) / flux) 2.14e-01 1.33e-02 +38 1 1 Np-237 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 1 1 Pu-238 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 1 1 Pu-239 ((total - scatter-1) / flux) 2.91e-03 6.39e-04 +41 1 1 Pu-240 ((total - scatter-1) / flux) 4.43e-03 8.06e-04 +42 1 1 Pu-241 ((total - scatter-1) / flux) 6.90e-04 3.87e-04 +43 1 1 Pu-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +44 1 1 Am-241 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 +45 1 1 Am-242m ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +46 1 1 Am-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +47 1 1 Cm-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +48 1 1 Cm-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +49 1 1 Cm-244 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +50 1 1 Cm-245 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +51 1 1 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +52 1 1 Tc-99 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 +53 1 1 Ru-101 ((total - scatter-1) / flux) 2.38e-04 2.54e-04 +54 1 1 Ru-103 ((total - scatter-1) / flux) 2.26e-06 2.43e-04 +55 1 1 Ag-109 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +56 1 1 Xe-135 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +57 1 1 Cs-133 ((total - scatter-1) / flux) 3.47e-04 2.13e-04 +58 1 1 Nd-143 ((total - scatter-1) / flux) 4.47e-04 2.92e-04 +59 1 1 Nd-145 ((total - scatter-1) / flux) 5.64e-04 2.94e-04 +60 1 1 Sm-147 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +61 1 1 Sm-149 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +62 1 1 Sm-150 ((total - scatter-1) / flux) 4.72e-04 2.39e-04 +63 1 1 Sm-151 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +64 1 1 Sm-152 ((total - scatter-1) / flux) 4.92e-04 3.52e-04 +65 1 1 Eu-153 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 +66 1 1 Gd-155 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +67 1 1 O-16 ((total - scatter-1) / flux) 1.35e-01 9.80e-03 +0 1 2 U-234 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 1 2 U-235 ((total - scatter-1) / flux) 2.00e-01 7.78e-03 +2 1 2 U-236 ((total - scatter-1) / flux) 1.50e-03 2.04e-03 +3 1 2 U-238 ((total - scatter-1) / flux) 2.55e-01 2.97e-02 +4 1 2 Np-237 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 1 2 Pu-238 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 1 2 Pu-239 ((total - scatter-1) / flux) 1.60e-01 1.14e-02 +7 1 2 Pu-240 ((total - scatter-1) / flux) 7.92e-03 3.71e-03 +8 1 2 Pu-241 ((total - scatter-1) / flux) 1.78e-02 3.73e-03 +9 1 2 Pu-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 1 2 Am-241 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 1 2 Am-242m ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 1 2 Am-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 1 2 Cm-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 1 2 Cm-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 1 2 Cm-244 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 1 2 Cm-245 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 1 2 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 1 2 Tc-99 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 1 2 Ru-101 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 1 2 Ru-103 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +21 1 2 Ag-109 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +22 1 2 Xe-135 ((total - scatter-1) / flux) 1.39e-02 3.98e-03 +23 1 2 Cs-133 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 1 2 Nd-143 ((total - scatter-1) / flux) 3.96e-03 2.43e-03 +25 1 2 Nd-145 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 1 2 Sm-147 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +27 1 2 Sm-149 ((total - scatter-1) / flux) 1.98e-03 1.98e-03 +28 1 2 Sm-150 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 1 2 Sm-151 ((total - scatter-1) / flux) 1.98e-03 1.98e-03 +30 1 2 Sm-152 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 1 2 Eu-153 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 1 2 Gd-155 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 1 2 O-16 ((total - scatter-1) / flux) 1.97e-01 1.47e-02 material group in nuclide score mean std. dev. +34 1 1 U-234 (nu-fission / flux) 7.27e-06 4.42e-07 +35 1 1 U-235 (nu-fission / flux) 9.59e-03 5.94e-04 +36 1 1 U-236 (nu-fission / flux) 7.57e-05 7.52e-06 +37 1 1 U-238 (nu-fission / flux) 7.18e-03 6.51e-04 +38 1 1 Np-237 (nu-fission / flux) 1.32e-05 8.04e-07 +39 1 1 Pu-238 (nu-fission / flux) 7.75e-06 3.99e-07 +40 1 1 Pu-239 (nu-fission / flux) 3.81e-03 3.64e-04 +41 1 1 Pu-240 (nu-fission / flux) 6.94e-05 4.73e-06 +42 1 1 Pu-241 (nu-fission / flux) 1.03e-03 9.08e-05 +43 1 1 Pu-242 (nu-fission / flux) 6.00e-06 3.82e-07 +44 1 1 Am-241 (nu-fission / flux) 1.15e-06 8.27e-08 +45 1 1 Am-242m (nu-fission / flux) 1.10e-06 6.16e-08 +46 1 1 Am-243 (nu-fission / flux) 8.32e-07 5.84e-08 +47 1 1 Cm-242 (nu-fission / flux) 5.09e-07 5.26e-08 +48 1 1 Cm-243 (nu-fission / flux) 2.25e-07 1.46e-08 +49 1 1 Cm-244 (nu-fission / flux) 2.99e-07 2.75e-08 +50 1 1 Cm-245 (nu-fission / flux) 3.06e-07 3.06e-08 +51 1 1 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 +52 1 1 Tc-99 (nu-fission / flux) 0.00e+00 0.00e+00 +53 1 1 Ru-101 (nu-fission / flux) 0.00e+00 0.00e+00 +54 1 1 Ru-103 (nu-fission / flux) 0.00e+00 0.00e+00 +55 1 1 Ag-109 (nu-fission / flux) 0.00e+00 0.00e+00 +56 1 1 Xe-135 (nu-fission / flux) 0.00e+00 0.00e+00 +57 1 1 Cs-133 (nu-fission / flux) 0.00e+00 0.00e+00 +58 1 1 Nd-143 (nu-fission / flux) 0.00e+00 0.00e+00 +59 1 1 Nd-145 (nu-fission / flux) 0.00e+00 0.00e+00 +60 1 1 Sm-147 (nu-fission / flux) 0.00e+00 0.00e+00 +61 1 1 Sm-149 (nu-fission / flux) 0.00e+00 0.00e+00 +62 1 1 Sm-150 (nu-fission / flux) 0.00e+00 0.00e+00 +63 1 1 Sm-151 (nu-fission / flux) 0.00e+00 0.00e+00 +64 1 1 Sm-152 (nu-fission / flux) 0.00e+00 0.00e+00 +65 1 1 Eu-153 (nu-fission / flux) 0.00e+00 0.00e+00 +66 1 1 Gd-155 (nu-fission / flux) 0.00e+00 0.00e+00 +67 1 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +0 1 2 U-234 (nu-fission / flux) 4.41e-07 2.83e-08 +1 1 2 U-235 (nu-fission / flux) 3.77e-01 2.45e-02 +2 1 2 U-236 (nu-fission / flux) 6.10e-06 3.73e-07 +3 1 2 U-238 (nu-fission / flux) 5.35e-07 3.31e-08 +4 1 2 Np-237 (nu-fission / flux) 2.70e-07 2.10e-08 +5 1 2 Pu-238 (nu-fission / flux) 3.46e-05 2.64e-06 +6 1 2 Pu-239 (nu-fission / flux) 2.89e-01 1.38e-02 +7 1 2 Pu-240 (nu-fission / flux) 4.53e-06 2.54e-07 +8 1 2 Pu-241 (nu-fission / flux) 4.81e-02 2.78e-03 +9 1 2 Pu-242 (nu-fission / flux) 8.72e-08 5.46e-09 +10 1 2 Am-241 (nu-fission / flux) 4.61e-06 2.16e-07 +11 1 2 Am-242m (nu-fission / flux) 1.43e-04 8.44e-06 +12 1 2 Am-243 (nu-fission / flux) 7.88e-08 4.73e-09 +13 1 2 Cm-242 (nu-fission / flux) 9.73e-07 6.14e-08 +14 1 2 Cm-243 (nu-fission / flux) 1.83e-06 1.07e-07 +15 1 2 Cm-244 (nu-fission / flux) 1.58e-07 9.94e-09 +16 1 2 Cm-245 (nu-fission / flux) 1.21e-05 8.81e-07 +17 1 2 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 +18 1 2 Tc-99 (nu-fission / flux) 0.00e+00 0.00e+00 +19 1 2 Ru-101 (nu-fission / flux) 0.00e+00 0.00e+00 +20 1 2 Ru-103 (nu-fission / flux) 0.00e+00 0.00e+00 +21 1 2 Ag-109 (nu-fission / flux) 0.00e+00 0.00e+00 +22 1 2 Xe-135 (nu-fission / flux) 0.00e+00 0.00e+00 +23 1 2 Cs-133 (nu-fission / flux) 0.00e+00 0.00e+00 +24 1 2 Nd-143 (nu-fission / flux) 0.00e+00 0.00e+00 +25 1 2 Nd-145 (nu-fission / flux) 0.00e+00 0.00e+00 +26 1 2 Sm-147 (nu-fission / flux) 0.00e+00 0.00e+00 +27 1 2 Sm-149 (nu-fission / flux) 0.00e+00 0.00e+00 +28 1 2 Sm-150 (nu-fission / flux) 0.00e+00 0.00e+00 +29 1 2 Sm-151 (nu-fission / flux) 0.00e+00 0.00e+00 +30 1 2 Sm-152 (nu-fission / flux) 0.00e+00 0.00e+00 +31 1 2 Eu-153 (nu-fission / flux) 0.00e+00 0.00e+00 +32 1 2 Gd-155 (nu-fission / flux) 0.00e+00 0.00e+00 +33 1 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +102 1 1 1 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +103 1 1 1 U-235 ((nu-scatter-0 - scatter-1) / flux) 3.23e-03 1.14e-03 +104 1 1 1 U-236 ((nu-scatter-0 - scatter-1) / flux) 1.70e-03 9.23e-04 +105 1 1 1 U-238 ((nu-scatter-0 - scatter-1) / flux) 1.95e-01 1.33e-02 +106 1 1 1 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +107 1 1 1 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +108 1 1 1 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 1.01e-03 4.77e-04 +109 1 1 1 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 1.31e-03 2.95e-04 +110 1 1 1 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 3.44e-04 2.44e-04 +111 1 1 1 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +112 1 1 1 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +113 1 1 1 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +114 1 1 1 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +115 1 1 1 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +116 1 1 1 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +117 1 1 1 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +118 1 1 1 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +119 1 1 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +120 1 1 1 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +121 1 1 1 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 2.38e-04 2.54e-04 +122 1 1 1 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 2.26e-06 2.43e-04 +123 1 1 1 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +124 1 1 1 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +125 1 1 1 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +126 1 1 1 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 4.47e-04 2.92e-04 +127 1 1 1 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 5.64e-04 2.94e-04 +128 1 1 1 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +129 1 1 1 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +130 1 1 1 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 2.99e-04 2.38e-04 +131 1 1 1 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +132 1 1 1 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 4.92e-04 3.52e-04 +133 1 1 1 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +134 1 1 1 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +135 1 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.33e-01 9.82e-03 +68 1 1 2 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 1 1 2 U-235 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 1 1 2 U-236 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 1 1 2 U-238 ((nu-scatter-0 - scatter-1) / flux) 1.73e-04 1.73e-04 +72 1 1 2 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 1 1 2 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 1 1 2 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 1 1 2 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 1 1 2 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 1 1 2 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 1 1 2 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 1 1 2 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 1 1 2 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +81 1 1 2 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 1 1 2 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 1 1 2 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +84 1 1 2 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +85 1 1 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +86 1 1 2 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +87 1 1 2 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +88 1 1 2 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +89 1 1 2 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +90 1 1 2 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +91 1 1 2 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +92 1 1 2 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +93 1 1 2 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +94 1 1 2 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +95 1 1 2 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +96 1 1 2 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +97 1 1 2 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +98 1 1 2 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +99 1 1 2 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +100 1 1 2 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +101 1 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.39e-03 4.46e-04 +34 1 2 1 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 1 2 1 U-235 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 1 2 1 U-236 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 1 2 1 U-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 1 2 1 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 1 2 1 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 1 2 1 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 1 2 1 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 1 2 1 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 1 2 1 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 1 2 1 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 1 2 1 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 1 2 1 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 1 2 1 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 1 2 1 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 1 2 1 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 1 2 1 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 1 2 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 1 2 1 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 1 2 1 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 1 2 1 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 1 2 1 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 1 2 1 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 1 2 1 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 1 2 1 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 1 2 1 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 1 2 1 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 1 2 1 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 1 2 1 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +63 1 2 1 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +64 1 2 1 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 1 2 1 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 1 2 1 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 1 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 1 2 2 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 1 2 2 U-235 ((nu-scatter-0 - scatter-1) / flux) 3.89e-03 3.96e-03 +2 1 2 2 U-236 ((nu-scatter-0 - scatter-1) / flux) 1.50e-03 2.04e-03 +3 1 2 2 U-238 ((nu-scatter-0 - scatter-1) / flux) 2.20e-01 2.60e-02 +4 1 2 2 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 1 2 2 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 1 2 2 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 1 2 2 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 1 2 2 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 1 2 2 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 1 2 2 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 1 2 2 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 1 2 2 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 1 2 2 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 1 2 2 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 1 2 2 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 1 2 2 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 1 2 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 1 2 2 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 1 2 2 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 1 2 2 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 1 2 2 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 1 2 2 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 1 2 2 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 1 2 2 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 1 2 2 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 1 2 2 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 1 2 2 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 1 2 2 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 1 2 2 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 1 2 2 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 1 2 2 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 1 2 2 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 1 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.97e-01 1.47e-02 material group out nuclide score mean std. dev. +34 1 1 U-234 nu-fission 0.00e+00 0.00e+00 +35 1 1 U-235 nu-fission 1.00e+00 6.64e-02 +36 1 1 U-236 nu-fission 0.00e+00 0.00e+00 +37 1 1 U-238 nu-fission 1.00e+00 9.31e-02 +38 1 1 Np-237 nu-fission 0.00e+00 0.00e+00 +39 1 1 Pu-238 nu-fission 0.00e+00 0.00e+00 +40 1 1 Pu-239 nu-fission 1.00e+00 1.05e-01 +41 1 1 Pu-240 nu-fission 0.00e+00 0.00e+00 +42 1 1 Pu-241 nu-fission 1.00e+00 2.64e-01 +43 1 1 Pu-242 nu-fission 0.00e+00 0.00e+00 +44 1 1 Am-241 nu-fission 0.00e+00 0.00e+00 +45 1 1 Am-242m nu-fission 0.00e+00 0.00e+00 +46 1 1 Am-243 nu-fission 0.00e+00 0.00e+00 +47 1 1 Cm-242 nu-fission 0.00e+00 0.00e+00 +48 1 1 Cm-243 nu-fission 0.00e+00 0.00e+00 +49 1 1 Cm-244 nu-fission 0.00e+00 0.00e+00 +50 1 1 Cm-245 nu-fission 0.00e+00 0.00e+00 +51 1 1 Mo-95 nu-fission 0.00e+00 0.00e+00 +52 1 1 Tc-99 nu-fission 0.00e+00 0.00e+00 +53 1 1 Ru-101 nu-fission 0.00e+00 0.00e+00 +54 1 1 Ru-103 nu-fission 0.00e+00 0.00e+00 +55 1 1 Ag-109 nu-fission 0.00e+00 0.00e+00 +56 1 1 Xe-135 nu-fission 0.00e+00 0.00e+00 +57 1 1 Cs-133 nu-fission 0.00e+00 0.00e+00 +58 1 1 Nd-143 nu-fission 0.00e+00 0.00e+00 +59 1 1 Nd-145 nu-fission 0.00e+00 0.00e+00 +60 1 1 Sm-147 nu-fission 0.00e+00 0.00e+00 +61 1 1 Sm-149 nu-fission 0.00e+00 0.00e+00 +62 1 1 Sm-150 nu-fission 0.00e+00 0.00e+00 +63 1 1 Sm-151 nu-fission 0.00e+00 0.00e+00 +64 1 1 Sm-152 nu-fission 0.00e+00 0.00e+00 +65 1 1 Eu-153 nu-fission 0.00e+00 0.00e+00 +66 1 1 Gd-155 nu-fission 0.00e+00 0.00e+00 +67 1 1 O-16 nu-fission 0.00e+00 0.00e+00 +0 1 2 U-234 nu-fission 0.00e+00 0.00e+00 +1 1 2 U-235 nu-fission 0.00e+00 0.00e+00 +2 1 2 U-236 nu-fission 0.00e+00 0.00e+00 +3 1 2 U-238 nu-fission 0.00e+00 0.00e+00 +4 1 2 Np-237 nu-fission 0.00e+00 0.00e+00 +5 1 2 Pu-238 nu-fission 0.00e+00 0.00e+00 +6 1 2 Pu-239 nu-fission 0.00e+00 0.00e+00 +7 1 2 Pu-240 nu-fission 0.00e+00 0.00e+00 +8 1 2 Pu-241 nu-fission 0.00e+00 0.00e+00 +9 1 2 Pu-242 nu-fission 0.00e+00 0.00e+00 +10 1 2 Am-241 nu-fission 0.00e+00 0.00e+00 +11 1 2 Am-242m nu-fission 0.00e+00 0.00e+00 +12 1 2 Am-243 nu-fission 0.00e+00 0.00e+00 +13 1 2 Cm-242 nu-fission 0.00e+00 0.00e+00 +14 1 2 Cm-243 nu-fission 0.00e+00 0.00e+00 +15 1 2 Cm-244 nu-fission 0.00e+00 0.00e+00 +16 1 2 Cm-245 nu-fission 0.00e+00 0.00e+00 +17 1 2 Mo-95 nu-fission 0.00e+00 0.00e+00 +18 1 2 Tc-99 nu-fission 0.00e+00 0.00e+00 +19 1 2 Ru-101 nu-fission 0.00e+00 0.00e+00 +20 1 2 Ru-103 nu-fission 0.00e+00 0.00e+00 +21 1 2 Ag-109 nu-fission 0.00e+00 0.00e+00 +22 1 2 Xe-135 nu-fission 0.00e+00 0.00e+00 +23 1 2 Cs-133 nu-fission 0.00e+00 0.00e+00 +24 1 2 Nd-143 nu-fission 0.00e+00 0.00e+00 +25 1 2 Nd-145 nu-fission 0.00e+00 0.00e+00 +26 1 2 Sm-147 nu-fission 0.00e+00 0.00e+00 +27 1 2 Sm-149 nu-fission 0.00e+00 0.00e+00 +28 1 2 Sm-150 nu-fission 0.00e+00 0.00e+00 +29 1 2 Sm-151 nu-fission 0.00e+00 0.00e+00 +30 1 2 Sm-152 nu-fission 0.00e+00 0.00e+00 +31 1 2 Eu-153 nu-fission 0.00e+00 0.00e+00 +32 1 2 Gd-155 nu-fission 0.00e+00 0.00e+00 +33 1 2 O-16 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +5 2 1 Zr-90 ((total - scatter-1) / flux) 1.05e-01 8.92e-03 +6 2 1 Zr-91 ((total - scatter-1) / flux) 3.62e-02 3.74e-03 +7 2 1 Zr-92 ((total - scatter-1) / flux) 4.24e-02 3.03e-03 +8 2 1 Zr-94 ((total - scatter-1) / flux) 4.61e-02 6.25e-03 +9 2 1 Zr-96 ((total - scatter-1) / flux) 7.79e-03 1.54e-03 +0 2 2 Zr-90 ((total - scatter-1) / flux) 1.22e-01 3.49e-02 +1 2 2 Zr-91 ((total - scatter-1) / flux) 6.18e-02 2.43e-02 +2 2 2 Zr-92 ((total - scatter-1) / flux) 4.16e-02 1.63e-02 +3 2 2 Zr-94 ((total - scatter-1) / flux) 6.08e-02 2.15e-02 +4 2 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +5 2 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +6 2 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +7 2 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +8 2 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +9 2 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 +0 2 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +1 2 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +2 2 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +3 2 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +4 2 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +15 2 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 1.05e-01 8.92e-03 +16 2 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 3.62e-02 3.74e-03 +17 2 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 4.24e-02 3.03e-03 +18 2 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.61e-02 6.25e-03 +19 2 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 7.79e-03 1.54e-03 +10 2 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 2 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 2 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 2 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 2 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 2 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 2 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 2 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 2 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 2 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 2 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 1.22e-01 3.49e-02 +1 2 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 6.18e-02 2.43e-02 +2 2 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 4.16e-02 1.63e-02 +3 2 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 6.08e-02 2.15e-02 +4 2 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +5 2 1 Zr-90 nu-fission 0.00e+00 0.00e+00 +6 2 1 Zr-91 nu-fission 0.00e+00 0.00e+00 +7 2 1 Zr-92 nu-fission 0.00e+00 0.00e+00 +8 2 1 Zr-94 nu-fission 0.00e+00 0.00e+00 +9 2 1 Zr-96 nu-fission 0.00e+00 0.00e+00 +0 2 2 Zr-90 nu-fission 0.00e+00 0.00e+00 +1 2 2 Zr-91 nu-fission 0.00e+00 0.00e+00 +2 2 2 Zr-92 nu-fission 0.00e+00 0.00e+00 +3 2 2 Zr-94 nu-fission 0.00e+00 0.00e+00 +4 2 2 Zr-96 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +4 3 1 H-1 ((total - scatter-1) / flux) 2.07e-01 2.30e-02 +5 3 1 O-16 ((total - scatter-1) / flux) 7.93e-02 5.20e-03 +6 3 1 B-10 ((total - scatter-1) / flux) 5.21e-04 2.44e-04 +7 3 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 3 2 H-1 ((total - scatter-1) / flux) 1.28e+00 2.51e-01 +1 3 2 O-16 ((total - scatter-1) / flux) 8.54e-02 1.40e-02 +2 3 2 B-10 ((total - scatter-1) / flux) 4.92e-02 8.23e-03 +3 3 2 B-11 ((total - scatter-1) / flux) 1.95e-04 1.53e-03 material group in nuclide score mean std. dev. +4 3 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +5 3 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +6 3 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +7 3 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +0 3 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 3 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 3 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 3 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +12 3 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.81e-01 2.21e-02 +13 3 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 7.86e-02 5.04e-03 +14 3 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 3 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 3 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.57e-02 1.58e-03 +9 3 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 5.21e-04 1.31e-04 +10 3 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 3 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 3 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 3 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 3 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 3 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 3 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.27e+00 2.51e-01 +1 3 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 8.54e-02 1.40e-02 +2 3 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 3 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 1.95e-04 1.53e-03 material group out nuclide score mean std. dev. +4 3 1 H-1 nu-fission 0.00e+00 0.00e+00 +5 3 1 O-16 nu-fission 0.00e+00 0.00e+00 +6 3 1 B-10 nu-fission 0.00e+00 0.00e+00 +7 3 1 B-11 nu-fission 0.00e+00 0.00e+00 +0 3 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 3 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 3 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 3 2 B-11 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +4 4 1 H-1 ((total - scatter-1) / flux) 1.75e-01 5.37e-02 +5 4 1 O-16 ((total - scatter-1) / flux) 6.65e-02 1.01e-02 +6 4 1 B-10 ((total - scatter-1) / flux) 5.70e-04 3.52e-04 +7 4 1 B-11 ((total - scatter-1) / flux) 8.88e-05 3.46e-04 +0 4 2 H-1 ((total - scatter-1) / flux) 1.14e+00 3.65e-01 +1 4 2 O-16 ((total - scatter-1) / flux) 8.51e-02 2.81e-02 +2 4 2 B-10 ((total - scatter-1) / flux) 2.59e-02 7.28e-03 +3 4 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +4 4 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +5 4 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +6 4 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +7 4 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +0 4 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 4 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 4 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 4 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +12 4 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.51e-01 5.15e-02 +13 4 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 6.65e-02 1.01e-02 +14 4 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 4 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 8.88e-05 3.46e-04 +8 4 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.37e-02 3.08e-03 +9 4 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 4 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 4 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 4 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 4 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 4 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 4 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 4 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.13e+00 3.62e-01 +1 4 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 8.51e-02 2.81e-02 +2 4 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 4 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +4 4 1 H-1 nu-fission 0.00e+00 0.00e+00 +5 4 1 O-16 nu-fission 0.00e+00 0.00e+00 +6 4 1 B-10 nu-fission 0.00e+00 0.00e+00 +7 4 1 B-11 nu-fission 0.00e+00 0.00e+00 +0 4 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 4 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 4 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 4 2 B-11 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +27 5 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 5 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 5 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 5 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 5 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 5 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 5 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 5 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 5 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 5 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 5 1 Mo-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 5 1 Mo-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 5 1 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 5 1 Mo-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +41 5 1 Mo-97 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +42 5 1 Mo-98 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +43 5 1 Mo-100 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +44 5 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +45 5 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +46 5 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +47 5 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +48 5 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +49 5 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +50 5 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +51 5 1 C-Nat ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +52 5 1 Cu-63 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +53 5 1 Cu-65 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 5 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 5 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 5 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 5 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 5 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 5 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 5 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 5 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 5 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 5 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 5 2 Mo-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 5 2 Mo-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 5 2 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 5 2 Mo-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 5 2 Mo-97 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 5 2 Mo-98 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 5 2 Mo-100 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 5 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 5 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 5 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 5 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +21 5 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +22 5 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +23 5 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 5 2 C-Nat ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 5 2 Cu-63 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 5 2 Cu-65 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +27 5 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +28 5 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +29 5 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +30 5 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +31 5 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +32 5 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +33 5 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +34 5 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +35 5 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +36 5 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +37 5 1 Mo-92 (nu-fission / flux) 0.00e+00 0.00e+00 +38 5 1 Mo-94 (nu-fission / flux) 0.00e+00 0.00e+00 +39 5 1 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 +40 5 1 Mo-96 (nu-fission / flux) 0.00e+00 0.00e+00 +41 5 1 Mo-97 (nu-fission / flux) 0.00e+00 0.00e+00 +42 5 1 Mo-98 (nu-fission / flux) 0.00e+00 0.00e+00 +43 5 1 Mo-100 (nu-fission / flux) 0.00e+00 0.00e+00 +44 5 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +45 5 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +46 5 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +47 5 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +48 5 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +49 5 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +50 5 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +51 5 1 C-Nat (nu-fission / flux) 0.00e+00 0.00e+00 +52 5 1 Cu-63 (nu-fission / flux) 0.00e+00 0.00e+00 +53 5 1 Cu-65 (nu-fission / flux) 0.00e+00 0.00e+00 +0 5 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +1 5 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +2 5 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +3 5 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +4 5 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +5 5 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +6 5 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +7 5 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +8 5 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +9 5 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +10 5 2 Mo-92 (nu-fission / flux) 0.00e+00 0.00e+00 +11 5 2 Mo-94 (nu-fission / flux) 0.00e+00 0.00e+00 +12 5 2 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 +13 5 2 Mo-96 (nu-fission / flux) 0.00e+00 0.00e+00 +14 5 2 Mo-97 (nu-fission / flux) 0.00e+00 0.00e+00 +15 5 2 Mo-98 (nu-fission / flux) 0.00e+00 0.00e+00 +16 5 2 Mo-100 (nu-fission / flux) 0.00e+00 0.00e+00 +17 5 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +18 5 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +19 5 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +20 5 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +21 5 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +22 5 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +23 5 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +24 5 2 C-Nat (nu-fission / flux) 0.00e+00 0.00e+00 +25 5 2 Cu-63 (nu-fission / flux) 0.00e+00 0.00e+00 +26 5 2 Cu-65 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +81 5 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 5 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 5 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +84 5 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +85 5 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +86 5 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +87 5 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +88 5 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +89 5 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +90 5 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +91 5 1 1 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +92 5 1 1 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +93 5 1 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +94 5 1 1 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +95 5 1 1 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +96 5 1 1 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +97 5 1 1 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +98 5 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +99 5 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +100 5 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +101 5 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +102 5 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +103 5 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +104 5 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +105 5 1 1 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +106 5 1 1 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +107 5 1 1 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 5 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 5 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 5 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 5 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 5 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 5 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 5 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 5 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 5 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +63 5 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +64 5 1 2 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 5 1 2 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 5 1 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 5 1 2 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 5 1 2 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 5 1 2 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 5 1 2 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 5 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 5 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 5 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 5 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 5 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 5 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 5 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 5 1 2 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 5 1 2 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 5 1 2 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 5 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 5 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 5 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 5 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 5 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 5 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 5 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 5 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 5 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 5 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 5 2 1 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 5 2 1 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 5 2 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 5 2 1 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 5 2 1 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 5 2 1 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 5 2 1 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 5 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 5 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 5 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 5 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 5 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 5 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 5 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 5 2 1 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 5 2 1 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 5 2 1 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 5 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 5 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 5 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 5 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 5 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 5 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 5 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 5 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 5 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 5 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 5 2 2 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 5 2 2 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 5 2 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 5 2 2 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 5 2 2 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 5 2 2 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 5 2 2 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 5 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 5 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 5 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 5 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 5 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 5 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 5 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 5 2 2 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 5 2 2 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 5 2 2 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +27 5 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +28 5 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +29 5 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +30 5 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +31 5 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +32 5 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +33 5 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +34 5 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +35 5 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +36 5 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +37 5 1 Mo-92 nu-fission 0.00e+00 0.00e+00 +38 5 1 Mo-94 nu-fission 0.00e+00 0.00e+00 +39 5 1 Mo-95 nu-fission 0.00e+00 0.00e+00 +40 5 1 Mo-96 nu-fission 0.00e+00 0.00e+00 +41 5 1 Mo-97 nu-fission 0.00e+00 0.00e+00 +42 5 1 Mo-98 nu-fission 0.00e+00 0.00e+00 +43 5 1 Mo-100 nu-fission 0.00e+00 0.00e+00 +44 5 1 Si-28 nu-fission 0.00e+00 0.00e+00 +45 5 1 Si-29 nu-fission 0.00e+00 0.00e+00 +46 5 1 Si-30 nu-fission 0.00e+00 0.00e+00 +47 5 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +48 5 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +49 5 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +50 5 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +51 5 1 C-Nat nu-fission 0.00e+00 0.00e+00 +52 5 1 Cu-63 nu-fission 0.00e+00 0.00e+00 +53 5 1 Cu-65 nu-fission 0.00e+00 0.00e+00 +0 5 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +1 5 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +2 5 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +3 5 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +4 5 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +5 5 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +6 5 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +7 5 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +8 5 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +9 5 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +10 5 2 Mo-92 nu-fission 0.00e+00 0.00e+00 +11 5 2 Mo-94 nu-fission 0.00e+00 0.00e+00 +12 5 2 Mo-95 nu-fission 0.00e+00 0.00e+00 +13 5 2 Mo-96 nu-fission 0.00e+00 0.00e+00 +14 5 2 Mo-97 nu-fission 0.00e+00 0.00e+00 +15 5 2 Mo-98 nu-fission 0.00e+00 0.00e+00 +16 5 2 Mo-100 nu-fission 0.00e+00 0.00e+00 +17 5 2 Si-28 nu-fission 0.00e+00 0.00e+00 +18 5 2 Si-29 nu-fission 0.00e+00 0.00e+00 +19 5 2 Si-30 nu-fission 0.00e+00 0.00e+00 +20 5 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +21 5 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +22 5 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +23 5 2 Cr-54 nu-fission 0.00e+00 0.00e+00 +24 5 2 C-Nat nu-fission 0.00e+00 0.00e+00 +25 5 2 Cu-63 nu-fission 0.00e+00 0.00e+00 +26 5 2 Cu-65 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 6 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +22 6 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +23 6 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 6 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 6 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 6 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +27 6 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 6 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 6 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 6 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 6 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 6 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 6 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 6 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 6 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 6 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 6 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 6 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 6 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 6 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +41 6 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 6 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 6 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 6 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 6 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 6 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 6 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 6 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 6 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 6 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 6 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 6 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 6 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 6 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 6 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 6 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 6 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 6 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 6 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 6 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 6 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 6 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 6 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +22 6 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +23 6 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +24 6 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +25 6 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +26 6 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +27 6 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +28 6 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +29 6 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +30 6 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +31 6 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +32 6 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +33 6 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +34 6 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +35 6 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +36 6 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +37 6 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +38 6 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +39 6 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +40 6 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +41 6 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +0 6 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 6 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 6 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 6 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 6 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +5 6 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +6 6 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +7 6 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +8 6 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +9 6 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +10 6 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +11 6 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +12 6 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +13 6 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +14 6 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +15 6 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +16 6 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +17 6 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +18 6 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +19 6 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +20 6 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +63 6 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +64 6 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 6 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 6 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 6 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 6 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 6 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 6 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 6 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 6 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 6 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 6 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 6 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 6 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 6 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 6 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 6 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 6 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +81 6 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 6 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 6 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 6 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 6 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 6 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 6 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 6 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 6 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 6 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 6 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 6 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 6 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 6 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 6 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 6 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 6 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 6 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 6 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 6 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 6 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 6 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 6 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 6 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 6 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 6 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 6 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 6 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 6 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 6 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 6 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 6 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 6 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 6 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 6 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 6 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 6 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 6 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 6 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 6 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 6 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 6 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 6 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 6 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 6 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 6 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 6 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 6 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 6 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 6 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 6 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 6 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 6 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 6 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 6 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 6 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 6 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 6 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 6 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 6 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 6 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 6 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 6 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 6 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 6 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 6 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +21 6 1 H-1 nu-fission 0.00e+00 0.00e+00 +22 6 1 O-16 nu-fission 0.00e+00 0.00e+00 +23 6 1 B-10 nu-fission 0.00e+00 0.00e+00 +24 6 1 B-11 nu-fission 0.00e+00 0.00e+00 +25 6 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +26 6 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +27 6 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +28 6 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +29 6 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +30 6 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +31 6 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +32 6 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +33 6 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +34 6 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +35 6 1 Si-28 nu-fission 0.00e+00 0.00e+00 +36 6 1 Si-29 nu-fission 0.00e+00 0.00e+00 +37 6 1 Si-30 nu-fission 0.00e+00 0.00e+00 +38 6 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +39 6 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +40 6 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +41 6 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +0 6 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 6 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 6 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 6 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 6 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +5 6 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +6 6 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +7 6 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +8 6 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +9 6 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +10 6 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +11 6 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +12 6 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +13 6 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +14 6 2 Si-28 nu-fission 0.00e+00 0.00e+00 +15 6 2 Si-29 nu-fission 0.00e+00 0.00e+00 +16 6 2 Si-30 nu-fission 0.00e+00 0.00e+00 +17 6 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +18 6 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +19 6 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +20 6 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 7 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +22 7 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +23 7 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 7 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 7 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 7 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +27 7 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 7 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 7 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 7 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 7 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 7 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 7 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 7 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 7 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 7 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 7 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 7 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 7 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 7 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +41 7 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 7 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 7 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 7 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 7 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 7 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 7 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 7 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 7 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 7 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 7 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 7 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 7 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 7 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 7 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 7 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 7 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 7 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 7 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 7 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 7 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 7 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 7 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +22 7 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +23 7 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +24 7 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +25 7 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +26 7 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +27 7 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +28 7 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +29 7 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +30 7 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +31 7 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +32 7 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +33 7 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +34 7 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +35 7 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +36 7 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +37 7 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +38 7 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +39 7 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +40 7 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +41 7 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +0 7 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 7 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 7 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 7 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 7 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +5 7 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +6 7 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +7 7 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +8 7 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +9 7 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +10 7 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +11 7 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +12 7 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +13 7 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +14 7 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +15 7 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +16 7 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +17 7 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +18 7 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +19 7 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +20 7 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +63 7 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +64 7 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 7 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 7 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 7 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 7 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 7 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 7 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 7 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 7 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 7 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 7 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 7 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 7 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 7 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 7 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 7 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 7 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +81 7 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 7 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 7 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 7 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 7 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 7 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 7 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 7 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 7 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 7 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 7 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 7 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 7 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 7 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 7 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 7 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 7 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 7 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 7 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 7 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 7 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 7 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 7 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 7 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 7 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 7 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 7 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 7 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 7 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 7 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 7 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 7 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 7 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 7 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 7 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 7 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 7 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 7 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 7 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 7 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 7 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 7 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 7 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 7 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 7 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 7 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 7 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 7 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 7 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 7 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 7 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 7 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 7 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 7 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 7 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 7 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 7 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 7 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 7 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 7 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 7 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 7 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 7 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 7 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 7 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 7 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +21 7 1 H-1 nu-fission 0.00e+00 0.00e+00 +22 7 1 O-16 nu-fission 0.00e+00 0.00e+00 +23 7 1 B-10 nu-fission 0.00e+00 0.00e+00 +24 7 1 B-11 nu-fission 0.00e+00 0.00e+00 +25 7 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +26 7 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +27 7 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +28 7 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +29 7 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +30 7 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +31 7 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +32 7 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +33 7 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +34 7 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +35 7 1 Si-28 nu-fission 0.00e+00 0.00e+00 +36 7 1 Si-29 nu-fission 0.00e+00 0.00e+00 +37 7 1 Si-30 nu-fission 0.00e+00 0.00e+00 +38 7 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +39 7 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +40 7 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +41 7 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +0 7 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 7 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 7 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 7 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 7 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +5 7 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +6 7 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +7 7 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +8 7 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +9 7 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +10 7 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +11 7 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +12 7 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +13 7 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +14 7 2 Si-28 nu-fission 0.00e+00 0.00e+00 +15 7 2 Si-29 nu-fission 0.00e+00 0.00e+00 +16 7 2 Si-30 nu-fission 0.00e+00 0.00e+00 +17 7 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +18 7 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +19 7 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +20 7 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 8 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +22 8 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +23 8 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 8 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 8 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 8 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +27 8 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 8 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 8 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 8 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 8 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 8 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 8 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 8 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 8 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 8 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 8 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 8 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 8 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 8 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +41 8 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 8 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 8 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 8 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 8 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 8 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 8 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 8 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 8 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 8 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 8 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 8 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 8 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 8 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 8 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 8 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 8 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 8 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 8 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 8 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 8 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 8 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 8 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +22 8 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +23 8 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +24 8 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +25 8 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +26 8 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +27 8 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +28 8 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +29 8 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +30 8 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +31 8 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +32 8 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +33 8 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +34 8 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +35 8 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +36 8 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +37 8 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +38 8 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +39 8 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +40 8 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +41 8 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +0 8 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 8 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 8 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 8 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 8 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +5 8 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +6 8 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +7 8 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +8 8 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +9 8 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +10 8 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +11 8 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +12 8 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +13 8 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +14 8 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +15 8 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +16 8 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +17 8 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +18 8 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +19 8 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +20 8 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +63 8 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +64 8 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 8 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 8 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 8 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 8 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 8 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 8 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 8 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 8 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 8 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 8 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 8 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 8 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 8 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 8 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 8 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 8 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +81 8 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 8 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 8 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 8 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 8 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 8 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 8 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 8 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 8 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 8 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 8 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 8 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 8 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 8 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 8 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 8 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 8 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 8 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 8 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 8 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 8 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 8 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 8 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 8 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 8 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 8 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 8 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 8 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 8 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 8 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 8 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 8 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 8 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 8 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 8 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 8 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 8 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 8 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 8 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 8 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 8 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 8 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 8 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 8 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 8 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 8 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 8 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 8 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 8 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 8 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 8 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 8 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 8 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 8 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 8 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 8 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 8 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 8 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 8 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 8 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 8 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 8 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 8 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 8 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 8 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 8 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +21 8 1 H-1 nu-fission 0.00e+00 0.00e+00 +22 8 1 O-16 nu-fission 0.00e+00 0.00e+00 +23 8 1 B-10 nu-fission 0.00e+00 0.00e+00 +24 8 1 B-11 nu-fission 0.00e+00 0.00e+00 +25 8 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +26 8 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +27 8 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +28 8 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +29 8 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +30 8 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +31 8 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +32 8 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +33 8 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +34 8 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +35 8 1 Si-28 nu-fission 0.00e+00 0.00e+00 +36 8 1 Si-29 nu-fission 0.00e+00 0.00e+00 +37 8 1 Si-30 nu-fission 0.00e+00 0.00e+00 +38 8 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +39 8 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +40 8 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +41 8 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +0 8 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 8 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 8 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 8 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 8 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +5 8 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +6 8 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +7 8 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +8 8 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +9 8 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +10 8 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +11 8 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +12 8 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +13 8 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +14 8 2 Si-28 nu-fission 0.00e+00 0.00e+00 +15 8 2 Si-29 nu-fission 0.00e+00 0.00e+00 +16 8 2 Si-30 nu-fission 0.00e+00 0.00e+00 +17 8 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +18 8 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +19 8 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +20 8 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 9 1 H-1 ((total - scatter-1) / flux) 1.51e-01 4.81e-01 +22 9 1 O-16 ((total - scatter-1) / flux) 1.16e-01 1.14e-01 +23 9 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 9 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 9 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 9 1 Fe-56 ((total - scatter-1) / flux) 1.86e-01 2.00e-01 +27 9 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 9 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 9 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 9 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 9 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 9 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 9 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 9 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 9 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 9 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 9 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 9 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +39 9 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 9 1 Cr-53 ((total - scatter-1) / flux) 1.47e-01 1.40e-01 +41 9 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 9 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 9 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 9 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 9 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 9 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 9 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 9 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 9 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 9 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 9 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 9 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 9 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 9 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 9 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 9 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 9 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 9 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 9 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 9 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 9 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 9 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 9 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +22 9 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +23 9 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +24 9 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +25 9 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +26 9 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +27 9 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +28 9 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +29 9 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +30 9 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +31 9 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +32 9 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +33 9 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +34 9 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +35 9 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +36 9 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +37 9 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +38 9 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +39 9 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +40 9 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +41 9 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +0 9 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 9 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 9 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 9 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 9 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +5 9 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +6 9 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +7 9 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +8 9 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +9 9 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +10 9 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +11 9 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +12 9 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +13 9 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +14 9 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +15 9 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +16 9 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +17 9 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +18 9 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +19 9 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +20 9 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +63 9 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.51e-01 4.81e-01 +64 9 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.16e-01 1.14e-01 +65 9 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 9 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 9 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 9 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 1.86e-01 2.00e-01 +69 9 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 9 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 9 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 9 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 9 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 9 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 9 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 9 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 9 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 9 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 9 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 9 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +81 9 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 9 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 1.47e-01 1.40e-01 +83 9 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 9 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 9 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 9 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 9 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 9 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 9 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 9 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 9 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 9 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 9 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 9 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 9 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 9 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 9 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 9 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 9 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 9 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 9 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 9 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 9 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 9 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 9 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 9 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 9 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 9 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 9 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 9 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 9 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 9 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 9 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 9 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 9 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 9 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 9 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 9 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 9 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 9 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 9 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 9 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 9 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 9 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 9 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 9 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 9 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 9 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 9 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 9 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 9 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 9 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 9 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 9 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 9 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 9 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 9 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 9 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 9 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 9 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 9 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 9 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 9 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 9 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 9 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 9 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +21 9 1 H-1 nu-fission 0.00e+00 0.00e+00 +22 9 1 O-16 nu-fission 0.00e+00 0.00e+00 +23 9 1 B-10 nu-fission 0.00e+00 0.00e+00 +24 9 1 B-11 nu-fission 0.00e+00 0.00e+00 +25 9 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +26 9 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +27 9 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +28 9 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +29 9 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +30 9 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +31 9 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +32 9 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +33 9 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +34 9 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +35 9 1 Si-28 nu-fission 0.00e+00 0.00e+00 +36 9 1 Si-29 nu-fission 0.00e+00 0.00e+00 +37 9 1 Si-30 nu-fission 0.00e+00 0.00e+00 +38 9 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +39 9 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +40 9 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +41 9 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +0 9 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 9 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 9 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 9 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 9 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +5 9 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +6 9 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +7 9 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +8 9 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +9 9 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +10 9 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +11 9 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +12 9 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +13 9 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +14 9 2 Si-28 nu-fission 0.00e+00 0.00e+00 +15 9 2 Si-29 nu-fission 0.00e+00 0.00e+00 +16 9 2 Si-30 nu-fission 0.00e+00 0.00e+00 +17 9 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +18 9 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +19 9 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +20 9 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 10 1 H-1 ((total - scatter-1) / flux) 1.24e-01 5.41e-01 +22 10 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +23 10 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +24 10 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +25 10 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +26 10 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +27 10 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +28 10 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +29 10 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +30 10 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +31 10 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +32 10 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +33 10 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +34 10 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +35 10 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +36 10 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +37 10 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +38 10 1 Cr-50 ((total - scatter-1) / flux) 1.12e-01 1.38e-01 +39 10 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +40 10 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +41 10 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 10 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +1 10 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 10 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +3 10 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 10 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 10 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 10 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 10 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 10 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +9 10 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +10 10 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +11 10 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 10 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 10 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +14 10 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 10 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 10 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +17 10 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +18 10 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +19 10 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +20 10 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +21 10 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +22 10 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +23 10 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +24 10 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +25 10 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +26 10 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +27 10 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +28 10 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +29 10 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +30 10 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +31 10 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +32 10 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +33 10 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +34 10 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +35 10 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +36 10 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +37 10 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +38 10 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +39 10 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +40 10 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +41 10 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 +0 10 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 10 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 10 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 10 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 10 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 +5 10 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 +6 10 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 +7 10 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 +8 10 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 +9 10 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 +10 10 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 +11 10 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 +12 10 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 +13 10 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 +14 10 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 +15 10 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 +16 10 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 +17 10 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 +18 10 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 +19 10 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 +20 10 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +63 10 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.24e-01 5.41e-01 +64 10 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +65 10 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +66 10 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +67 10 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +68 10 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +69 10 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +70 10 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +71 10 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +72 10 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +73 10 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +74 10 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +75 10 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +76 10 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +77 10 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +78 10 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +79 10 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +80 10 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 1.12e-01 1.38e-01 +81 10 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +82 10 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +83 10 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +42 10 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +43 10 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +44 10 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +45 10 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +46 10 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +47 10 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +48 10 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +49 10 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +50 10 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +51 10 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +52 10 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +53 10 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +54 10 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +55 10 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +56 10 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +57 10 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +58 10 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +59 10 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +60 10 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +61 10 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +62 10 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 10 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 10 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 10 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 10 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 10 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 10 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +27 10 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +28 10 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +29 10 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 10 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 10 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +32 10 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 10 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 10 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +35 10 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +36 10 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +37 10 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +38 10 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +39 10 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +40 10 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +41 10 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 10 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +1 10 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 10 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 10 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 10 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 10 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 10 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 10 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 10 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 10 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 10 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 10 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 10 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 10 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 10 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 10 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 10 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 10 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 10 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +19 10 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 10 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +21 10 1 H-1 nu-fission 0.00e+00 0.00e+00 +22 10 1 O-16 nu-fission 0.00e+00 0.00e+00 +23 10 1 B-10 nu-fission 0.00e+00 0.00e+00 +24 10 1 B-11 nu-fission 0.00e+00 0.00e+00 +25 10 1 Fe-54 nu-fission 0.00e+00 0.00e+00 +26 10 1 Fe-56 nu-fission 0.00e+00 0.00e+00 +27 10 1 Fe-57 nu-fission 0.00e+00 0.00e+00 +28 10 1 Fe-58 nu-fission 0.00e+00 0.00e+00 +29 10 1 Ni-58 nu-fission 0.00e+00 0.00e+00 +30 10 1 Ni-60 nu-fission 0.00e+00 0.00e+00 +31 10 1 Ni-61 nu-fission 0.00e+00 0.00e+00 +32 10 1 Ni-62 nu-fission 0.00e+00 0.00e+00 +33 10 1 Ni-64 nu-fission 0.00e+00 0.00e+00 +34 10 1 Mn-55 nu-fission 0.00e+00 0.00e+00 +35 10 1 Si-28 nu-fission 0.00e+00 0.00e+00 +36 10 1 Si-29 nu-fission 0.00e+00 0.00e+00 +37 10 1 Si-30 nu-fission 0.00e+00 0.00e+00 +38 10 1 Cr-50 nu-fission 0.00e+00 0.00e+00 +39 10 1 Cr-52 nu-fission 0.00e+00 0.00e+00 +40 10 1 Cr-53 nu-fission 0.00e+00 0.00e+00 +41 10 1 Cr-54 nu-fission 0.00e+00 0.00e+00 +0 10 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 10 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 10 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 10 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 10 2 Fe-54 nu-fission 0.00e+00 0.00e+00 +5 10 2 Fe-56 nu-fission 0.00e+00 0.00e+00 +6 10 2 Fe-57 nu-fission 0.00e+00 0.00e+00 +7 10 2 Fe-58 nu-fission 0.00e+00 0.00e+00 +8 10 2 Ni-58 nu-fission 0.00e+00 0.00e+00 +9 10 2 Ni-60 nu-fission 0.00e+00 0.00e+00 +10 10 2 Ni-61 nu-fission 0.00e+00 0.00e+00 +11 10 2 Ni-62 nu-fission 0.00e+00 0.00e+00 +12 10 2 Ni-64 nu-fission 0.00e+00 0.00e+00 +13 10 2 Mn-55 nu-fission 0.00e+00 0.00e+00 +14 10 2 Si-28 nu-fission 0.00e+00 0.00e+00 +15 10 2 Si-29 nu-fission 0.00e+00 0.00e+00 +16 10 2 Si-30 nu-fission 0.00e+00 0.00e+00 +17 10 2 Cr-50 nu-fission 0.00e+00 0.00e+00 +18 10 2 Cr-52 nu-fission 0.00e+00 0.00e+00 +19 10 2 Cr-53 nu-fission 0.00e+00 0.00e+00 +20 10 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +9 11 1 H-1 ((total - scatter-1) / flux) 1.31e-01 4.76e-01 +10 11 1 O-16 ((total - scatter-1) / flux) 2.87e-02 4.30e-02 +11 11 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 11 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 11 1 Zr-90 ((total - scatter-1) / flux) 2.20e-02 4.00e-02 +14 11 1 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 11 1 Zr-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +16 11 1 Zr-94 ((total - scatter-1) / flux) 4.19e-03 8.73e-02 +17 11 1 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +0 11 2 H-1 ((total - scatter-1) / flux) 6.87e-01 1.24e+00 +1 11 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +2 11 2 B-10 ((total - scatter-1) / flux) 4.29e-02 6.07e-02 +3 11 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 11 2 Zr-90 ((total - scatter-1) / flux) 3.96e-02 1.05e-01 +5 11 2 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +6 11 2 Zr-92 ((total - scatter-1) / flux) 8.42e-02 1.03e-01 +7 11 2 Zr-94 ((total - scatter-1) / flux) 9.20e-02 1.26e-01 +8 11 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +9 11 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +10 11 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +11 11 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +12 11 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +13 11 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +14 11 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +15 11 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +16 11 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +17 11 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 +0 11 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 11 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 11 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 11 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 11 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +5 11 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +6 11 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +7 11 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +8 11 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +27 11 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 9.96e-02 4.43e-01 +28 11 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 2.87e-02 4.30e-02 +29 11 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 11 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 11 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 2.20e-02 4.00e-02 +32 11 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 11 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +34 11 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.19e-03 8.73e-02 +35 11 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +18 11 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 3.19e-02 4.51e-02 +19 11 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 11 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 11 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 11 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 11 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 11 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 11 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 11 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 11 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 11 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 11 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 11 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 11 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 11 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 11 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 11 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 11 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 11 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 6.87e-01 1.24e+00 +1 11 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +2 11 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 11 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 11 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 3.96e-02 1.05e-01 +5 11 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +6 11 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 8.42e-02 1.03e-01 +7 11 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 9.20e-02 1.26e-01 +8 11 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +9 11 1 H-1 nu-fission 0.00e+00 0.00e+00 +10 11 1 O-16 nu-fission 0.00e+00 0.00e+00 +11 11 1 B-10 nu-fission 0.00e+00 0.00e+00 +12 11 1 B-11 nu-fission 0.00e+00 0.00e+00 +13 11 1 Zr-90 nu-fission 0.00e+00 0.00e+00 +14 11 1 Zr-91 nu-fission 0.00e+00 0.00e+00 +15 11 1 Zr-92 nu-fission 0.00e+00 0.00e+00 +16 11 1 Zr-94 nu-fission 0.00e+00 0.00e+00 +17 11 1 Zr-96 nu-fission 0.00e+00 0.00e+00 +0 11 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 11 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 11 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 11 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 11 2 Zr-90 nu-fission 0.00e+00 0.00e+00 +5 11 2 Zr-91 nu-fission 0.00e+00 0.00e+00 +6 11 2 Zr-92 nu-fission 0.00e+00 0.00e+00 +7 11 2 Zr-94 nu-fission 0.00e+00 0.00e+00 +8 11 2 Zr-96 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +9 12 1 H-1 ((total - scatter-1) / flux) 9.89e-02 1.79e-01 +10 12 1 O-16 ((total - scatter-1) / flux) 1.33e-02 2.04e-02 +11 12 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +12 12 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +13 12 1 Zr-90 ((total - scatter-1) / flux) 9.00e-02 7.55e-02 +14 12 1 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +15 12 1 Zr-92 ((total - scatter-1) / flux) 3.50e-03 1.70e-02 +16 12 1 Zr-94 ((total - scatter-1) / flux) 4.85e-03 1.63e-02 +17 12 1 Zr-96 ((total - scatter-1) / flux) 2.73e-03 1.75e-02 +0 12 2 H-1 ((total - scatter-1) / flux) 1.26e+00 1.98e+00 +1 12 2 O-16 ((total - scatter-1) / flux) 7.92e-02 1.05e-01 +2 12 2 B-10 ((total - scatter-1) / flux) 1.69e-02 2.39e-02 +3 12 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +4 12 2 Zr-90 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +5 12 2 Zr-91 ((total - scatter-1) / flux) 3.32e-02 4.07e-02 +6 12 2 Zr-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +7 12 2 Zr-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 +8 12 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. +9 12 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +10 12 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +11 12 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +12 12 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +13 12 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +14 12 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +15 12 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +16 12 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +17 12 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 +0 12 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 +1 12 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 +2 12 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 +3 12 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 +4 12 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 +5 12 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 +6 12 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 +7 12 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 +8 12 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. +27 12 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 7.17e-02 1.68e-01 +28 12 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.33e-02 2.04e-02 +29 12 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +30 12 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +31 12 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 9.00e-02 7.55e-02 +32 12 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +33 12 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 3.50e-03 1.70e-02 +34 12 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.85e-03 1.63e-02 +35 12 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 2.73e-03 1.75e-02 +18 12 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.72e-02 2.96e-02 +19 12 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +20 12 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +21 12 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +22 12 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +23 12 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +24 12 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +25 12 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +26 12 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +9 12 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +10 12 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +11 12 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +12 12 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +13 12 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +14 12 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +15 12 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +16 12 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +17 12 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +0 12 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.24e+00 1.96e+00 +1 12 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 7.92e-02 1.05e-01 +2 12 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +3 12 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +4 12 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +5 12 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 3.32e-02 4.07e-02 +6 12 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +7 12 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 +8 12 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. +9 12 1 H-1 nu-fission 0.00e+00 0.00e+00 +10 12 1 O-16 nu-fission 0.00e+00 0.00e+00 +11 12 1 B-10 nu-fission 0.00e+00 0.00e+00 +12 12 1 B-11 nu-fission 0.00e+00 0.00e+00 +13 12 1 Zr-90 nu-fission 0.00e+00 0.00e+00 +14 12 1 Zr-91 nu-fission 0.00e+00 0.00e+00 +15 12 1 Zr-92 nu-fission 0.00e+00 0.00e+00 +16 12 1 Zr-94 nu-fission 0.00e+00 0.00e+00 +17 12 1 Zr-96 nu-fission 0.00e+00 0.00e+00 +0 12 2 H-1 nu-fission 0.00e+00 0.00e+00 +1 12 2 O-16 nu-fission 0.00e+00 0.00e+00 +2 12 2 B-10 nu-fission 0.00e+00 0.00e+00 +3 12 2 B-11 nu-fission 0.00e+00 0.00e+00 +4 12 2 Zr-90 nu-fission 0.00e+00 0.00e+00 +5 12 2 Zr-91 nu-fission 0.00e+00 0.00e+00 +6 12 2 Zr-92 nu-fission 0.00e+00 0.00e+00 +7 12 2 Zr-94 nu-fission 0.00e+00 0.00e+00 +8 12 2 Zr-96 nu-fission 0.00e+00 0.00e+00 \ No newline at end of file From 203d5a3fe46fdd8586948fb927cdd03f7a8bcabc Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 13:42:15 -0400 Subject: [PATCH 099/147] Updated MGXS Notebooks with KappaFissionXS --- .../pythonapi/examples/mgxs-part-i.ipynb | 11 +- .../pythonapi/examples/mgxs-part-ii.ipynb | 679 +++++++++--------- .../pythonapi/examples/mgxs-part-iii.ipynb | 176 ++--- 3 files changed, 457 insertions(+), 409 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index 610e82ec1..a97a0c02e 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -376,6 +376,7 @@ "* `CaptureXS`\n", "* `FissionXS`\n", "* `NuFissionXS`\n", + "* `KappaFissionXS`\n", "* `ScatterXS`\n", "* `NuScatterXS`\n", "* `ScatterMatrixXS`\n", @@ -1162,21 +1163,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 3", + "display_name": "Python 2", "language": "python", - "name": "python3" + "name": "python2" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 3 + "version": 2 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython3", - "version": "3.5.1" + "pygments_lexer": "ipython2", + "version": "2.7.6" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index fd8d09052..7b313da74 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -34,16 +34,16 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/romano/miniconda3/envs/default/lib/python3.5/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", + "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:884: UserWarning: axes.color_cycle is deprecated and replaced with axes.prop_cycle; please use the latter.\n", + " warnings.warn(self.msg_depr % (key, alt_key))\n", + "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", "\n", " warnings.warn(_use_error_msg)\n", - "/home/romano/miniconda3/envs/default/lib/python3.5/importlib/_bootstrap.py:222: QAWarning: pyne.rxname is not yet QA compliant.\n", - " return f(*args, **kwds)\n", - "/home/romano/miniconda3/envs/default/lib/python3.5/importlib/_bootstrap.py:222: QAWarning: pyne.ace is not yet QA compliant.\n", - " return f(*args, **kwds)\n" + "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:9: QAWarning: pyne.rxname is not yet QA compliant.\n", + "/usr/local/lib/python2.7/dist-packages/IPython/kernel/__main__.py:9: QAWarning: pyne.ace is not yet QA compliant.\n" ] } ], @@ -443,10 +443,11 @@ " 888\n", "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", - " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", - " Date/Time: 2016-05-05 15:00:51\n", + " Git SHA1: 7b20f8ad4aa9e6f02f8b1d51e002f9f56ba7aa15\n", + " Date/Time: 2016-05-09 13:34:05\n", + " MPI Processes: 1\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -522,7 +523,7 @@ " 48/1 1.21610 1.22612 +/- 0.00251\n", " 49/1 1.22199 1.22602 +/- 0.00245\n", " 50/1 1.20860 1.22558 +/- 0.00243\n", - " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10056\n", + " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10050\n", " The estimated number of batches is 73\n", " Creating state point statepoint.050.h5...\n", " 51/1 1.21850 1.22541 +/- 0.00237\n", @@ -548,7 +549,7 @@ " 71/1 1.19720 1.22444 +/- 0.00195\n", " 72/1 1.23770 1.22465 +/- 0.00193\n", " 73/1 1.23894 1.22488 +/- 0.00191\n", - " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10056\n", + " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10050\n", " The estimated number of batches is 74\n", " 74/1 1.22437 1.22487 +/- 0.00188\n", " Triggers satisfied for batch 74\n", @@ -561,20 +562,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.8600E-01 seconds\n", - " Reading cross sections = 1.1000E-01 seconds\n", - " Total time in simulation = 2.3697E+02 seconds\n", - " Time in transport only = 2.3690E+02 seconds\n", - " Time in inactive batches = 1.5640E+01 seconds\n", - " Time in active batches = 2.2133E+02 seconds\n", - " Time synchronizing fission bank = 3.0000E-02 seconds\n", - " Sampling source sites = 1.9000E-02 seconds\n", - " SEND/RECV source sites = 1.1000E-02 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 1.0000E-02 seconds\n", - " Total time elapsed = 2.3743E+02 seconds\n", - " Calculation Rate (inactive) = 6393.86 neutrons/second\n", - " Calculation Rate (active) = 1807.26 neutrons/second\n", + " Total time for initialization = 3.8900E-01 seconds\n", + " Reading cross sections = 8.3000E-02 seconds\n", + " Total time in simulation = 2.2066E+02 seconds\n", + " Time in transport only = 2.2061E+02 seconds\n", + " Time in inactive batches = 1.5872E+01 seconds\n", + " Time in active batches = 2.0478E+02 seconds\n", + " Time synchronizing fission bank = 1.9000E-02 seconds\n", + " Sampling source sites = 1.2000E-02 seconds\n", + " SEND/RECV source sites = 6.0000E-03 seconds\n", + " Time accumulating tallies = 3.0000E-03 seconds\n", + " Total time for finalization = 1.1000E-02 seconds\n", + " Total time elapsed = 2.2111E+02 seconds\n", + " Calculation Rate (inactive) = 6300.40 neutrons/second\n", + " Calculation Rate (active) = 1953.28 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -785,6 +786,7 @@ " group in\n", " group out\n", " nuclide\n", + " score\n", " mean\n", " std. dev.\n", " \n", @@ -796,6 +798,7 @@ " 1\n", " 1\n", " H-1\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.234115\n", " 0.003568\n", " \n", @@ -805,6 +808,7 @@ " 1\n", " 1\n", " O-16\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 1.563707\n", " 0.005953\n", " \n", @@ -814,6 +818,7 @@ " 1\n", " 2\n", " H-1\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 1.594129\n", " 0.002369\n", " \n", @@ -823,6 +828,7 @@ " 1\n", " 2\n", " O-16\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.285761\n", " 0.001676\n", " \n", @@ -832,6 +838,7 @@ " 1\n", " 3\n", " H-1\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.011089\n", " 0.000248\n", " \n", @@ -841,6 +848,7 @@ " 1\n", " 3\n", " O-16\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -850,6 +858,7 @@ " 1\n", " 4\n", " H-1\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -859,6 +868,7 @@ " 1\n", " 4\n", " O-16\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -868,6 +878,7 @@ " 1\n", " 5\n", " H-1\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -877,6 +888,7 @@ " 1\n", " 5\n", " O-16\n", + " ((nu-scatter-0 - scatter-1) / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -885,17 +897,29 @@ "" ], "text/plain": [ - " cell group in group out nuclide mean std. dev.\n", - "126 10002 1 1 H-1 0.234115 0.003568\n", - "127 10002 1 1 O-16 1.563707 0.005953\n", - "124 10002 1 2 H-1 1.594129 0.002369\n", - "125 10002 1 2 O-16 0.285761 0.001676\n", - "122 10002 1 3 H-1 0.011089 0.000248\n", - "123 10002 1 3 O-16 0.000000 0.000000\n", - "120 10002 1 4 H-1 0.000000 0.000000\n", - "121 10002 1 4 O-16 0.000000 0.000000\n", - "118 10002 1 5 H-1 0.000000 0.000000\n", - "119 10002 1 5 O-16 0.000000 0.000000" + " cell group in group out nuclide score \\\n", + "126 10002 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", + "127 10002 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", + "124 10002 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", + "125 10002 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", + "122 10002 1 3 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", + "123 10002 1 3 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", + "120 10002 1 4 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", + "121 10002 1 4 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", + "118 10002 1 5 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", + "119 10002 1 5 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", + "\n", + " mean std. dev. \n", + "126 0.234115 0.003568 \n", + "127 1.563707 0.005953 \n", + "124 1.594129 0.002369 \n", + "125 0.285761 0.001676 \n", + "122 0.011089 0.000248 \n", + "123 0.000000 0.000000 \n", + "120 0.000000 0.000000 \n", + "121 0.000000 0.000000 \n", + "118 0.000000 0.000000 \n", + "119 0.000000 0.000000 " ] }, "execution_count": 19, @@ -995,6 +1019,7 @@ " cell\n", " group in\n", " nuclide\n", + " score\n", " mean\n", " std. dev.\n", " \n", @@ -1005,6 +1030,7 @@ " 10000\n", " 1\n", " U-235\n", + " ((total - scatter-1) / flux)\n", " 20.611692\n", " 0.104237\n", " \n", @@ -1013,6 +1039,7 @@ " 10000\n", " 1\n", " U-238\n", + " ((total - scatter-1) / flux)\n", " 9.585358\n", " 0.013808\n", " \n", @@ -1021,6 +1048,7 @@ " 10000\n", " 1\n", " O-16\n", + " ((total - scatter-1) / flux)\n", " 3.164190\n", " 0.005049\n", " \n", @@ -1029,6 +1057,7 @@ " 10000\n", " 2\n", " U-235\n", + " ((total - scatter-1) / flux)\n", " 485.413426\n", " 0.996410\n", " \n", @@ -1037,6 +1066,7 @@ " 10000\n", " 2\n", " U-238\n", + " ((total - scatter-1) / flux)\n", " 11.190386\n", " 0.028731\n", " \n", @@ -1045,6 +1075,7 @@ " 10000\n", " 2\n", " O-16\n", + " ((total - scatter-1) / flux)\n", " 3.794859\n", " 0.011139\n", " \n", @@ -1053,13 +1084,13 @@ "" ], "text/plain": [ - " cell group in nuclide mean std. dev.\n", - "3 10000 1 U-235 20.611692 0.104237\n", - "4 10000 1 U-238 9.585358 0.013808\n", - "5 10000 1 O-16 3.164190 0.005049\n", - "0 10000 2 U-235 485.413426 0.996410\n", - "1 10000 2 U-238 11.190386 0.028731\n", - "2 10000 2 O-16 3.794859 0.011139" + " cell group in nuclide score mean std. dev.\n", + "3 10000 1 U-235 ((total - scatter-1) / flux) 2.06e+01 1.04e-01\n", + "4 10000 1 U-238 ((total - scatter-1) / flux) 9.59e+00 1.38e-02\n", + "5 10000 1 O-16 ((total - scatter-1) / flux) 3.16e+00 5.05e-03\n", + "0 10000 2 U-235 ((total - scatter-1) / flux) 4.85e+02 9.96e-01\n", + "1 10000 2 U-238 ((total - scatter-1) / flux) 1.12e+01 2.87e-02\n", + "2 10000 2 O-16 ((total - scatter-1) / flux) 3.79e+00 1.11e-02" ] }, "execution_count": 22, @@ -1166,81 +1197,81 @@ "[ NORMAL ] Iteration 0:\tk_eff = 0.574672\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.679815\tres = 4.253E-01\n", "[ NORMAL ] Iteration 2:\tk_eff = 0.660826\tres = 1.830E-01\n", - "[ NORMAL ] Iteration 3:\tk_eff = 0.658941\tres = 2.793E-02\n", - "[ NORMAL ] Iteration 4:\tk_eff = 0.643012\tres = 2.852E-03\n", + "[ NORMAL ] Iteration 3:\tk_eff = 0.658940\tres = 2.793E-02\n", + "[ NORMAL ] Iteration 4:\tk_eff = 0.643012\tres = 2.853E-03\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.625810\tres = 2.417E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.606678\tres = 2.675E-02\n", "[ NORMAL ] Iteration 7:\tk_eff = 0.587485\tres = 3.057E-02\n", "[ NORMAL ] Iteration 8:\tk_eff = 0.569029\tres = 3.164E-02\n", - "[ NORMAL ] Iteration 9:\tk_eff = 0.551708\tres = 3.142E-02\n", + "[ NORMAL ] Iteration 9:\tk_eff = 0.551707\tres = 3.142E-02\n", "[ NORMAL ] Iteration 10:\tk_eff = 0.536035\tres = 3.044E-02\n", "[ NORMAL ] Iteration 11:\tk_eff = 0.522275\tres = 2.841E-02\n", "[ NORMAL ] Iteration 12:\tk_eff = 0.510610\tres = 2.567E-02\n", - "[ NORMAL ] Iteration 13:\tk_eff = 0.501107\tres = 2.233E-02\n", + "[ NORMAL ] Iteration 13:\tk_eff = 0.501106\tres = 2.234E-02\n", "[ NORMAL ] Iteration 14:\tk_eff = 0.493832\tres = 1.861E-02\n", "[ NORMAL ] Iteration 15:\tk_eff = 0.488781\tres = 1.452E-02\n", "[ NORMAL ] Iteration 16:\tk_eff = 0.485924\tres = 1.023E-02\n", - "[ NORMAL ] Iteration 17:\tk_eff = 0.485212\tres = 5.845E-03\n", - "[ NORMAL ] Iteration 18:\tk_eff = 0.486571\tres = 1.466E-03\n", - "[ NORMAL ] Iteration 19:\tk_eff = 0.489906\tres = 2.802E-03\n", - "[ NORMAL ] Iteration 20:\tk_eff = 0.495106\tres = 6.853E-03\n", + "[ NORMAL ] Iteration 17:\tk_eff = 0.485211\tres = 5.846E-03\n", + "[ NORMAL ] Iteration 18:\tk_eff = 0.486571\tres = 1.467E-03\n", + "[ NORMAL ] Iteration 19:\tk_eff = 0.489905\tres = 2.802E-03\n", + "[ NORMAL ] Iteration 20:\tk_eff = 0.495105\tres = 6.853E-03\n", "[ NORMAL ] Iteration 21:\tk_eff = 0.502056\tres = 1.061E-02\n", - "[ NORMAL ] Iteration 22:\tk_eff = 0.510631\tres = 1.404E-02\n", + "[ NORMAL ] Iteration 22:\tk_eff = 0.510630\tres = 1.404E-02\n", "[ NORMAL ] Iteration 23:\tk_eff = 0.520696\tres = 1.708E-02\n", - "[ NORMAL ] Iteration 24:\tk_eff = 0.532121\tres = 1.971E-02\n", + "[ NORMAL ] Iteration 24:\tk_eff = 0.532120\tres = 1.971E-02\n", "[ NORMAL ] Iteration 25:\tk_eff = 0.544768\tres = 2.194E-02\n", - "[ NORMAL ] Iteration 26:\tk_eff = 0.558506\tres = 2.377E-02\n", + "[ NORMAL ] Iteration 26:\tk_eff = 0.558505\tres = 2.377E-02\n", "[ NORMAL ] Iteration 27:\tk_eff = 0.573200\tres = 2.522E-02\n", "[ NORMAL ] Iteration 28:\tk_eff = 0.588723\tres = 2.631E-02\n", "[ NORMAL ] Iteration 29:\tk_eff = 0.604951\tres = 2.708E-02\n", - "[ NORMAL ] Iteration 30:\tk_eff = 0.621766\tres = 2.757E-02\n", - "[ NORMAL ] Iteration 31:\tk_eff = 0.639054\tres = 2.779E-02\n", - "[ NORMAL ] Iteration 32:\tk_eff = 0.656709\tres = 2.781E-02\n", + "[ NORMAL ] Iteration 30:\tk_eff = 0.621765\tres = 2.756E-02\n", + "[ NORMAL ] Iteration 31:\tk_eff = 0.639053\tres = 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207:\tk_eff = 1.222824\tres = 2.480E-05\n", + "[ NORMAL ] Iteration 208:\tk_eff = 1.222852\tres = 2.385E-05\n", + "[ NORMAL ] Iteration 209:\tk_eff = 1.222879\tres = 2.294E-05\n", + "[ NORMAL ] Iteration 210:\tk_eff = 1.222905\tres = 2.206E-05\n", + "[ NORMAL ] Iteration 211:\tk_eff = 1.222930\tres = 2.122E-05\n", + "[ NORMAL ] Iteration 212:\tk_eff = 1.222954\tres = 2.041E-05\n", + "[ NORMAL ] Iteration 213:\tk_eff = 1.222977\tres = 1.963E-05\n", + "[ NORMAL ] Iteration 214:\tk_eff = 1.222999\tres = 1.888E-05\n", + "[ NORMAL ] Iteration 215:\tk_eff = 1.223020\tres = 1.816E-05\n", + "[ NORMAL ] Iteration 216:\tk_eff = 1.223041\tres = 1.747E-05\n", + "[ NORMAL ] Iteration 217:\tk_eff = 1.223061\tres = 1.680E-05\n", + "[ NORMAL ] Iteration 218:\tk_eff = 1.223080\tres = 1.616E-05\n", + "[ NORMAL ] Iteration 219:\tk_eff = 1.223098\tres = 1.554E-05\n", + "[ NORMAL ] Iteration 220:\tk_eff = 1.223116\tres = 1.495E-05\n", + "[ NORMAL ] Iteration 221:\tk_eff = 1.223132\tres = 1.437E-05\n", + "[ NORMAL ] Iteration 222:\tk_eff = 1.223149\tres = 1.382E-05\n", + "[ NORMAL ] Iteration 223:\tk_eff = 1.223164\tres = 1.330E-05\n", + "[ NORMAL ] Iteration 224:\tk_eff = 1.223179\tres = 1.279E-05\n", + "[ NORMAL ] Iteration 225:\tk_eff = 1.223194\tres = 1.230E-05\n", + "[ NORMAL ] Iteration 226:\tk_eff = 1.223208\tres = 1.183E-05\n", + "[ NORMAL ] Iteration 227:\tk_eff = 1.223221\tres = 1.138E-05\n", + "[ NORMAL ] Iteration 228:\tk_eff = 1.223234\tres = 1.094E-05\n", + "[ NORMAL ] Iteration 229:\tk_eff = 1.223246\tres = 1.052E-05\n", + "[ NORMAL ] Iteration 230:\tk_eff = 1.223258\tres = 1.012E-05\n" ] } ], @@ -1780,9 +1811,9 @@ }, { "data": { - "image/png": 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s//SZaStbolLd0ZyNidDkt7hJQUQeUNXTRGQ2zn0J4e0AqGonmuHGpEqwvEub\nI4/Kg6vY9a3r+PX3MVm3EE28pNBRV/hWUzDp1lpN4X73+1VpKIfppKrHT6Ds1hvbTAxdWcWTTxYy\ndmx2LeURb+6jeFZn3QVj0qG1ldc+cX+cCyxX1XeAdYH9gW/TUDbTCbQ2fLX5kNXHHivMuonmkm0+\nSvaE7/FYhjDplUiL5RPAYSKyA3A1UIlzI5sxadWtW4h33sn8WP5QqOU6CqnsUwgGoa4uNcc3prlE\nkkI/Vb0COAx4SFWvpXFtBWPS5thjG3jiicJMF4Pevbvy0ENOOZKZ5gJgxQoPTz2V3FDce+8tZL31\nuia07/TpPi65pLjJNls/2yQjkaTgE5G1gIOBV0RkbSBld9mIyO4i8oCIPC4iW6Uqjsk9I0Y08O67\nvqxY7nL+fKfGEr55LZFZUsFJCuPGJbc63YIF8f9Nr766mGXLGj+PBx4o5KGHmt4U2LdvV954I/M1\nLJMbEkkKtwIfAq+46yq8C1yTwjKVqmp4Ar69UhjH5JgNN6rgzxVeNt+iKz17VTT56tGvD6X3pm/2\nleY1hCVLUpOo2hp9dM89Rbz9duMJP16fxa+/2thWk5hEZkl9UlU3VNVzRaQCOERV/9WeYCIy2B3i\nioh4RGSyiLwvIm+JSH833isiUgaMxfouOr1EJ9ZrbabVP//syBI5mieFSZOK4+/cQb7/PvM1JJP/\nEpkl9WQR+YeI9AS+Bp4VkeuSDSQi44EHgfB/z8FAsaruBEwAJrr7rYUz4d4Vqros2TgmvyQz42qs\nYa0ffgibbNK1w4d5hm8qa28Hc2UlfPZZ7H+/+qhRtzNnNvY/7LVXOdtsU95i/0WLvKxY4fwcCjmJ\nY/LkwpR1fpv8lkid8kzgAuAo4EVgK2CfdsRaABwS9XgX4HUAd8K97dzttwNrAzeKyKHtiGPySKwh\nq9ddW8NhI+pjDlttbv585yQZ3e7eEcJJob3J5sYbi9l775Yn+IULPQwZ0pgEb721sQaycqWHRYta\n/sted10xJ51U2qQ8V15Z0uHv2XQOCQ2DUNU/RGQ/4O+q6heR5HrKnGNME5H1ozZVACuiHgdExKuq\nJyRzXJ/PS0VF0sVpF4uVHfFOPhm23LKA5ctLWX/9ps81P+5XXzkn0draEiqazqLRqlmzPPz8M5x4\nYuyz/gsv+Bg0qIwdd2x8Pvp9lZYWUVHhjFBqaGj5eo8n9r9efX3LCYgLC5vuW1FR2uIzrKwsiGwP\n69Kl8T0BezfgAAAgAElEQVRfdFEJ48a1fwLCfP17tFgxXpvAPl+JyMtAf2CWiDwDfNyuaE1VAtHj\n7LyqmvStSX5/kMrKmg4oTtsqKkotVhbE8/nguOOKuO46D7ffXtdkac/mx503z7nq/vXXetZbL/H2\nlHPPLeO77woYMSLWVF9dqa31cMEFBbz+ehXhf6PGv8WuzJ3rJxgMsNdeAcaMaXmir6/3Ay2nDq+q\nqiP63zIUAr+/6b6VlTVRn6HzLxQIOLH9/jLA6XhetaqWyspQZJ/V+czz9e+xM8fq2TP2MOdEmo9O\nAm4BhqhqPfC4u211zQH2AxCRIcD8Djim6STOOKOel18uZOHC+E0kwSB8+SVsv30g6c7mggRHcMa7\nP2HSpGKOPbaMe+8tZOrUlvdWTJkSey2JG25o2mEdPWNqIqKbsw44oIxFi6wJySQnblIQkdPcHy8B\nhgJnicgVwEDg0g6IPQ2oE5E5OP0I53bAMU0n0b07jBlTz2WXxV/v6b//9VBRARtsEOTPP5M7OSba\nSdt8zqPmd1xfdVVy61G9917blfepU1vu8+WXBUyf3nT7jz96OeOMpvHPPLOEOXPsngUTX2t/gZ5m\n31ebqv4E7OT+HALO6Khjm87n9NPreeaZ+PdRzp9fwIABIbp1C7FiRXJ/xuGb0trSvKN55MjUr542\nZkwpY8bA7NlNr+k++aTlyX7u3Kb/4s8+W0hJSYidd7ahSSa21pLCpwCqenWaymJMUoqK4Lbb6uDA\n2M9/8kkBO+wQYsWKEKtWJZsUEt9v440D/PFH+ptpvvyyaVK4997cX97UZF5rfQrhqbMRkdvTUBZj\nkjZkSPwr3g8+KGDwYOjaNcTKlalLCkVF0NCQ/qQwdmz6RoyZzqO1pBD9Vz4s1QUxpiOET+Y//ujh\nxx897LJLiK5dnXWPk5Ho/QfhpJDo3EfZ6I47iqiqynQpTLZIdEIUG8JgcsJxx5XywQcFXHRRCaNG\nNVBYmNqaQiAAxcWhlCaFjrob+/nnndbi8HxKgQAcf3wJN95YHLM/wnROrSWFUJyfjclagwYFuOyy\nYvr1C3L++c58EckkhZoa6NWra8JJIRQKNx+1t8Tp88ADTfscqqrg9dczPxW5yS6tdTRvIyLhBltP\n9M9ASFXt0sJknXPPrefcc5su2ZlM81F4lFKiaxD4/U5SgNQttBOez2j1j9P0cXhqDIDx40v44Qcv\nS5Yk2c5m8k7cpKCqNteuyQtduiReUwjfLBbvprHmzUSBgAefL0RhYepqCx3VfBR9nI8+8vLuu43/\n/j/80Pjvruqle/cQPXtaA0FnZCd+k/e6dk18SGqlO7+e3x97/+Y1CL/fmRzP58v+pDBvnlO5f/zx\nIv72t5aT8YXtums5p52W3E13Jn9YUjB5r6Ii8ZpCdXXr+9XWNn0+GHQSQnW1hx13TE2LakdP+52I\nOXN8rGo5E7npBCwpmLzXpYvTp5DIybW6uvXn6+qaPvb7G+dJWrAgvwbp/fijnR46ozYnWhERD3A6\nsIe7/2xgUntmNDUm1Xr2ajk/dh/AD9C77dcf536FBft1oXr8BGrOHAu0bD4KBBKfPK+90llT6NWr\ncebMyZOLOOecerp1C9Grl48lS9JXDpM5iVwK3ALsDUwBHsG5kc3ucDZZI9GV2dqj+TKfNTVNawPp\nSAqZMnVqIQ89VBjpZzGdQyJJYS/gUFV9SVVfBA6jfSuvGZMSySzZ2R7Ry3w2bz4Kjz5KpUz0KZjO\nK5FFdnzuV33UY5ti0WSNmjPHRpp3mgsvNjJ8eBm33FLLwIGtt3pOmlTEtdc6axqEYtzI37yjOTz6\nKJWyJSl8/72HDTfMksKYlEnkz/mfwNsiMlZExgJvAU+mtljGdKxE72quaWNhrFh9Cj6fcy9Eqjz3\nXObuOn722cLItBg77pi62pjJHokkhZuBa4G+wAbA9ap6QyoLZUxHi5UUFi/2cP75TVc6a+t+huY1\nhXCfQnl5fl5Br1zpoaoqv0ZVmdYl0nz0kapuC7yW6sIYkyqxprp4++0CHn+8iNtvb+woWLrUw5pr\nhli+PPaJsGWfgpMUSvL4Xq+5cxt70hct8tCnT4hp03xsskmQLbawQYj5JpGk8D8R2RX4j6rWtbm3\nMVmoW7dQi4VwPDHO+0uWeOjbN8jy5bGHFLW8T8FDQQEUFuZnTQHg8ssbM94BB5SxzTYBpk8vZNdd\n/Tz3XHoWojfpk0hSGAS8AyAiIWxCPJODttoqwFtv+YDGuShiJYWlSz307dvyBB++/+Fs9yvi2g4t\nZvb72f0CeA/o1b7DBMub3v9hskebfQqq2lNVve4EeT73Z0sIJqfssEOADz8saDKSJzw9dvTspkuX\neqiocHZahXWspkrz+z9M9mgzKYjIUBGZ4z7cREQWishOKS6XMR2qX78QDQ3wyy+N1YNwB2p4aouG\nBmfq7LIyJyncVHJlSu9/6Oyi7/8w2SOR5qOJwPEAqqoish/wOLB9KgtmTEfyeJzawn/+U8B66znz\nXzcmBQ9duzp9DmuuGWKLLYL07h3kzlXnM+6H0YAz/cP776/i2WcLmTSpKLIm87nn1lFcDDNn+jr1\n6mXz5q2iT5/E+lViTUViskciQ1JLVPXL8ANV/T/AlmsyOSecFMLCNYTw+sQrVzqjlEaNauD996ta\nrL723/96eeaZQrp1azz5hSfEa6ujeZddcngRZ9OpJJIU/k9EbhaRLd2v64BvU10wYzrarrsGeOMN\nX2QEUbimEP6+apWHLl1CeDxQWNhyJbWXX/bxyy9eevRoTACBgIeCghC+Nurcu+2W35MA/PSTzaia\nLxL5TZ4MdAGewpkUrwtwaioLZUwqbLVVkC23DHLTTc4Na+H1AponBXCu/sNJIdw5HR6ttO660UnB\n2bd379ZrCtGT5l11VYJrfeaQgw4qy5rpOMzqabNPQVWXA2PSUBZjUu6uu2r429/K8flC/PKLc00U\nbkZatcpZewHCScHJAuHk8McfHs49t46KipA7vLVxmovbb69l9mxfi3shwqInzeuSp33XdXX5fRNf\nZxG3piAin7rfgyISiPoKikh+14VN3ureHaZPr+ajjwp4770CBg/2x6wphCe5CwYbk8Ly5c5w1eim\novCEeGVlNEkI337b9Pbp6JpCvk61PX16IuNWTLaL+1t0p7bAvT8h7URkGHC0qlpTlelQa60VYtq0\nGurr4YYbivn+e+dPfNUqT5M5jAoKQgQCTZNCt25NJ8UL1xSi3XlnDWus0XRb06SQn+0s48aVMHKk\nDTPNdXGTgogc39oLVXVKxxcnEntDYCBQ3Na+xrSHxwPFxTBkSIB77inknHOaNh9BY79CeBTS7787\nNYX6+sYaQfQiO19/7WfzzX0cfnjLkUapnl47G/j9NnFePmitvvcosASYhbOWQvRvPITT6Zw0ERkM\n3KSqw9ylPu8FBgC1wCmqulBVvwcmikjKEo8xAMOH+7nssmI+/tjbpPkIGpOC3z3HL1/u3M8QPVle\nfb2HoiLnNf37w6JFK2OORIqeUiPW9BrGZIvWrl+2xVl+c1OcJPAUcLKqnqiqJ7UnmIiMBx6ksQZw\nMFCsqjsBE3BulItm/z4mpXw+GDOmnjvuKKaqyjnphxUUhPsUnD/DhgYP3bo17VOor4eioqbHi8Xj\ngdtuc9qdOkOtweSuuH+eqjpPVSeo6iBgMjAc+I+I3CciQ9sZbwFwSNTjXYDX3Xgf4ky+Fy0/G19N\nVjn66AbmzfMyf763RfOR39/0foWKilCTPoHmSSEer5fInEoVFSHWWsumnDbZKaHhAqr6MfCxO4X2\nTcCxkPxsYao6TUTWj9pUAayIeuwXEa+qBt39W+3XAPD5vFRUlCZblHaxWLkXL5FYFRWw774wZYqP\nM8/0UFHhc18LZWWl1Nc37tunTwnl5Y0V2FCogDXW8FJRUdhqrNLSQsrKnJ/XWKOYX34JUlKSf1WG\nZH+vsfbPtr+Pzhar1aTgtvnvBowE9gXmAZOA6e2K1lIl0DXqcSQhJMrvD1JZmZ453cPr/Vqs3ImX\naKzBg31MmVKKz1dHZaVTNfB4yvnzz1oaGiB8DeT11lBf7wOcf7jq6iANDfVUVgZixGr8066ra6C2\nNgSUUlsbjhH9p58fEvmse7axfzb+feRjrJ49Y//9tTb6aDKwD/AZ8AxwkapWtb+YMc0B9geeFZEh\nwPwOPr4xCdluOycRxO5TaNyvpKRpv0FDQ/zmI2dIqyfyc7iD2TqaTTZrrf46GufyaCBwIzDfnTZ7\noYgs7KD404A6d2ru24FzO+i4xiSlX78QO+7oZ6ONGiuq4dFHzedAiu4obmjwxJ0Mb968xmuoQMAT\nSQbJdDSPHNnQ9k7GdKDWmo/6pSKgqv4E7OT+HALOSEUcY5Lh8cCLLzatbjcmBU+L7WF1dfFrCuGh\nquB0SLeVFCZNqmHsWKdZ6v77a6irc+ZlmjrVJiU26dPaHc0/pbMgxmQbrzd2TSF69FFDgzOjaizR\nzUQNDbTafLRkiTMtxuef1/PQQ0Uccohzc8TDD1tCMOmVf8MfjOkg4T6F6NFH4e1h9fUeiotjNx9F\n1wiiawqt9Sk0f85mHjXpZknBmDjCHcWtJYVEawp+vwevNzzZXuJn+lxLCuEZZ03usqRgTBw+n3Pz\nWniuo803d9qRopNAbW38PoXopHDggQ2Rx4nc7JarBg0qd4fwmlxlScGYOLxep/morg7+8pcgU6Y4\nHdHhYaseT4i6uvijjxoX5QnSv3/jkNR4NYt88eGHjVWpUAgWL7YxuLnEkoIxcYRHH9XUeNhyywB9\n+zon/379ggwe7MfnS6ymEL6vIZGawlZbNe3VzrV7Gk47rYFLLinmmWd87LlnGY8+WsjWW3fh1Vcb\nl0E12c2SgjFxhJPCH3946N69sTZQUQHTp9dQWBi+TyH268NTbj//vNPQ3lhTiN9RcOSR/shIpOjX\n5IoxY+q59NI6Lr+8hAULvFx0kbMU26hRpcyYYYvw5AJLCsbEER6S+uuvHnr1anki79HD2Rbvyr+s\nDM47r4711gs3N9Hq/vmgsBD23jvA449Xc889TdeiXrYsxzJcJ2VJwZg4CgpCBIMe5s4tYPDglivQ\nhmc9jXc17/XCxRc3Dl0KT4hXUpL4kKJcqymE7bBDkL/9zc/LLzfe1X3nnUUt7vkw2ceSgjFxFBTA\nypUwb17spBCr9tCacBLp1i3x1+RqUgjbYYcg8+atYsMNg/ToEWLcuJJMF8m0wZKCMXH4fPDvf/sY\nMCDQZJ2F6OeT0bOnkxSi73PoDPr0CTF3bhUjRzbwzDNNO2B++inHs14esqRgTBzFxfD22wXstFPs\nNo9kr+J79gw16URORK7XFKKdcUYDP/3U9P1vv30XFi3KozeZBywpGBNHWVmIb74pYNCgzDWE51NS\n8HigNMa6L5dfXsyqVXDTTUX88kseveEcZWPEjIkjfALr3z/2uk/BNKyomU9JIZ7p0wv5/nsvX39d\nwKxZPt58M0RlpfP519dDeXmmS9i5WE3BmDhKS50+gN69Y3copyMpNHfjjbVt75RDFixYyaGHNvD1\n105HyxdfFNCzp4+NNurKhRcWM3Bg0qv+mtVkScGYOMIT4YWHkjaXiZrCySfn18RCFRVw/PGN72n9\n9YORCQP/+c8i/vzTQ+/elhjSyZKCMXGsWNF6200magr5aMCAAIce2sA771Tx0UdVVFcH2G03Zz0J\nkQChkIc//gBVL08+6WPpUg+ff26nrlSxPgVj4qiszHxS6NUr/zNPeTncd1/TZrHbb6/l8suLmTKl\nlg026MKmm3alsDBEQ4OHI45oYPFiD1Ontr4wvWkfS7fGxHHggX6OOCJ+c82VV9Zx993tPzFFL9cZ\nz157JTfy6cMPV7W3OFll/fVDTJniJIrp06sZObKBbbZxEuS//lXIO+/4uO++PJ9uNkOspmBMHCec\n0MAJJ8RPCgMGBBkwoP1X8v36BVEt4IUX4q9M09boo9Gj6/n5Zw+vvlroHjPHVuVJwFZbBbn77lqq\nquD99ws49link+eKK0r49Vcve+7pZ/vtA3H7fjq7UAimTvUxdWoha64Z4rzz6tl00/h/t1ZTMCZD\nws1P3bq1/0S+zjrBpO+szkUeD3TpAnvuGWDatGo23jjACSfUU14e4pZbitliiy6MHl3C7NkFNr9S\nMy+84OPOO4s47rgGttwyyIgRpey2W/wMaknBmAwJN4ckei/Clls2nu2+/dYf+bmtJTufeKKxJnLr\nrW0PaT3ppPo298kUrxd23jnAnDnV3HprHRdfXM8rr1Tz6aer2GGHANdfX8ygQeXcdFMRn37qpTa/\nRvAmrboarr++mNtuq+PAA/2cfXY9X3xRxb/+Fb/Z05KCMRkyaZJzxkokKZx0Uj1vvdW+BZCT7ZfY\nZZfcu9Rec01nuO6sWdU88UQNVVUezj+/BJEu7LlnGeefX8ysWQV5O2Ksvh4uuaSYrbYq5+CDSznr\nLC/PPuvj6quLGTgw0GSqloICWGed+FcSnaDiaUx28rqXZIkkhb59m57N2qodjB5dz5AhAU48seW8\nEttsE2DevPiz8nXvHuKpp6o56qjUN9L37FURe/tqHHOo+xXxhfv1eJwyrEasRATLu1A9fgJcfGHK\nYlxzTTHff+/lhReq+fVXLz/9VMzzzxfy22+eVmsFsVhSMCbD2koKd9xRy777xu/wjpUgRo5sYMMN\nY18WDx7cMikUFIQIBJyCDBkS4O23UzeVa7C8C96q/BgllQhv1SrKbr2RhhQlhV9/9TB1aiH//ncV\nPXuG2HDDABUVIY47rn0j46z5yJgMayspHHNMA927N9225pqNr22r1pBMrET3WR3V4ycQLO9cdymn\nMglOnVrIwQc3RKZmX11WUzAmw5I9CS9ZspKKihjTjbbT8cfXs9ZaISZOLG6zPJttFuCbb1avFlFz\n5lhqzhwb9/mKilIqK9NzY1pFRSkrVtTw9ddeZs8uYPZsH598UsCAAQF23jnAvvv62XzzYLvXwIjX\nPNaRXn7Zx9VX13XY8bIuKYjIjsBoIASMU9XKDBfJmJTyeFbvCu/yy+uorPTw3nuN/87xag+xTvi3\n3eacUMJJId5+ANtuG6Cy0sOvv+ZPI4PHA1tsEWSLLYKcdVYD1dUwZ04B777r49RTS6mshOHDAxxz\nTD3bbx/s0JpUZSV89VUB33zjZdEiD717h1h33RAbbBBk002DkX6neH780cOiRR6GDOm4wQFZlxSA\n09yvHYAjgQcyWxxjUmt17zPo3z/EI4/U8MorrR+oW7cQf/2rn2+/LWp3LI8HNt882CIpbLZZgAMP\n9Md5VW4pK3OSwPDhAa69to7PPvMya5aPs88upaoK1lwzhNfrfA5bbRVgyJAAAwe2PaypuKSwRad2\nT2BD4MB2lrUnsBRgndjPtSrOlUNak4KIDAZuUtVhIuIB7gUGALXAKaq6EPCqar2ILAZ2T2f5jEm3\nN9+sYoMNVr8tuKICjjqq9ZPyAw/U0LdviDXWaDtea1fDXbs6rx82zM+ff3r47LMCZs+ubvOqNlcN\nHBhk4MB6Lrignv/+10N1tYf6evjqKy/z5xfw8MNFrLNOkN12C7DBBkHWXjtEeXmI+noP+5R0obA2\ntzrV05YURGQ8cBwQ/oQOBopVdSc3WUx0t1WLSBFO7lucrvIZkwlbbbV6A+djnYjXWivIX/7S8sQf\nPtHvt5+fm28upqwsRHV17LN/a0nh1ltref75QtZYIxSZSTZfE0I0j8eZk8lp2cad4sTPtdfW8dpr\nPr780svMmT6WLHESR1FRiB97X8Epv1xDaSB3EkM6awoLgENoHC28C/A6gKp+KCLbudsfBO53yzY6\njeUzJqc8+2x1zKVCv/66CnDuZo2ltRN+QYFzwisujr9P166w/fYB9t7bzwMPtL8pKl/4fHDAAX4O\nOCDWs6ezitNZRcd1oC9Z4mHSpCKee87HuHH1jB7dcrhyIrHiNS+lLSmo6jQRWT9qUwWwIupxQES8\nqvopcGKix/X5vB06EsNi5Ve8fI61//6tn5DDfRXhMpWXF1NREaJLs9Gg0WUOhZzHw4fDBx/4GTLE\nOcjee4eYMcNDYaGPigov770XAgp5+GFvi2Osrnz+nXVErIoKuOsuuOuuIM4pvOVpfHViZbKjuRLo\nGvXYq6pJ16X9/mBah69ZrNyK15ljOTWFru5+XamurqOyMsCqVV6i//Ubj9O1yeP+/Ru3vfhigFdf\ndWbXrKxsbJrq37+ETz7xdej7zrbPMV9j9ezZNeb2TLYEzgH2AxCRIcD8DJbFmLy31lrOyTzecNWZ\nM6t4442mbU7h5iRw5kQKHyNs4sRavv8+d9rLTdsyWVOYBgwXkTnu44SbjIwxyfn555Wt9hMAMdeG\nWLRoFb17x76iBCgsdL5M/khrUlDVn4Cd3J9DwBnpjG9MZxLdoRwrISQ65cXChSuB9PU5mczKxpvX\njDFpcNddtXFHKEVr3jFt8pslBWPyVEkJTJkS/6yfL3cgm47VCW45MaZz8nhgn31yb8Eck1mWFIzp\nZJKZatt0PpYUjDHGRFhSMMYYE2FJwZhOpk+fIGutlacr2JvVZknBmE5mjTUaJ80zpjlLCsYYYyIs\nKRhjjImwpGCMMSbCkoIxxpgISwrGGGMiLCkYY4yJsKRgjDEmwpKCMcaYCEsKxhhjIiwpGGOMibCk\nYIwxJsKSgjHGmAhLCsYYYyIsKRhjjImwpGCMMSbCkoIxxpgISwrGGGMiLCkYY4yJsKRgjDEmIiuT\ngogME5EHM10OY4zpbLIuKYjIhsBAoDjTZTHGmM7Gl44gIjIYuElVh4mIB7gXGADUAqeo6sLwvqr6\nPTBRRKako2zGGGMapbymICLjgQdpvPI/GChW1Z2ACcBEd79rRORJEVnD3c+T6rIZY4xpKh01hQXA\nIcDj7uNdgNcBVPVDERnk/nxFs9eF0lA2Y4wxUTyhUOrPvSKyPvCUqu7kdiA/q6oz3Od+BPqrajDl\nBTHGGNOqTHQ0VwJdo8tgCcEYY7JDJpLCHGA/ABEZAszPQBmMMcbEkJbRR81MA4aLyBz38YkZKIMx\nxpgY0tKnYIwxJjdk3c1rxhhjMseSgjHGmAhLCsYYYyIsKRhjjInIxOijlBKRYcDRqnpqrMepiCMi\nOwKjce7CHqeqlR0ZKyrmEcBeOPd6XKaqVamI48YahDMyrAK4TVU/T2GsccA2wMbAE6p6XwpjbQaM\nw5l25VZV/TqFsbYGJgELgUdV9Z1UxYqK2Rt4WVW3T3GcbYGx7sMLVXVpCmPtDhwJlAK3qGrKh7Gn\n6rzRLEZazhtR8RJ6T3lVU2g+w2qqZlyNcdzT3K+Hcf54U+UA4FScKUNOSGEcgO2AzYB1gZ9TGUhV\n78L5/L5MZUJwnQL8gjMZ448pjjUY+A3wA1+lOFbYeFL/vsD52x8HvArsmOJYpap6GnA7zkVRSqVx\npuZ0nTeSek9ZX1NYnRlWk5lxdTVnci1Q1XoRWQzsnqr3B9wNPAT8BCR9F3iSsT7F+WPdHdgfSGrW\n2iRjARwFPJ/se2pHrI1wEup27vfJKYz1HvA00BvnZH1RKt+biJwOPAGcn2ycZGOp6lz35tPzgcNT\nHOsVESnDqZkk/Rm2I95qz9ScYDxve88bycZK5j1ldU2hA2dYbXXG1dWIE1YlIkXAOsDiVL0/YG2c\nK91/k+TVe5KxngKuxanWLgO6pzDWkyKyJrCbqr6RTJx2vq+lQDXwB0nOxNuO39c2QAHwp/s91e/t\nMJzmiB1EZEQq35uIbA98gjM7QVJJqB2xeuI0w12hqsuSidXOeKs1U3Oi8YDq9pw32hkrrM33lNVJ\ngcYZVsOazLAKRGZYVdWjVfVPd7/md+S1dYdee+OEPQjcj1MVfCKB99WuuMAK4FFgFPBMEnGSjXUU\nztXG4zhXZ8m8p2RjHa2qy3Hai9sj2fc1Gef3dS7wVApjHY1To5sE3Ox+T1ZS701V91TVM4APVfW5\nFMY6Gmf+sn8AtwD/THGs23AuiG4UkUOTjJV0vFbOIx0Vbzt3e3vPG8nEGtRs/zbfU1Y3H6nqNHeG\n1bAKnBNjmF9EWkyop6rHt/a4o+Oo6qe0Y7qOZOOq6mxgdrJx2hnrJeCldMRyX3NMOmKp6ie0sz+m\nHbHmAnPbE6s98aJe1+rfe0fEUtW3gLeSjdPOWKvVf5bOzzHBeAE3XrvOG0nGav5Ztvmesr2m0Fy6\nZljN1Eyu6YxrsXIrVrrj5WusfI+32rFyLSmka4bVTM3kms64Fiu3YqU7Xr7Gyvd4qx0rq5uPYkjX\nDKuZmsk1nXEtVm7FSne8fI2V7/FWO5bNkmqMMSYi15qPjDHGpJAlBWOMMRGWFIwxxkRYUjDGGBNh\nScEYY0yEJQVjjDERlhSMMcZE5NrNa8YkxJ0P5lucdQzCM0OGgAdVNanpsju4XCfgzFw5HbgS+AG4\n353ILrzPNjhTl49S1ZhTHYvIScDhqrpPs+3/AObh3LS0ObCxqv43Fe/F5CdLCiaf/aqq22a6EDG8\nqKonuYnrd2AfEfGoavhO0iOAJW0c4xngdhFZKzydtIiU4qx9cZ6q/l1Emq9ZYUybLCmYTklEFgHP\n4kw13IBz1f2TOMuQ3oEzlfcyYLS7fTbOGgyb45y0NwWuBqqAz3D+lx4HrlXVnd0YxwODVXVMK0VZ\n5b5+NyC8XOdwYFZUWfdxY/lwahanqupyEZnmluUed9eDgTejpn5u13oApnOzPgWTz9YVkU/dr8/c\n71u4z60NzHRrEu8BZ4lIIc7Kdkep6iCcZp6Hoo73uapuBizCSRzD3P26AyF3OuneItLP3f8EnPUv\n2vIMMBIia2N/DtS7j9cCbgT2UtXtgDdw1jDAPXb0lOPH46xxYEy7WU3B5LPWmo9CwAz35y+BXYFN\ngA2Bl9xlDQG6RL3mQ/f7rsD7qhpeLesxnKt0cJYtPVZEHgV6qepHbZQxhNO/cL37+AjgXzjLk4Kz\nzokqVCIAAAGwSURBVHNfYLZbJi9OkxOq+q6I9HCboWpx+g9mthHPmFZZUjCdlqrWuz+GcJpaCoDv\nw4nEPQn3jnpJjfs9QPzlNR/FWfmqjgTXtVbVKhGZJyK7AsNw1iEOJ4UC4D1VPdgtUxHOQiphj+HU\nFmpo/+pdxkRY85HJZ621qcd67v+A7iKyi/v4FODJGPu9DwwSkd5u4jgSd5lDd6TPL8DpOH0MiZoK\n3AR83GxRlA+BHUVkY/fxlTQ2H4GTeA7FWZ/5kSTiGROT1RRMPltHRD5ttu1dVT2HGGvVqmq9iBwO\n3CUixTirWIWXLwxF7bdMRMbhdAbXAD/SWIsAp/nnkKjmpURMx+m/uDQ6nqr+zx1++oyIeHESzrFR\nZflFRJYCHlX9KYl4xsRk6ykYkyQR6Q6crapXuY/vAr5V1XtExIdz9f6Mqr4Q47UnAENVNeULN4nI\nD8Bf7T4FkwxrPjImSar6B7CGiHwlIp/jrIn7oPv0r4A/VkKIcoDbEZ0SIlIiIp/hjLAyJilWUzDG\nGBNhNQVjjDERlhSMMcZEWFIwxhgTYUnBGGNMhCUFY4wxEZYUjDHGRPw/PCiTIUUUagEAAAAASUVO\nRK5CYII=\n", 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N73Q6ue++BxgzZhyPPfZos+WNVcYlBxEpFZGPReSUVMdu397DrFm1dO7s5uSTS1izRjuq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\n+KP1PP8hsU6nNWku3KqsyVy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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1896,21 +1927,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 3", + "display_name": "Python 2", "language": "python", - "name": "python3" + "name": "python2" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 3 + "version": 2 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython3", - "version": "3.5.1" + "pygments_lexer": "ipython2", + "version": "2.7.6" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index c39f21dfa..21aae7e40 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -32,7 +32,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/romano/miniconda3/envs/default/lib/python3.5/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", + "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -543,6 +543,7 @@ "* `CaptureXS` (`\"capture\"`)\n", "* `FissionXS` (`\"fission\"`)\n", "* `NuFissionXS` (`\"nu-fission\"`)\n", + "* `KappaFissionXS` (`\"kappa-fission\"`)\n", "* `ScatterXS` (`\"scatter\"`)\n", "* `NuScatterXS` (`\"nu-scatter\"`)\n", "* `ScatterMatrixXS` (`\"scatter matrix\"`)\n", @@ -722,10 +723,11 @@ " 888\n", "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", - " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", - " Date/Time: 2016-05-05 15:06:49\n", + " Git SHA1: 7b20f8ad4aa9e6f02f8b1d51e002f9f56ba7aa15\n", + " Date/Time: 2016-05-09 13:39:11\n", + " MPI Processes: 1\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -811,20 +813,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.1500E-01 seconds\n", - " Reading cross sections = 1.1800E-01 seconds\n", - " Total time in simulation = 5.3686E+01 seconds\n", - " Time in transport only = 5.3657E+01 seconds\n", - " Time in inactive batches = 4.3970E+00 seconds\n", - " Time in active batches = 4.9289E+01 seconds\n", - " Time synchronizing fission bank = 3.0000E-03 seconds\n", + " Total time for initialization = 5.0300E-01 seconds\n", + " Reading cross sections = 1.0400E-01 seconds\n", + " Total time in simulation = 4.8096E+01 seconds\n", + " Time in transport only = 4.8074E+01 seconds\n", + " Time in inactive batches = 4.1080E+00 seconds\n", + " Time in active batches = 4.3988E+01 seconds\n", + " Time synchronizing fission bank = 4.0000E-03 seconds\n", " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 5.4118E+01 seconds\n", - " Calculation Rate (inactive) = 5685.70 neutrons/second\n", - " Calculation Rate (active) = 2028.85 neutrons/second\n", + " Total time elapsed = 4.8613E+01 seconds\n", + " Calculation Rate (inactive) = 6085.69 neutrons/second\n", + " Calculation Rate (active) = 2273.35 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -950,8 +952,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/romano/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", - " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n" + "/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n" ] }, { @@ -965,6 +966,7 @@ " cell\n", " group in\n", " nuclide\n", + " score\n", " mean\n", " std. dev.\n", " \n", @@ -975,6 +977,7 @@ " 10000\n", " 1\n", " U-235\n", + " (nu-fission / flux)\n", " 8.055246e-03\n", " 2.857567e-05\n", " \n", @@ -983,6 +986,7 @@ " 10000\n", " 1\n", " U-238\n", + " (nu-fission / flux)\n", " 7.339215e-03\n", " 4.349466e-05\n", " \n", @@ -991,6 +995,7 @@ " 10000\n", " 1\n", " O-16\n", + " (nu-fission / flux)\n", " 0.000000e+00\n", " 0.000000e+00\n", " \n", @@ -999,6 +1004,7 @@ " 10000\n", " 2\n", " U-235\n", + " (nu-fission / flux)\n", " 3.615565e-01\n", " 2.050486e-03\n", " \n", @@ -1007,6 +1013,7 @@ " 10000\n", " 2\n", " U-238\n", + " (nu-fission / flux)\n", " 6.742638e-07\n", " 3.795256e-09\n", " \n", @@ -1015,6 +1022,7 @@ " 10000\n", " 2\n", " O-16\n", + " (nu-fission / flux)\n", " 0.000000e+00\n", " 0.000000e+00\n", " \n", @@ -1023,13 +1031,13 @@ "" ], "text/plain": [ - " cell group in nuclide mean std. dev.\n", - "3 10000 1 U-235 8.055246e-03 2.857567e-05\n", - "4 10000 1 U-238 7.339215e-03 4.349466e-05\n", - "5 10000 1 O-16 0.000000e+00 0.000000e+00\n", - "0 10000 2 U-235 3.615565e-01 2.050486e-03\n", - "1 10000 2 U-238 6.742638e-07 3.795256e-09\n", - "2 10000 2 O-16 0.000000e+00 0.000000e+00" + " cell group in nuclide score mean std. dev.\n", + "3 10000 1 U-235 (nu-fission / flux) 8.06e-03 2.86e-05\n", + "4 10000 1 U-238 (nu-fission / flux) 7.34e-03 4.35e-05\n", + "5 10000 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00\n", + "0 10000 2 U-235 (nu-fission / flux) 3.62e-01 2.05e-03\n", + "1 10000 2 U-238 (nu-fission / flux) 6.74e-07 3.80e-09\n", + "2 10000 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00" ] }, "execution_count": 30, @@ -1178,6 +1186,7 @@ " cell\n", " group in\n", " nuclide\n", + " score\n", " mean\n", " std. dev.\n", " \n", @@ -1188,6 +1197,7 @@ " 10000\n", " 1\n", " U-235\n", + " (nu-fission / flux)\n", " 0.074860\n", " 0.000303\n", " \n", @@ -1196,6 +1206,7 @@ " 10000\n", " 1\n", " U-238\n", + " (nu-fission / flux)\n", " 0.005952\n", " 0.000035\n", " \n", @@ -1204,6 +1215,7 @@ " 10000\n", " 1\n", " O-16\n", + " (nu-fission / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -1212,10 +1224,10 @@ "" ], "text/plain": [ - " cell group in nuclide mean std. dev.\n", - "0 10000 1 U-235 0.074860 0.000303\n", - "1 10000 1 U-238 0.005952 0.000035\n", - "2 10000 1 O-16 0.000000 0.000000" + " cell group in nuclide score mean std. dev.\n", + "0 10000 1 U-235 (nu-fission / flux) 7.49e-02 3.03e-04\n", + "1 10000 1 U-238 (nu-fission / flux) 5.95e-03 3.52e-05\n", + "2 10000 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00" ] }, "execution_count": 36, @@ -1299,12 +1311,12 @@ "[ NORMAL ] Computing the eigenvalue...\n", "[ NORMAL ] Iteration 0:\tk_eff = 0.854370\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.801922\tres = 1.521E-01\n", - "[ NORMAL ] Iteration 2:\tk_eff = 0.761745\tres = 6.349E-02\n", + "[ NORMAL ] Iteration 2:\tk_eff = 0.761746\tres = 6.349E-02\n", "[ NORMAL ] Iteration 3:\tk_eff = 0.732367\tres = 5.029E-02\n", "[ NORMAL ] Iteration 4:\tk_eff = 0.711075\tres = 3.869E-02\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.696557\tres = 2.912E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.687673\tres = 2.044E-02\n", - "[ NORMAL ] Iteration 7:\tk_eff = 0.683469\tres = 1.277E-02\n", + "[ NORMAL ] Iteration 7:\tk_eff = 0.683470\tres = 1.277E-02\n", "[ NORMAL ] Iteration 8:\tk_eff = 0.683129\tres = 6.141E-03\n", "[ NORMAL ] Iteration 9:\tk_eff = 0.685949\tres = 7.889E-04\n", "[ NORMAL ] Iteration 10:\tk_eff = 0.691329\tres = 4.181E-03\n", @@ -1317,11 +1329,11 @@ "[ NORMAL ] Iteration 17:\tk_eff = 0.765800\tres = 1.655E-02\n", "[ NORMAL ] Iteration 18:\tk_eff = 0.778371\tres = 1.660E-02\n", "[ NORMAL ] Iteration 19:\tk_eff = 0.790897\tres = 1.643E-02\n", - "[ NORMAL ] Iteration 20:\tk_eff = 0.803272\tres = 1.611E-02\n", - "[ NORMAL ] Iteration 21:\tk_eff = 0.815414\tres = 1.566E-02\n", + "[ NORMAL ] Iteration 20:\tk_eff = 0.803273\tres = 1.611E-02\n", + "[ NORMAL ] Iteration 21:\tk_eff = 0.815415\tres = 1.566E-02\n", "[ NORMAL ] Iteration 22:\tk_eff = 0.827256\tres = 1.513E-02\n", "[ NORMAL ] Iteration 23:\tk_eff = 0.838747\tres = 1.453E-02\n", - "[ NORMAL ] Iteration 24:\tk_eff = 0.849846\tres = 1.390E-02\n", + "[ NORMAL ] Iteration 24:\tk_eff = 0.849847\tres = 1.390E-02\n", "[ NORMAL ] Iteration 25:\tk_eff = 0.860527\tres = 1.324E-02\n", "[ NORMAL ] Iteration 26:\tk_eff = 0.870770\tres = 1.258E-02\n", "[ NORMAL ] Iteration 27:\tk_eff = 0.880562\tres = 1.191E-02\n", @@ -1343,8 +1355,8 @@ "[ NORMAL ] Iteration 43:\tk_eff = 0.981021\tres = 4.104E-03\n", "[ NORMAL ] Iteration 44:\tk_eff = 0.984493\tres = 3.814E-03\n", "[ NORMAL ] Iteration 45:\tk_eff = 0.987729\tres = 3.543E-03\n", - "[ NORMAL ] Iteration 46:\tk_eff = 0.990741\tres = 3.290E-03\n", - "[ NORMAL ] Iteration 47:\tk_eff = 0.993545\tres = 3.053E-03\n", + "[ NORMAL ] Iteration 46:\tk_eff = 0.990742\tres = 3.290E-03\n", + "[ NORMAL ] Iteration 47:\tk_eff = 0.993546\tres = 3.053E-03\n", "[ NORMAL ] Iteration 48:\tk_eff = 0.996153\tres = 2.833E-03\n", "[ NORMAL ] Iteration 49:\tk_eff = 0.998577\tres = 2.627E-03\n", "[ NORMAL ] Iteration 50:\tk_eff = 1.000829\tres = 2.436E-03\n", @@ -1358,63 +1370,63 @@ "[ NORMAL ] Iteration 58:\tk_eff = 1.013868\tres = 1.314E-03\n", "[ NORMAL ] Iteration 59:\tk_eff = 1.015006\tres = 1.215E-03\n", "[ NORMAL ] Iteration 60:\tk_eff = 1.016059\tres = 1.124E-03\n", - "[ NORMAL ] Iteration 61:\tk_eff = 1.017033\tres = 1.038E-03\n", + "[ NORMAL ] Iteration 61:\tk_eff = 1.017033\tres = 1.039E-03\n", "[ NORMAL ] Iteration 62:\tk_eff = 1.017933\tres = 9.596E-04\n", "[ NORMAL ] Iteration 63:\tk_eff = 1.018766\tres = 8.865E-04\n", "[ NORMAL ] Iteration 64:\tk_eff = 1.019535\tres = 8.188E-04\n", - "[ NORMAL ] Iteration 65:\tk_eff = 1.020246\tres = 7.561E-04\n", + "[ NORMAL ] Iteration 65:\tk_eff = 1.020246\tres = 7.562E-04\n", "[ NORMAL ] Iteration 66:\tk_eff = 1.020903\tres = 6.981E-04\n", - "[ NORMAL ] Iteration 67:\tk_eff = 1.021509\tres = 6.444E-04\n", + "[ NORMAL ] Iteration 67:\tk_eff = 1.021509\tres = 6.445E-04\n", "[ NORMAL ] Iteration 68:\tk_eff = 1.022069\tres = 5.948E-04\n", - "[ NORMAL ] Iteration 69:\tk_eff = 1.022586\tres = 5.488E-04\n", + "[ NORMAL ] Iteration 69:\tk_eff = 1.022586\tres = 5.489E-04\n", "[ NORMAL ] Iteration 70:\tk_eff = 1.023063\tres = 5.064E-04\n", "[ NORMAL ] Iteration 71:\tk_eff = 1.023503\tres = 4.671E-04\n", "[ NORMAL ] Iteration 72:\tk_eff = 1.023909\tres = 4.308E-04\n", "[ NORMAL ] Iteration 73:\tk_eff = 1.024284\tres = 3.973E-04\n", "[ NORMAL ] Iteration 74:\tk_eff = 1.024629\tres = 3.663E-04\n", - "[ NORMAL ] Iteration 75:\tk_eff = 1.024947\tres = 3.377E-04\n", + "[ NORMAL ] Iteration 75:\tk_eff = 1.024948\tres = 3.377E-04\n", "[ NORMAL ] Iteration 76:\tk_eff = 1.025241\tres = 3.113E-04\n", "[ NORMAL ] Iteration 77:\tk_eff = 1.025512\tres = 2.869E-04\n", "[ NORMAL ] Iteration 78:\tk_eff = 1.025761\tres = 2.644E-04\n", "[ NORMAL ] Iteration 79:\tk_eff = 1.025991\tres = 2.436E-04\n", "[ NORMAL ] Iteration 80:\tk_eff = 1.026203\tres = 2.244E-04\n", "[ NORMAL ] Iteration 81:\tk_eff = 1.026398\tres = 2.067E-04\n", - "[ NORMAL ] Iteration 82:\tk_eff = 1.026577\tres = 1.904E-04\n", - "[ NORMAL ] Iteration 83:\tk_eff = 1.026743\tres = 1.753E-04\n", + "[ NORMAL ] Iteration 82:\tk_eff = 1.026578\tres = 1.904E-04\n", + "[ NORMAL ] Iteration 83:\tk_eff = 1.026743\tres = 1.754E-04\n", "[ NORMAL ] Iteration 84:\tk_eff = 1.026895\tres = 1.615E-04\n", "[ NORMAL ] Iteration 85:\tk_eff = 1.027036\tres = 1.487E-04\n", "[ NORMAL ] Iteration 86:\tk_eff = 1.027165\tres = 1.369E-04\n", "[ NORMAL ] Iteration 87:\tk_eff = 1.027284\tres = 1.260E-04\n", "[ NORMAL ] Iteration 88:\tk_eff = 1.027393\tres = 1.160E-04\n", - "[ NORMAL ] Iteration 89:\tk_eff = 1.027493\tres = 1.067E-04\n", - "[ NORMAL ] Iteration 90:\tk_eff = 1.027586\tres = 9.824E-05\n", - "[ NORMAL ] Iteration 91:\tk_eff = 1.027671\tres = 9.043E-05\n", - "[ NORMAL ] Iteration 92:\tk_eff = 1.027750\tres = 8.318E-05\n", - "[ NORMAL ] Iteration 93:\tk_eff = 1.027822\tres = 7.654E-05\n", - "[ NORMAL ] Iteration 94:\tk_eff = 1.027889\tres = 7.041E-05\n", - "[ NORMAL ] Iteration 95:\tk_eff = 1.027950\tres = 6.481E-05\n", - "[ NORMAL ] Iteration 96:\tk_eff = 1.028006\tres = 5.960E-05\n", - "[ NORMAL ] Iteration 97:\tk_eff = 1.028058\tres = 5.480E-05\n", - "[ NORMAL ] Iteration 98:\tk_eff = 1.028105\tres = 5.043E-05\n", - "[ NORMAL ] Iteration 99:\tk_eff = 1.028149\tres = 4.634E-05\n", - "[ NORMAL ] Iteration 100:\tk_eff = 1.028189\tres = 4.266E-05\n", - "[ NORMAL ] Iteration 101:\tk_eff = 1.028226\tres = 3.920E-05\n", - "[ NORMAL ] Iteration 102:\tk_eff = 1.028260\tres = 3.604E-05\n", - "[ NORMAL ] Iteration 103:\tk_eff = 1.028291\tres = 3.316E-05\n", - "[ NORMAL ] Iteration 104:\tk_eff = 1.028320\tres = 3.047E-05\n", - "[ NORMAL ] Iteration 105:\tk_eff = 1.028347\tres = 2.800E-05\n", - "[ NORMAL ] Iteration 106:\tk_eff = 1.028371\tres = 2.576E-05\n", - "[ NORMAL ] Iteration 107:\tk_eff = 1.028393\tres = 2.367E-05\n", - "[ NORMAL ] Iteration 108:\tk_eff = 1.028414\tres = 2.176E-05\n", - "[ NORMAL ] Iteration 109:\tk_eff = 1.028433\tres = 2.003E-05\n", - "[ NORMAL ] Iteration 110:\tk_eff = 1.028450\tres = 1.836E-05\n", + "[ NORMAL ] Iteration 89:\tk_eff = 1.027494\tres = 1.068E-04\n", + "[ NORMAL ] Iteration 90:\tk_eff = 1.027587\tres = 9.825E-05\n", + "[ NORMAL ] Iteration 91:\tk_eff = 1.027672\tres = 9.041E-05\n", + "[ NORMAL ] Iteration 92:\tk_eff = 1.027751\tres = 8.319E-05\n", + "[ NORMAL ] Iteration 93:\tk_eff = 1.027823\tres = 7.654E-05\n", + "[ NORMAL ] Iteration 94:\tk_eff = 1.027889\tres = 7.042E-05\n", + "[ NORMAL ] Iteration 95:\tk_eff = 1.027950\tres = 6.478E-05\n", + "[ NORMAL ] Iteration 96:\tk_eff = 1.028007\tres = 5.959E-05\n", + "[ NORMAL ] Iteration 97:\tk_eff = 1.028058\tres = 5.481E-05\n", + "[ NORMAL ] Iteration 98:\tk_eff = 1.028106\tres = 5.041E-05\n", + "[ NORMAL ] Iteration 99:\tk_eff = 1.028150\tres = 4.636E-05\n", + "[ NORMAL ] Iteration 100:\tk_eff = 1.028190\tres = 4.263E-05\n", + "[ NORMAL ] Iteration 101:\tk_eff = 1.028227\tres = 3.920E-05\n", + "[ NORMAL ] Iteration 102:\tk_eff = 1.028261\tres = 3.604E-05\n", + "[ NORMAL ] Iteration 103:\tk_eff = 1.028292\tres = 3.314E-05\n", + "[ NORMAL ] Iteration 104:\tk_eff = 1.028321\tres = 3.047E-05\n", + "[ NORMAL ] Iteration 105:\tk_eff = 1.028347\tres = 2.801E-05\n", + "[ NORMAL ] Iteration 106:\tk_eff = 1.028371\tres = 2.575E-05\n", + "[ NORMAL ] Iteration 107:\tk_eff = 1.028394\tres = 2.367E-05\n", + "[ NORMAL ] Iteration 108:\tk_eff = 1.028414\tres = 2.175E-05\n", + "[ NORMAL ] Iteration 109:\tk_eff = 1.028433\tres = 1.999E-05\n", + "[ NORMAL ] Iteration 110:\tk_eff = 1.028450\tres = 1.838E-05\n", "[ NORMAL ] Iteration 111:\tk_eff = 1.028466\tres = 1.689E-05\n", - "[ NORMAL ] Iteration 112:\tk_eff = 1.028481\tres = 1.553E-05\n", - "[ NORMAL ] Iteration 113:\tk_eff = 1.028494\tres = 1.427E-05\n", - "[ NORMAL ] Iteration 114:\tk_eff = 1.028507\tres = 1.309E-05\n", - "[ NORMAL ] Iteration 115:\tk_eff = 1.028518\tres = 1.202E-05\n", - "[ NORMAL ] Iteration 116:\tk_eff = 1.028528\tres = 1.107E-05\n", - "[ NORMAL ] Iteration 117:\tk_eff = 1.028538\tres = 1.015E-05\n" + "[ NORMAL ] Iteration 112:\tk_eff = 1.028481\tres = 1.552E-05\n", + "[ NORMAL ] Iteration 113:\tk_eff = 1.028494\tres = 1.426E-05\n", + "[ NORMAL ] Iteration 114:\tk_eff = 1.028507\tres = 1.310E-05\n", + "[ NORMAL ] Iteration 115:\tk_eff = 1.028518\tres = 1.204E-05\n", + "[ NORMAL ] Iteration 116:\tk_eff = 1.028528\tres = 1.106E-05\n", + "[ NORMAL ] Iteration 117:\tk_eff = 1.028538\tres = 1.017E-05\n" ] } ], @@ -1556,7 +1568,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 43, @@ -1565,9 +1577,9 @@ }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1575,6 +1587,10 @@ } ], "source": [ + "# Ignore zero fission rates in guide tubes with Matplotlib color scheme\n", + "openmc_fission_rates[openmc_fission_rates == 0] = np.nan\n", + "openmoc_fission_rates[openmoc_fission_rates == 0] = np.nan\n", + "\n", "# Plot OpenMC's fission rates in the left subplot\n", "fig = plt.subplot(121)\n", "plt.imshow(openmc_fission_rates, interpolation='none', cmap='jet')\n", @@ -1589,21 +1605,21 @@ ], "metadata": { "kernelspec": { - "display_name": "Python 3", + "display_name": "Python 2", "language": "python", - "name": "python3" + "name": "python2" }, "language_info": { "codemirror_mode": { "name": "ipython", - "version": 3 + "version": 2 }, "file_extension": ".py", "mimetype": "text/x-python", "name": "python", "nbconvert_exporter": "python", - "pygments_lexer": "ipython3", - "version": "3.5.1" + "pygments_lexer": "ipython2", + "version": "2.7.6" } }, "nbformat": 4, From 502482dcf630ee6e290c15b8535e6e850a351c88 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 18:24:25 -0400 Subject: [PATCH 100/147] Type checking now ensures that Legendre moments do not exceed 10 --- openmc/mgxs/library.py | 2 +- openmc/mgxs/mgxs.py | 7 +++++-- 2 files changed, 6 insertions(+), 3 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index ad0bfd77a..f2a5c7569 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -59,7 +59,7 @@ class Library(object): correction : {'P0', None} Apply the P0 correction to scattering matrices if set to 'P0' legendre_order : int - The highest legendre moments in the scattering matrices (default is 0) + The highest legendre moment in the scattering matrices (default is 0) energy_groups : openmc.mgxs.EnergyGroups Energy group structure for energy condensation tally_trigger : openmc.Trigger diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 051dd3cf1..1479f7241 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1948,6 +1948,7 @@ class ScatterMatrixXS(MGXS): def legendre_order(self, legendre_order): cv.check_type('legendre_order', legendre_order, Integral) cv.check_greater_than('legendre_order', legendre_order, 0, equality=True) + cv.check_less_than('legendre_order', legendre_order, 10, equality=True) if self.correction == 'P0' and legendre_order > 0: msg = 'The P0 correction will be ignored since the scattering ' \ @@ -2112,7 +2113,8 @@ class ScatterMatrixXS(MGXS): if moment != 'all': cv.check_type('moment', moment, Integral) cv.check_greater_than('moment', moment, 0, equality=True) - cv.check_less_than('moment', moment, 10, equality=True) + cv.check_less_than( + 'moment', moment, self.legendre_order, equality=True) scores = [self.xs_tally.scores[moment]] else: scores = [] @@ -2230,7 +2232,8 @@ class ScatterMatrixXS(MGXS): if moment != 'all': cv.check_type('moment', moment, Integral) cv.check_greater_than('moment', moment, 0, equality=True) - cv.check_less_than('moment', moment, 10, equality=True) + cv.check_less_than( + 'moment', moment, self.legendre_order, equality=True) df = df[df['score'] == str(self.xs_tally.scores[moment])] return df From bbb5690a003f33cc0e21ea22299a081be67bc0c0 Mon Sep 17 00:00:00 2001 From: jingang Date: Mon, 9 May 2016 19:27:29 -0400 Subject: [PATCH 101/147] fix errors of setting material density using 'sum' --- docs/source/usersguide/input.rst | 8 ++++---- openmc/material.py | 26 ++++++++++++++++---------- 2 files changed, 20 insertions(+), 14 deletions(-) diff --git a/docs/source/usersguide/input.rst b/docs/source/usersguide/input.rst index 2158e1d8c..37b441ef2 100644 --- a/docs/source/usersguide/input.rst +++ b/docs/source/usersguide/input.rst @@ -1215,11 +1215,11 @@ Each ``material`` element can have the following attributes or sub-elements: An element with attributes/sub-elements called ``value`` and ``units``. The ``value`` attribute is the numeric value of the density while the ``units`` can be "g/cm3", "kg/m3", "atom/b-cm", "atom/cm3", or "sum". The "sum" unit - indicates that values appearing in ``ao`` attributes for ```` and - ```` sub-elements are to be interpreted as nuclide/element - densities in atom/b-cm, and the total density of the material is taken as + indicates that values appearing in ``ao`` or ``wo`` attributes for ```` and + ```` sub-elements are to be interpreted as absolute nuclide/element + densities in atom/b-cm or g/cm3, and the total density of the material is taken as the sum of all nuclides/elements. The "sum" option cannot be used in - conjunction with weight percents. The "macro" unit is used with + conjunction with atom or weight percents. The "macro" unit is used with a ``macroscopic`` quantity to indicate that the density is already included in the library and thus not needed here. However, if a value is provided for the ``value``, then this is treated as a number density multiplier on diff --git a/openmc/material.py b/openmc/material.py index ff690aa9a..c74f8f1cd 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -245,19 +245,25 @@ class Material(object): """ - cv.check_type('the density for Material ID="{0}"'.format(self._id), - density, Real) cv.check_value('density units', units, DENSITY_UNITS) - - if density is None and units is not 'sum': - msg = 'Unable to set the density for Material ID="{0}" ' \ - 'because a density must be set when not using ' \ - 'sum unit'.format(self._id) - raise ValueError(msg) - - self._density = density self._density_units = units + if units is 'sum': + if density is not None: + msg = 'Density "{0}" for Material ID="{1}" is ignored ' \ + 'because the unit is "sum"'.format(density, self._id) + warnings.warn(msg) + else: + if density is None: + msg = 'Unable to set the density for Material ID="{0}" ' \ + 'because a density must be set when not using ' \ + '"sum" unit'.format(self._id) + raise ValueError(msg) + + cv.check_type('the density for Material ID="{0}"'.format(self._id), + density, Real) + self._density = density + @distrib_otf_file.setter def distrib_otf_file(self, filename): # TODO: remove this when distributed materials are merged From 95406d52fcc0541dc039b1a99db3b4d6056ff1c8 Mon Sep 17 00:00:00 2001 From: liangjg Date: Mon, 9 May 2016 22:34:18 -0400 Subject: [PATCH 102/147] update description according to comments --- docs/source/usersguide/input.rst | 9 ++++----- openmc/material.py | 8 ++++---- 2 files changed, 8 insertions(+), 9 deletions(-) diff --git a/docs/source/usersguide/input.rst b/docs/source/usersguide/input.rst index 37b441ef2..775407d70 100644 --- a/docs/source/usersguide/input.rst +++ b/docs/source/usersguide/input.rst @@ -1215,11 +1215,10 @@ Each ``material`` element can have the following attributes or sub-elements: An element with attributes/sub-elements called ``value`` and ``units``. The ``value`` attribute is the numeric value of the density while the ``units`` can be "g/cm3", "kg/m3", "atom/b-cm", "atom/cm3", or "sum". The "sum" unit - indicates that values appearing in ``ao`` or ``wo`` attributes for ```` and - ```` sub-elements are to be interpreted as absolute nuclide/element - densities in atom/b-cm or g/cm3, and the total density of the material is taken as - the sum of all nuclides/elements. The "sum" option cannot be used in - conjunction with atom or weight percents. The "macro" unit is used with + indicates that values appearing in ``ao`` or ``wo`` attributes for ```` + and ```` sub-elements are to be interpreted as absolute nuclide/element + densities in atom/b-cm or g/cm3, and the total density of the material is + taken as the sum of all nuclides/elements. The "macro" unit is used with a ``macroscopic`` quantity to indicate that the density is already included in the library and thus not needed here. However, if a value is provided for the ``value``, then this is treated as a number density multiplier on diff --git a/openmc/material.py b/openmc/material.py index c74f8f1cd..e9a74f1e7 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -251,16 +251,16 @@ class Material(object): if units is 'sum': if density is not None: msg = 'Density "{0}" for Material ID="{1}" is ignored ' \ - 'because the unit is "sum"'.format(density, self._id) + 'because the unit is "sum"'.format(density, self.id) warnings.warn(msg) else: if density is None: msg = 'Unable to set the density for Material ID="{0}" ' \ - 'because a density must be set when not using ' \ - '"sum" unit'.format(self._id) + 'because a density value must be given when not using ' \ + '"sum" unit'.format(self.id) raise ValueError(msg) - cv.check_type('the density for Material ID="{0}"'.format(self._id), + cv.check_type('the density for Material ID="{0}"'.format(self.id), density, Real) self._density = density From 4201cb98722e5be3a0b6b74abca639ecedac7745 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 9 May 2016 23:02:31 -0400 Subject: [PATCH 103/147] Fixed issue with lattice cell indexing for p-value calculation in Pandas DF notebook --- .../examples/pandas-dataframes.ipynb | 58 +++++++++---------- 1 file changed, 29 insertions(+), 29 deletions(-) diff --git a/docs/source/pythonapi/examples/pandas-dataframes.ipynb b/docs/source/pythonapi/examples/pandas-dataframes.ipynb index 0f93999e2..b88cf9949 100644 --- a/docs/source/pythonapi/examples/pandas-dataframes.ipynb +++ b/docs/source/pythonapi/examples/pandas-dataframes.ipynb @@ -370,7 +370,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -554,8 +554,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 7b20f8ad4aa9e6f02f8b1d51e002f9f56ba7aa15\n", - " Date/Time: 2016-05-09 12:52:02\n", + " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", + " Date/Time: 2016-05-09 23:01:18\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -619,20 +619,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.1000E-01 seconds\n", - " Reading cross sections = 9.7000E-02 seconds\n", - " Total time in simulation = 9.8510E+00 seconds\n", - " Time in transport only = 9.8370E+00 seconds\n", - " Time in inactive batches = 1.3970E+00 seconds\n", - " Time in active batches = 8.4540E+00 seconds\n", + " Total time for initialization = 3.9000E-01 seconds\n", + " Reading cross sections = 8.6000E-02 seconds\n", + " Total time in simulation = 1.0830E+01 seconds\n", + " Time in transport only = 1.0818E+01 seconds\n", + " Time in inactive batches = 1.3590E+00 seconds\n", + " Time in active batches = 9.4710E+00 seconds\n", " Time synchronizing fission bank = 3.0000E-03 seconds\n", - " Sampling source sites = 3.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.0275E+01 seconds\n", - " Calculation Rate (inactive) = 8947.75 neutrons/second\n", - " Calculation Rate (active) = 4435.77 neutrons/second\n", + " Total time elapsed = 1.1234E+01 seconds\n", + " Calculation Rate (inactive) = 9197.94 neutrons/second\n", + " Calculation Rate (active) = 3959.46 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1097,7 +1097,7 @@ "data": { "image/png": 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J50fEc2PFt6sP9v2SHsm7EE5tUx3MrGrDtWIbICnqtrWjHG03sLDu+Vn5viJl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\n", "text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2042,15 +2042,15 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 6.038663783e-42\n" + "Mann-Whitney Test p-value: 0.303583331507\n" ] } ], "source": [ - "# Extract tally data from pins in the pins divided along y=-x diagonal\n", + "# Extract tally data from pins in the pins divided along y=x diagonal \n", "multi_index = ('level 2', 'lat',)\n", - "lower = df[df[multi_index + ('x',)] > df[multi_index + ('y',)]]\n", - "upper = df[df[multi_index + ('x',)] < df[multi_index + ('y',)]]\n", + "lower = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] < 16]\n", + "upper = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] > 16]\n", "lower = lower[lower['score'] == 'absorption']\n", "upper = upper[upper['score'] == 'absorption']\n", "\n", @@ -2080,15 +2080,15 @@ "name": "stdout", "output_type": "stream", "text": [ - "Mann-Whitney Test p-value: 0.303583331507\n" + "Mann-Whitney Test p-value: 6.038663783e-42\n" ] } ], "source": [ - "# Extract tally data from pins in the pins divided along y=x diagonal \n", + "# Extract tally data from pins in the pins divided along y=-x diagonal\n", "multi_index = ('level 2', 'lat',)\n", - "lower = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] < 16]\n", - "upper = df[df[multi_index + ('x',)] + df[multi_index + ('y',)] > 16]\n", + "lower = df[df[multi_index + ('x',)] > df[multi_index + ('y',)]]\n", + "upper = df[df[multi_index + ('x',)] < df[multi_index + ('y',)]]\n", "lower = lower[lower['score'] == 'absorption']\n", "upper = upper[upper['score'] == 'absorption']\n", "\n", @@ -2126,7 +2126,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 36, @@ -2137,7 +2137,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, From 3079b5f6df0eb7c5c1b86b11be67b35b3ff518fd Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 10 May 2016 04:45:02 -0400 Subject: [PATCH 104/147] Simplification of mgxs_library - not done yet --- openmc/mgxs_library.py | 703 +++++++++++------------------------------ 1 file changed, 191 insertions(+), 512 deletions(-) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index bae23b0bc..ba9ba75b0 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -99,6 +99,12 @@ class XSdata(object): Unique identifier for the xsdata object alias : str Separate unique identifier for the xsdata object + zaid : int + 1000*(atomic number) + mass number. As an example, the zaid of U-235 + would be 92235. + awr : float + Atomic-weight-ratio of an isotope. That is, the ratio of the mass + of the isotope to the mass of a single neutron. kT : float Temperature (in units of MeV). energy_groups : openmc.mgxs.EnergyGroups @@ -198,7 +204,7 @@ class XSdata(object): """ - def __init__(self, name, energy_groups, representation="isotropic"): + def __init__(self, name, energy_groups, representation='isotropic'): # Initialize class attributes self._name = name self._energy_groups = energy_groups @@ -319,15 +325,7 @@ class XSdata(object): @energy_groups.setter def energy_groups(self, energy_groups): # Check validity of energy_groups - check_type("energy_groups", energy_groups, openmc.mgxs.EnergyGroups) - - # Check that there are one or more groups - ng = energy_groups.num_groups - if ((ng is None) or (ng < 1)): - - msg = 'energy_groups object incorrectly initialized.' - raise ValueError(msg) - + check_type('energy_groups', energy_groups, openmc.mgxs.EnergyGroups) self._energy_groups = energy_groups @representation.setter @@ -347,48 +345,48 @@ class XSdata(object): @zaid.setter def zaid(self, zaid): # Check type and value - check_type("zaid", zaid, Integral) - check_greater_than("zaid", zaid, 0, equality=False) + check_type('zaid', zaid, Integral) + check_greater_than('zaid', zaid, 0, equality=False) self._zaid = zaid @awr.setter def awr(self, awr): # Check validity of type and that the awr value is > 0 - check_type("awr", awr, Real) - check_greater_than("awr", awr, 0.0, equality=False) + check_type('awr', awr, Real) + check_greater_than('awr', awr, 0.0, equality=False) self._awr = awr @kT.setter def kT(self, kT): # Check validity of type and that the kT value is >= 0 - check_type("kT", kT, Real) - check_greater_than("kT", kT, 0.0, equality=True) + check_type('kT', kT, Real) + check_greater_than('kT', kT, 0.0, equality=True) self._kT = kT @scatt_type.setter def scatt_type(self, scatt_type): # check to see it is of a valid type and value - check_value("scatt_type", scatt_type, ['legendre', 'histogram', + check_value('scatt_type', scatt_type, ['legendre', 'histogram', 'tabular']) self._scatt_type = scatt_type @order.setter def order(self, order): # Check type and value - check_type("order", order, Integral) - check_greater_than("order", order, 0, equality=True) + check_type('order', order, Integral) + check_greater_than('order', order, 0, equality=True) self._order = order @tabular_legendre.setter def tabular_legendre(self, tabular_legendre): # Check to make sure this is a dict and it has our keys with the # right values. - check_type("tabular_legendre", tabular_legendre, dict) + check_type('tabular_legendre', tabular_legendre, dict) if 'enable' in tabular_legendre: enable = tabular_legendre['enable'] check_type('enable', enable, bool) else: - msg = "enable must be provided in tabular_legendre" + msg = 'enable must be provided in tabular_legendre' raise ValueError(msg) if 'num_points' in tabular_legendre: num_points = tabular_legendre['num_points'] @@ -404,14 +402,14 @@ class XSdata(object): @num_polar.setter def num_polar(self, num_polar): # Make sure we have positive ints - check_value("num_polar", num_polar, Integral) - check_greater_than("num_polar", num_polar, 0) + check_value('num_polar', num_polar, Integral) + check_greater_than('num_polar', num_polar, 0) self._num_polar = num_polar @num_azimuthal.setter def num_azimuthal(self, num_azimuthal): - check_value("num_azimuthal", num_azimuthal, Integral) - check_greater_than("num_azimuthal", num_azimuthal, 0) + check_value('num_azimuthal', num_azimuthal, Integral) + check_greater_than('num_azimuthal', num_azimuthal, 0) self._num_azimuthal = num_azimuthal @total.setter @@ -422,7 +420,7 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("total", total, np.ndarray, expected_iter_type=Real) + check_type('total', total, np.ndarray, expected_iter_type=Real) if total.shape == shape: self._total = np.copy(total) else: @@ -438,7 +436,7 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("absorption", absorption, np.ndarray, + check_type('absorption', absorption, np.ndarray, expected_iter_type=Real) if absorption.shape == shape: self._absorption = np.copy(absorption) @@ -455,7 +453,7 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("fission", fission, np.ndarray, expected_iter_type=Real) + check_type('fission', fission, np.ndarray, expected_iter_type=Real) if fission.shape == shape: self._fission = np.copy(fission) if np.sum(self._fission) > 0.0: @@ -473,7 +471,7 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("k_fission", k_fission, np.ndarray, + check_type('k_fission', k_fission, np.ndarray, expected_iter_type=Real) if k_fission.shape == shape: self._k_fission = np.copy(k_fission) @@ -497,7 +495,7 @@ class XSdata(object): shape = (self._num_polar, self._num_azimuthal, self._energy_groups.num_groups) # check we have a numpy list - check_type("chi", chi, np.ndarray, expected_iter_type=Real) + check_type('chi', chi, np.ndarray, expected_iter_type=Real) if chi.shape == shape: self._chi = np.copy(chi) else: @@ -519,7 +517,7 @@ class XSdata(object): self._energy_groups.num_groups) max_depth = 5 # check we have a numpy list - check_iterable_type("scatter", scatter, expected_type=Real, + check_iterable_type('scatter', scatter, expected_type=Real, max_depth=max_depth) if scatter.shape == shape: self._scatter = np.copy(scatter) @@ -540,7 +538,7 @@ class XSdata(object): self._energy_groups.num_groups) max_depth = 4 # check we have a numpy list - check_iterable_type("multiplicity", multiplicity, expected_type=Real, + check_iterable_type('multiplicity', multiplicity, expected_type=Real, max_depth=max_depth) if multiplicity.shape == shape: self._multiplicity = np.copy(multiplicity) @@ -582,7 +580,7 @@ class XSdata(object): else: shape = shape_mat if nu_fission.shape != shape: - msg = "Invalid Shape of Nu_fission!" + msg = 'Invalid Shape of Nu_fission!' raise ValueError(msg) else: # Get shape of nu_fission to determine if we need chi or not @@ -591,523 +589,204 @@ class XSdata(object): elif nu_fission.shape == shape_mat: self._use_chi = False else: - msg = "Invalid Shape of Nu_fission!" + msg = 'Invalid Shape of Nu_fission!' raise ValueError(msg) # check we have a numpy list - check_type("nu_fission", nu_fission, np.ndarray, + check_type('nu_fission', nu_fission, np.ndarray, expected_iter_type=Real) self._nu_fission = np.copy(nu_fission) if np.sum(self._nu_fission) > 0.0: self._fissionable = True - def set_total(self, total, **kwargs): - if (isinstance(total, openmc.mgxs.TotalXS) or - isinstance(total, openmc.mgxs.TransportXS)): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != total.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + def set_total(self, total, subdomain, nuclide='sum', xs_type='macro'): + if not isinstance(total, (openmc.mgxs.TotalXS, + openmc.mgxs.TransportXS)): + msg = 'Method must be passed an openmc.mgxs.TotalXS or ' \ + 'openmc.mgxs.TransportXS object' + raise TypeError(msg) - if self._representation is 'isotropic': - self._total = total.get_xs(subdomains=subdomains, - nuclides=nuclides, xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != total.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type("total", total, np.ndarray, expected_iter_type=Real) - if total.shape == shape: - self._total = np.copy(total) - else: - msg = 'Shape of provided total "{0}" does not match shape ' \ - 'required, "{1}"'.format(total.shape, shape) - raise ValueError(msg) + if self._representation is 'isotropic': + self._total = total.get_xs(subdomain=subdomains, nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - def set_absorption(self, absorption, **kwargs): - if isinstance(absorption, openmc.mgxs.AbsorptionXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != absorption.energy_groups: - msg = 'Group structure of provided AbsorptionXS does not ' \ - ' match group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + def set_absorption(self, absorption, subdomain, nuclide='sum', + xs_type='macro'): + if not isinstance(absorption, openmc.mgxs.AbsorptionXS): + msg = 'Method must be passed an openmc.mgxs.AbsorptionXS' + raise TypeError(msg) - if self._representation is 'isotropic': - self._absorption = absorption.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != absorption.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type("absorption", absorption, np.ndarray, expected_iter_type=Real) - if absorption.shape == shape: - self._absorption = np.copy(absorption) - else: - msg = 'Shape of provided absorption "{0}" does not match shape ' \ - 'required, "{1}"'.format(absorption.shape, shape) - raise ValueError(msg) + if self._representation is 'isotropic': + self._absorption = absorption.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - def set_fission(self, fission, **kwargs): - if isinstance(fission, openmc.mgxs.FissionXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != fission.energy_groups: - msg = 'Group structure of provided FissionXS does not match ' \ - 'group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + def set_fission(self, fission, subdomain, nuclide='sum', xs_type='macro'): + if not isinstance(fission, openmc.mgxs.FissionXS): + msg = 'Method must be passed an openmc.mgxs.FissionXS' + raise TypeError(msg) - if self._representation is 'isotropic': - self._fission = fission.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != fission.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type("fission", fission, np.ndarray, expected_iter_type=Real) - if fission.shape == shape: - self._fission = np.copy(fission) - if np.sum(self._fission) > 0.0: - self._fissionable = True - else: - msg = 'Shape of provided fission "{0}" does not match shape ' \ - 'required, "{1}"'.format(fission.shape, shape) - raise ValueError(msg) + if self._representation is 'isotropic': + self._fission = fission.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - def set_nu_fission(self, nu_fission, **kwargs): + def set_nu_fission(self, nu_fission, subdomain, nuclide='sum', + xs_type='macro'): # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. - if isinstance(nu_fission, openmc.mgxs.NuFissionXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != nu_fission.energy_groups: - msg = 'Group structure of provided NuFissionXS does not match'\ - ' group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + if not isinstance(nu_fission, openmc.mgxs.NuFissionXS): + msg = 'Method must be passed an openmc.mgxs.NuFissionXS' + raise TypeError(msg) - if self._representation is 'isotropic': - self._nu_fission = nu_fission.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != nu_fission.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - self._use_chi = True + if self._representation is 'isotropic': + self._nu_fission = nu_fission.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - else: - # nu_fission can be given as a vector or a matrix - # Vector is used when chi also exists. - # Matrix is used when chi does not exist. - # We have to check that the correct form is given, but only if - # chi already has been set. If not, we just check that this is OK - # and set the use_chi flag accordingly + self._use_chi = True - # First lets set our dimensions here since they get used repeatedly - # throughout this code. - if self._representation is 'isotropic': - shape_vec = (self._energy_groups.num_groups,) - shape_mat = (self._energy_groups.num_groups, - self._energy_groups.num_groups) - elif self._representation is 'angle': - shape_vec = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - shape_mat = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - - # Begin by checking the case when chi has already been given and - # thus the rules for filling in nu_fission are set. - if self._use_chi is not None: - if self._use_chi: - shape = shape_vec - else: - shape = shape_mat - if nu_fission.shape != shape: - msg = "Invalid Shape of Nu_fission!" - raise ValueError(msg) - else: - # Get shape of nu_fission to determine if we need chi or not - if nu_fission.shape == shape_vec: - self._use_chi = True - elif nu_fission.shape == shape_mat: - self._use_chi = False - else: - msg = "Invalid Shape of Nu_fission!" - raise ValueError(msg) - - # check we have a numpy list - check_type("nu_fission", nu_fission, np.ndarray, - expected_iter_type=Real) - self._nu_fission = np.copy(nu_fission) if np.sum(self._nu_fission) > 0.0: self._fissionable = True - def set_k_fission(self, k_fission, **kwargs): - if isinstance(k_fission, openmc.mgxs.KappaFissionXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != k_fission.energy_groups: - msg = 'Group structure of provided KappaFissionXS does not ' \ - 'match group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + def set_k_fission(self, k_fission, subdomain, nuclide='sum', + xs_type='macro'): + if not isinstance(k_fission, openmc.mgxs.KappaFissionXS): + msg = 'Method must be passed an openmc.mgxs.KappaFissionXS' + raise TypeError(msg) - if self._representation is 'isotropic': - self._k_fission = k_fission.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != k_fission.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type("k_fission", k_fission, np.ndarray, - expected_iter_type=Real) - if k_fission.shape == shape: - self._k_fission = np.copy(k_fission) - if np.sum(self._k_fission) > 0.0: - self._fissionable = True - else: - msg = 'Shape of provided k_fission "{0}" does not match ' \ - 'shape required, "{1}"'.format(k_fission.shape, shape) - raise ValueError(msg) + if self._representation is 'isotropic': + self._k_fission = k_fission.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - def set_chi(self, chi, **kwargs): + def set_chi(self, chi, subdomain, nuclide='sum', xs_type='macro'): if self._use_chi is not None: if not self._use_chi: - msg = 'Providing chi when nu_fission already provided as matrix!' + msg = 'Providing chi when nu_fission already provided as a ' \ + 'matrix!' raise ValueError(msg) - if isinstance(chi, openmc.mgxs.Chi): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != chi.energy_groups: - msg = 'Group structure of provided Chi does not ' \ - 'match group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + if not isinstance(chi, openmc.mgxs.Chi): + msg = 'Method must be passed an openmc.mgxs.Chi' + raise TypeError(msg) - if self._representation is 'isotropic': - self._chi = chi.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != chi.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type("chi", chi, np.ndarray, expected_iter_type=Real) - if chi.shape == shape: - self._chi = np.copy(chi) - else: - msg = 'Shape of provided chi "{0}" does not match shape ' \ - 'required, "{1}"'.format(chi.shape, shape) - raise ValueError(msg) - if self._use_chi is not None: - self._use_chi = True + if self._representation is 'isotropic': + self._chi = chi.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - def set_scatter(self, scatter, **kwargs): - if isinstance(scatter, openmc.mgxs.ScatterMatrixXS): - # Make sure passed MGXS object contains correct group structure - if self.energy_groups != scatter.energy_groups: - msg = 'Group structure of provided ScatterMatrixXS does not ' \ - 'match group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + if self._use_chi is not None: + self._use_chi = True - if self._representation is 'isotropic': - self._scatter = scatter.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + def set_scatter(self, scatter, subdomain, nuclide='sum', xs_type='macro'): + if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): + msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' + raise TypeError(msg) - else: - if self._representation is 'isotropic': - shape = (self.num_orders, self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 3 - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, self.num_orders, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 5 - # check we have a numpy list - check_iterable_type("scatter", scatter, expected_type=Real, - max_depth=max_depth) - if scatter.shape == shape: - self._scatter = np.copy(scatter) - else: - msg = 'Shape of provided scatter "{0}" does not match shape ' \ - 'required, "{1}"'.format(scatter.shape, shape) - raise ValueError(msg) + # Make sure passed MGXS object contains correct group structure + if self.energy_groups != scatter.energy_groups: + msg = 'Group structure of provided data does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) - def set_multiplicity(self, multiplicity, scatter=None, **kwargs): - if isinstance(multiplicity, openmc.mgxs.NuScatterMatrixXS): - if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): - msg = "Argument 'scatter' must be provided." - raise ValueError(msg) - # Make sure passed MGXS objects contain correct group structure - if self.energy_groups != multiplicity.energy_groups: - msg = 'Group structure of provided NuScatterMatrixXS does not ' \ - 'match group structure of XSdata object' - raise ValueError(msg) - if self.energy_groups != scatter.energy_groups: - msg = 'Group structure of provided ScatterMatrixXS does not ' \ - 'match group structure of XSdata object' - raise ValueError(msg) - # Get openmc.mgxs.get_xs() arguments from kwargs - # nuclides, xs_type, and value will have sane defaults but can be - # overridden by kwards - if 'nuclides' in kwargs: - nuclides = kwargs['nuclides'] - else: - nuclides = 'sum' - if 'xs_type' in kwargs: - xs_type = kwargs['xs_type'] - else: - xs_type = 'macro' - if 'value' in kwargs: - value = kwargs['value'] - else: - value = 'mean' - # subdomains is required from the kwargs as this is specific to - # this XSdata object. - if 'subdomains' in kwargs: - subdomains = kwargs['subdomains'] - else: - msg = "Argument 'subdomains' is required" - raise ValueError(msg) + if self._representation is 'isotropic': + self._scatter = scatter.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) - if self._representation is 'isotropic': - nuscatt = multiplicity.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - scatt = scatter.get_xs(subdomains=subdomains, - nuclides=nuclides, - xs_type=xs_type, - value=value) - self._multiplicity = np.divide(nuscatt, scatt) - elif self._representation is 'angle': - # Not yet implemented as MGXS do not yet support this - pass + def set_multiplicity(self, multiplicity, scatter, subdomain, + nuclide='sum', xs_type='macro'): + if not isinstance(multiplicity, openmc.mgxs.ScatterMatrixXS): + msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' + raise TypeError(msg) + if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): + msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' + raise TypeError(msg) - else: - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 2 - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 4 - # check we have a numpy list - check_iterable_type("multiplicity", multiplicity, expected_type=Real, - max_depth=max_depth) - if multiplicity.shape == shape: - self._multiplicity = np.copy(multiplicity) - else: - msg = 'Shape of provided multiplicity "{0}" does not match shape' \ - ' required, "{1}"'.format(multiplicity.shape, shape) - raise ValueError(msg) + # Make sure passed MGXS objects contain correct group structure + if self.energy_groups != multiplicity.energy_groups: + msg = 'Group structure of "multiplicity" does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) + if self.energy_groups != scatter.energy_groups: + msg = 'Group structure of "scatter" does not match' \ + ' group structure of XSdata object' + raise ValueError(msg) + + if self._representation is 'isotropic': + nuscatt = multiplicity.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + scatt = scatter.get_xs(subdomains=subdomain, + nuclides=nuclide, + xs_type=xs_type) + self._multiplicity = np.divide(nuscatt, scatt) + elif self._representation is 'angle': + msg = 'Angular-Dependent MGXS have not yet been implemented' + raise ValueError(msg) def _get_xsdata_xml(self): - element = ET.Element("xsdata") - element.set("name", self._name) + element = ET.Element('xsdata') + element.set('name', self._name) if self._alias is not None: subelement = ET.SubElement(element, 'alias') @@ -1213,7 +892,7 @@ class MGXSLibrary(object): self._xsdatas = [] self._energy_groups = energy_groups self._inverse_velocities = None - self._cross_sections_file = ET.Element("cross_sections") + self._cross_sections_file = ET.Element('cross_sections') @property def inverse_velocities(self): @@ -1232,7 +911,7 @@ class MGXSLibrary(object): @energy_groups.setter def energy_groups(self, energy_groups): - check_type("energy groups", energy_groups, openmc.mgxs.EnergyGroups) + check_type('energy groups', energy_groups, openmc.mgxs.EnergyGroups) self._energy_groups = energy_groups def add_xsdata(self, xsdata): @@ -1295,19 +974,19 @@ class MGXSLibrary(object): def _create_groups_subelement(self): if self._energy_groups is not None: - element = ET.SubElement(self._cross_sections_file, "groups") + element = ET.SubElement(self._cross_sections_file, 'groups') element.text = str(self._energy_groups.num_groups) def _create_group_structure_subelement(self): if self._energy_groups is not None: element = ET.SubElement(self._cross_sections_file, - "group_structure") + 'group_structure') element.text = ' '.join(map(str, self._energy_groups.group_edges)) def _create_inverse_velocities_subelement(self): if self._inverse_velocities is not None: element = ET.SubElement(self._cross_sections_file, - "inverse_velocities") + 'inverse_velocities') element.text = ' '.join(map(str, self._inverse_velocities)) def _create_xsdata_subelements(self): @@ -1341,4 +1020,4 @@ class MGXSLibrary(object): # Write the XML Tree to the xsdatas.xml file tree = ET.ElementTree(self._cross_sections_file) tree.write(filename, xml_declaration=True, - encoding='utf-8', method="xml") + encoding='utf-8', method='xml') From 33c52030a2a9d80afc2d6da0c3ccc4ed53d022c4 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 10 May 2016 05:32:04 -0400 Subject: [PATCH 105/147] Resolution of @paulromano comments --- src/mgxs_header.F90 | 194 ++++++++++++++-------------- src/scattdata_header.F90 | 269 ++++++++++++++++++++------------------- src/tally.F90 | 12 +- 3 files changed, 242 insertions(+), 233 deletions(-) diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 725aacffa..88c1b23e2 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -201,7 +201,7 @@ module mgxs_header ! the xsdata object node itself. !=============================================================================== - subroutine mgxs_init_file(this,node_xsdata,i_listing) + subroutine mgxs_init_file(this, node_xsdata, i_listing) class(Mgxs), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: i_listing ! Index in listings array @@ -236,7 +236,7 @@ module mgxs_header else if (temp_str == 'tabular') then this % scatt_type = ANGLE_TABULAR else - call fatal_error("Invalid Scatt Type Option!") + call fatal_error("Invalid scatt_type option!") end if else this % scatt_type = ANGLE_LEGENDRE @@ -259,8 +259,8 @@ module mgxs_header end subroutine mgxs_init_file - subroutine mgxsiso_init_file(this,node_xsdata,groups,get_kfiss,get_fiss, & - max_order,i_listing) + subroutine mgxsiso_init_file(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order, i_listing) class(MgxsIso), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups @@ -282,7 +282,7 @@ module mgxs_header integer :: legendre_mu_points, imu ! Call generic data gathering routine (will populate the metadata) - call mgxs_init_file(this,node_xsdata,i_listing) + call mgxs_init_file(this, node_xsdata, i_listing) ! Load the more specific data allocate(this % nu_fission(groups)) @@ -292,7 +292,7 @@ module mgxs_header ! Chi was provided, that means they are giving chi and nu-fission ! vectors ! Get chi - allocate(temp_arr(1 * groups)) + allocate(temp_arr(groups)) call get_node_array(node_xsdata, "chi", temp_arr) do gin = 1, groups do gout = 1, groups @@ -329,7 +329,7 @@ module mgxs_header end do ! Now pull out information needed for chi - this % chi = temp_2d + this % chi(:, :) = temp_2d ! Normalize chi so its CDF goes to 1 do gin = 1, groups this % chi(:, gin) = this % chi(:, gin) / sum(this % chi(:, gin)) @@ -375,14 +375,14 @@ module mgxs_header if (arr_len == groups * groups) then allocate(temp_arr(arr_len)) call get_node_array(node_xsdata, "multiplicity", temp_arr) - temp_mult = reshape(temp_arr, (/groups, groups/)) + temp_mult(:, :) = reshape(temp_arr, (/groups, groups/)) deallocate(temp_arr) else call fatal_error("Multiplicity length not same as number of groups& & squared!") end if else - temp_mult = ONE + temp_mult(:, :) = ONE end if ! Get scattering treatment information @@ -426,7 +426,7 @@ module mgxs_header if (check_for_node(node_xsdata, "order")) then call get_node_value(node_xsdata, "order", order) else - call fatal_error("Order Must Be Provided!") + call fatal_error("Order must be provided!") end if ! Before retrieving the data, store the dimensionality of the data in @@ -546,11 +546,11 @@ module mgxs_header if (check_for_node(node_xsdata, "total")) then call get_node_array(node_xsdata, "total", this % total) else - this % total = this % absorption + this % scatter % scattxs + this % total(:) = this % absorption(:) + this % scatter % scattxs(:) end if ! Deallocate temporaries for the next material - deallocate(input_scatt,scatt_coeffs,temp_mult) + deallocate(input_scatt, scatt_coeffs, temp_mult) ! Finally, check sigT to ensure it is not 0 since it is ! often divided by in the tally routines @@ -561,8 +561,8 @@ module mgxs_header end subroutine mgxsiso_init_file - subroutine mgxsang_init_file(this,node_xsdata,groups,get_kfiss,get_fiss, & - max_order,i_listing) + subroutine mgxsang_init_file(this, node_xsdata, groups, get_kfiss, get_fiss, & + max_order, i_listing) class(MgxsAngle), intent(inout) :: this ! Working Object type(Node), pointer, intent(in) :: node_xsdata ! Data from MGXS xml integer, intent(in) :: groups ! Number of Energy groups @@ -584,18 +584,18 @@ module mgxs_header integer :: legendre_mu_points, imu, ipol, iazi ! Call generic data gathering routine (will populate the metadata) - call mgxs_init_file(this,node_xsdata,i_listing) + call mgxs_init_file(this, node_xsdata, i_listing) if (check_for_node(node_xsdata, "num_polar")) then call get_node_value(node_xsdata, "num_polar", this % n_pol) else - call fatal_error("num_polar Must Be Provided!") + call fatal_error("num_polar must be provided!") end if if (check_for_node(node_xsdata, "num_azimuthal")) then call get_node_value(node_xsdata, "num_azimuthal", this % n_azi) else - call fatal_error("num_azimuthal Must Be Provided!") + call fatal_error("num_azimuthal must be provided!") end if ! Load angle data, if present (else equally spaced) @@ -663,8 +663,8 @@ module mgxs_header if (check_for_node(node_xsdata, "nu_fission")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "nu_fission", temp_arr) - this % nu_fission = reshape(temp_arr,(/groups, this % n_azi, & - this % n_pol/)) + this % nu_fission(:, :, :) = reshape(temp_arr, (/groups, & + this % n_azi, this % n_pol/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -677,8 +677,8 @@ module mgxs_header allocate(temp_arr(groups * groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "nu_fission", temp_arr) allocate(temp_4d(groups, groups, this % n_azi,this % n_pol)) - temp_4d = reshape(temp_arr, (/groups, groups, this % n_azi, & - this % n_pol/)) + temp_4d(:, :, :, :) = reshape(temp_arr, (/groups, groups, & + this % n_azi, this % n_pol/)) deallocate(temp_arr) else call fatal_error("If fissionable, must provide nu_fission!") @@ -716,8 +716,8 @@ module mgxs_header allocate(temp_arr(groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "fission", temp_arr) allocate(this % fission(groups, this % n_azi, this % n_pol)) - this % fission = reshape(temp_arr, (/groups, this % n_azi, & - this % n_pol/)) + this % fission(:, :, :) = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("Fission data missing, required due to fission& @@ -729,8 +729,8 @@ module mgxs_header allocate(temp_arr(groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "kappa_fission", temp_arr) allocate(this % k_fission(groups, this % n_azi, this % n_pol)) - this % k_fission = reshape(temp_arr, (/groups, this % n_azi, & - this % n_pol/)) + this % k_fission(:, :, :) = reshape(temp_arr, (/groups, & + this % n_azi, this % n_pol/)) deallocate(temp_arr) else call fatal_error("kappa_fission data missing, required due to & @@ -738,16 +738,16 @@ module mgxs_header end if end if else - this % nu_fission = ZERO - this % chi = ZERO + this % nu_fission(:, :, :) = ZERO + this % chi(:, :, :, :) = ZERO end if if (check_for_node(node_xsdata, "absorption")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "absorption", temp_arr) allocate(this % absorption(groups, this % n_azi, this % n_pol)) - this % absorption = reshape(temp_arr, (/groups, this % n_azi, & - this % n_pol/)) + this % absorption(:, :, :) = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else call fatal_error("Must provide absorption!") @@ -760,15 +760,15 @@ module mgxs_header if (arr_len == groups * groups * this % n_azi * this % n_pol) then allocate(temp_arr(arr_len)) call get_node_array(node_xsdata, "multiplicity", temp_arr) - temp_mult = reshape(temp_arr, (/groups, groups, this % n_azi, & - this % n_pol/)) + temp_mult(:, :, :, :) = reshape(temp_arr, (/groups, groups, & + this % n_azi, this % n_pol/)) deallocate(temp_arr) else call fatal_error("Multiplicity length not same as number of groups& & squared!") end if else - temp_mult = ONE + temp_mult(:, :, :, :) = ONE end if ! Get scattering treatment information @@ -812,7 +812,7 @@ module mgxs_header if (check_for_node(node_xsdata, "order")) then call get_node_value(node_xsdata, "order", order) else - call fatal_error("Order Must Be Provided!") + call fatal_error("Order must be provided!") end if ! Before retrieving the data, store the dimensionality of the data in @@ -836,8 +836,8 @@ module mgxs_header allocate(temp_arr(groups * groups * order_dim * this % n_azi * & this % n_pol)) call get_node_array(node_xsdata, "scatter", temp_arr) - input_scatt = reshape(temp_arr, (/groups, groups, order_dim, & - this % n_azi, this % n_pol/)) + input_scatt(:, :, :, :, :) = reshape(temp_arr, (/groups, groups, & + order_dim, this % n_azi, this % n_pol/)) deallocate(temp_arr) ! Compare the number of orders given with the maximum order of the @@ -951,8 +951,8 @@ module mgxs_header if (check_for_node(node_xsdata, "total")) then allocate(temp_arr(groups * this % n_azi * this % n_pol)) call get_node_array(node_xsdata, "total", temp_arr) - this % total = reshape(temp_arr, (/groups, this % n_azi, & - this % n_pol/)) + this % total(:, :, :) = reshape(temp_arr, (/groups, this % n_azi, & + this % n_pol/)) deallocate(temp_arr) else do ipol = 1, this % n_pol @@ -1251,7 +1251,7 @@ module mgxs_header if (present(gout)) then xs = this % chi(gout, gin, iazi, ipol) else - ! Not sure youd want a 1 or a 0, but here you go! + ! Not sure you would want a 1 or a 0, but here you go! xs = sum(this % chi(:, gin, iazi, ipol)) end if case('scatter') @@ -1316,7 +1316,7 @@ module mgxs_header ! objects !=============================================================================== - subroutine mgxs_combine(this,mat,scatt_type,i_listing) + subroutine mgxs_combine(this, mat, scatt_type, i_listing) class(Mgxs), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material integer, intent(in) :: scatt_type ! How is data presented @@ -1340,7 +1340,7 @@ module mgxs_header end subroutine mgxs_combine - subroutine mgxsiso_combine(this,mat,nuclides,groups,max_order,scatt_type, & + subroutine mgxsiso_combine(this, mat, nuclides, groups, max_order, scatt_type, & i_listing) class(MgxsIso), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material @@ -1373,9 +1373,9 @@ module mgxs_header do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) - if (order /= size(nuc % scatter % dist(1) % data,dim=1)) & - call fatal_error("All Histogram Scattering Entries Must Be& - & Same Length!") + if (order /= size(nuc % scatter % dist(1) % data, dim=1)) & + call fatal_error("All histogram scattering entries must be& + & same length!") end select end do ! Ok, got our order, store the dimensionality @@ -1390,8 +1390,8 @@ module mgxs_header select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) if (order /= size(nuc % scatter % dist(1) % data, dim=1)) & - call fatal_error("All Tabular Scattering Entries Must Be& - & Same Length!") + call fatal_error("All tabular scattering entries must be& + & same length!") end select end do ! Ok, got our order, store the dimensionality @@ -1406,7 +1406,7 @@ module mgxs_header do i = 1, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) - if (size(nuc % scatter % dist(1) % data,dim=1) > mat_max_order) & + if (size(nuc % scatter % dist(1) % data, dim=1) > mat_max_order) & mat_max_order = size(nuc % scatter % dist(1) % data, dim=1) end select end do @@ -1423,25 +1423,25 @@ module mgxs_header ! Allocate and initialize data needed for macro_xs(i_mat) object allocate(this % total(groups)) - this % total = ZERO + this % total(:) = ZERO allocate(this % absorption(groups)) - this % absorption = ZERO + this % absorption(:) = ZERO allocate(this % fission(groups)) - this % fission = ZERO + this % fission(:) = ZERO allocate(this % k_fission(groups)) - this % k_fission = ZERO + this % k_fission(:) = ZERO allocate(this % nu_fission(groups)) - this % nu_fission = ZERO + this % nu_fission(:) = ZERO allocate(this % chi(groups,groups)) - this % chi = ZERO + this % chi(:, :) = ZERO allocate(temp_mult(groups,groups)) - temp_mult = ZERO + temp_mult(:, :) = ZERO allocate(mult_num(groups,groups)) - mult_num = ZERO + mult_num(:, :) = ZERO allocate(mult_denom(groups,groups)) - mult_denom = ZERO + mult_denom(:, :) = ZERO allocate(scatt_coeffs(order_dim,groups,groups)) - scatt_coeffs = ZERO + scatt_coeffs(:, :, :) = ZERO ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -1452,19 +1452,19 @@ module mgxs_header select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) ! Add contributions to total, absorption, and fission data (if necessary) - this % total = this % total + atom_density * nuc % total - this % absorption = this % absorption + & - atom_density * nuc % absorption + this % total(:) = this % total(:) + atom_density * nuc % total(:) + this % absorption(:) = this % absorption(:) + & + atom_density * nuc % absorption(:) if (nuc % fissionable) then - this % chi = this % chi + atom_density * nuc % chi - this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission + this % chi(:, :) = this % chi(:, :) + atom_density * nuc % chi(:, :) + this % nu_fission(:) = this % nu_fission(:)+ atom_density * & + nuc % nu_fission(:) if (allocated(nuc % fission)) then - this % fission = this % fission + atom_density * nuc % fission + this % fission(:) = this % fission(:) + atom_density * nuc % fission(:) end if if (allocated(nuc % k_fission)) then - this % k_fission = this % k_fission + atom_density * & - nuc % k_fission + this % k_fission(:) = this % k_fission(:) + atom_density * & + nuc % k_fission(:) end if end if @@ -1498,7 +1498,7 @@ module mgxs_header nuc % scatter % get_matrix(min(nuc_order_dim, order_dim)) type is (MgxsAngle) - call fatal_error("Invalid Passing of MgxsAngle to MgxsIso Object") + call fatal_error("Invalid passing of MgxsAngle to MgxsIso object") end select end do @@ -1531,7 +1531,7 @@ module mgxs_header end subroutine mgxsiso_combine - subroutine mgxsang_combine(this,mat,nuclides,groups,max_order,scatt_type,& + subroutine mgxsang_combine(this, mat, nuclides, groups, max_order, scatt_type, & i_listing) class(MgxsAngle), intent(inout) :: this ! The Mgxs to initialize type(Material), pointer, intent(in) :: mat ! base material @@ -1551,7 +1551,7 @@ module mgxs_header real(8), allocatable :: mult_denom(:, :, :, :), scatt_coeffs(:, :, :, :, :) ! Set the meta-data - call mgxs_combine(this,mat,scatt_type,i_listing) + call mgxs_combine(this, mat, scatt_type, i_listing) ! Get the number of each polar and azi angles and make sure all the ! NuclideAngle types have the same number of these angles @@ -1564,12 +1564,12 @@ module mgxs_header n_pol = nuc % n_pol n_azi = nuc % n_azi allocate(this % polar(n_pol)) - this % polar = nuc % polar + this % polar(:) = nuc % polar(:) allocate(this % azimuthal(n_azi)) - this % azimuthal = nuc % azimuthal + this % azimuthal(:) = nuc % azimuthal(:) else if ((n_pol /= nuc % n_pol) .or. (n_azi /= nuc % n_azi)) then - call fatal_error("All Angular Data Must Be Same Length!") + call fatal_error("All angular data must be same length!") end if end if end select @@ -1589,8 +1589,8 @@ module mgxs_header select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsAngle) if (order /= size(nuc % scatter(1,1) % obj % dist(1) % data, dim=1)) & - call fatal_error("All Histogram Scattering Entries Must Be& - & Same Length!") + call fatal_error("All histogram scattering entries must be& + & same length!") end select end do ! Ok, got our order, store the dimensionality @@ -1609,9 +1609,9 @@ module mgxs_header do i = 2, mat % n_nuclides select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsAngle) - if (order /= size(nuc % scatter(1, 1) % obj % dist(1) % data,dim=1)) & - call fatal_error("All Tabular Scattering Entries Must Be& - & Same Length!") + if (order /= size(nuc % scatter(1, 1) % obj % dist(1) % data, dim=1)) & + call fatal_error("All tabular scattering entries must be& + & same length!") end select end do ! Ok, got our order, store the dimensionality @@ -1653,25 +1653,25 @@ module mgxs_header ! Allocate and initialize data within macro_xs(i_mat) object allocate(this % total(groups, n_azi, n_pol)) - this % total = ZERO + this % total(:, :, :) = ZERO allocate(this % absorption(groups, n_azi, n_pol)) - this % absorption = ZERO + this % absorption(:, :, :) = ZERO allocate(this % fission(groups, n_azi, n_pol)) - this % fission = ZERO + this % fission(:, :, :) = ZERO allocate(this % k_fission(groups, n_azi, n_pol)) - this % k_fission = ZERO + this % k_fission(:, :, :) = ZERO allocate(this % nu_fission(groups, n_azi, n_pol)) - this % nu_fission = ZERO + this % nu_fission(:, :, :) = ZERO allocate(this % chi(groups, groups, n_azi, n_pol)) - this % chi = ZERO + this % chi(:, :, :, :) = ZERO allocate(temp_mult(groups, groups, n_azi, n_pol)) - temp_mult = ZERO + temp_mult(:, :, :, :) = ZERO allocate(mult_num(groups, groups, n_azi, n_pol)) - mult_num = ZERO + mult_num(:, :, :, :) = ZERO allocate(mult_denom(groups, groups, n_azi, n_pol)) - mult_denom = ZERO + mult_denom(:, :, :, :) = ZERO allocate(scatt_coeffs(order_dim, groups, groups, n_azi, n_pol)) - scatt_coeffs = ZERO + scatt_coeffs(:, :, :, :, :) = ZERO ! Add contribution from each nuclide in material do i = 1, mat % n_nuclides @@ -1681,22 +1681,24 @@ module mgxs_header ! Perform our operations which depend upon the type select type(nuc => nuclides(mat % nuclide(i)) % obj) type is (MgxsIso) - call fatal_error("Invalid Passing of MgxsIso to MgxsAngle Object") + call fatal_error("Invalid passing of MgxsIso to MgxsAngle object") type is (MgxsAngle) ! Add contributions to total, absorption, and fission data (if necessary) - this % total = this % total + atom_density * nuc % total - this % absorption = this % absorption + & - atom_density * nuc % absorption + this % total(:, :, :) = this % total(:, :, :) + & + atom_density * nuc % total(:, :, :) + this % absorption(:, :, :) = this % absorption(:, :, :) + & + atom_density * nuc % absorption(:, :, :) if (nuc % fissionable) then this % chi = this % chi + atom_density * nuc % chi - this % nu_fission = this % nu_fission + atom_density * & - nuc % nu_fission + this % nu_fission(:, :, :) = this % nu_fission(:, :, :) + & + atom_density * nuc % nu_fission(:, :, :) if (allocated(nuc % fission)) then - this % fission = this % fission + atom_density * nuc % fission + this % fission(:, :, :) = this % fission(:, :, :) + & + atom_density * nuc % fission(:, :, :) end if if (allocated(nuc % k_fission)) then - this % k_fission = this % k_fission + atom_density * & - nuc % k_fission + this % k_fission(:, :, :) = this % k_fission(:, :, :) + & + atom_density * nuc % k_fission(:, :, :) end if end if @@ -1730,7 +1732,7 @@ module mgxs_header end do ! Get the complete scattering matrix - nuc_order_dim = size(nuc % scatter(1,1) % obj % dist(1) % data,dim=1) + nuc_order_dim = size(nuc % scatter(1, 1) % obj % dist(1) % data, dim=1) do ipol = 1, n_pol do iazi = 1, n_azi scatt_coeffs(1:min(nuc_order_dim, order_dim), :, :, iazi, ipol) = & diff --git a/src/scattdata_header.F90 b/src/scattdata_header.F90 index f36fe6043..12c11e2e4 100644 --- a/src/scattdata_header.F90 +++ b/src/scattdata_header.F90 @@ -14,7 +14,7 @@ module scattdata_header !=============================================================================== type :: Jagged2D - real(8), allocatable :: data(:,:) + real(8), allocatable :: data(:, :) end type Jagged2D type :: Jagged1D @@ -27,12 +27,15 @@ module scattdata_header !=============================================================================== type, abstract :: ScattData - ! normalized p0 matrix on its own for sampling energy + ! The data attribute of the energy, mult, and dist arrays + ! are not necessarily 1-indexed as they instead will be allocated + ! from a minimum outgoing group to an outgoing minimum group. + ! Normalized p0 matrix on its own for sampling energy type(Jagged1D), allocatable :: energy(:) ! (Gin % data(Gout)) - ! nu-scatter multiplication (i.e. nu-scatt/scatt) + ! Nu-scatter multiplication (i.e. nu-scatt/scatt) type(Jagged1D), allocatable :: mult(:) ! (Gin % data(Gout)) ! Angular distribution - type(Jagged2D), allocatable :: dist(:) ! (Gin % data(Order/Nmu x Gout) + type(Jagged2D), allocatable :: dist(:) ! (Gin % data(Order/Nmu, Gout) integer, allocatable :: gmin(:) ! Minimum outgoing group integer, allocatable :: gmax(:) ! Maximum outgoing group real(8), allocatable :: scattxs(:) ! Isotropic Sigma_{s,g_{in}} @@ -47,9 +50,9 @@ module scattdata_header abstract interface subroutine scattdata_init_(this, mult, coeffs) import ScattData - class(ScattData), intent(inout) :: this ! Scattering Object to work with - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + class(ScattData), intent(inout) :: this ! Object to work with + real(8), intent(in) :: mult(:, :) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:, :, :) ! Coefficients to use end subroutine scattdata_init_ pure function scattdata_calc_f_(this, gin, gout, mu) result(f) @@ -120,10 +123,10 @@ contains !=============================================================================== subroutine scattdata_init(this, order, energy, mult) - class(ScattData), intent(inout) :: this ! Object to work on - integer, intent(in) :: order ! Data Order - real(8), intent(inout) :: energy(:,:) ! Energy Transfer Matrix - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix + class(ScattData), intent(inout) :: this ! Object to work on + integer, intent(in) :: order ! Data Order + real(8), intent(inout) :: energy(:, :) ! Energy Transfer Matrix + real(8), intent(in) :: mult(:, :) ! Scatter Prod'n Matrix integer :: groups, gmin, gmax, gin real(8) :: norm @@ -139,15 +142,15 @@ contains ! Also set energy values when doing it do gin = 1, groups ! Make sure energy is normalized (i.e., CDF is 1) - norm = sum(energy(:,gin)) - if (norm /= ZERO) energy(:,gin) = energy(:,gin) / norm + norm = sum(energy(:, gin)) + if (norm /= ZERO) energy(:, gin) = energy(:, gin) / norm ! Find gmin by checking the P0 moment do gmin = 1, groups - if (energy(gmin,gin) > ZERO) exit + if (energy(gmin, gin) > ZERO) exit end do ! Find gmax by checking the P0 moment do gmax = groups, 1, -1 - if (energy(gmax,gin) > ZERO) exit + if (energy(gmax, gin) > ZERO) exit end do ! Treat the case of all zeros if (gmin > gmax) then @@ -156,10 +159,10 @@ contains ! By not changing energy(gin) here we are leaving it as zero end if allocate(this % energy(gin) % data(gmin:gmax)) - this % energy(gin) % data(gmin:gmax) = energy(gmin:gmax,gin) + this % energy(gin) % data(gmin:gmax) = energy(gmin:gmax, gin) allocate(this % mult(gin) % data(gmin:gmax)) - this % mult(gin) % data(gmin:gmax) = mult(gmin:gmax,gin) - allocate(this % dist(gin) % data(order,gmin:gmax)) + this % mult(gin) % data(gmin:gmax) = mult(gmin:gmax, gin) + allocate(this % dist(gin) % data(order, gmin:gmax)) this % dist(gin) % data = ZERO this % gmin(gin) = gmin this % gmax(gin) = gmax @@ -167,38 +170,38 @@ contains end subroutine scattdata_init subroutine scattdatalegendre_init(this, mult, coeffs) - class(ScattDataLegendre), intent(inout) :: this ! Object to work on - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + class(ScattDataLegendre), intent(inout) :: this ! Object to work on + real(8), intent(in) :: mult(:, :) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:, :, :) ! Coefficients to use real(8) :: dmu, mu, f, norm integer :: imu, Nmu, gout, gin, groups, order - real(8), allocatable :: energy(:,:) - real(8), allocatable :: matrix(:,:,:) + real(8), allocatable :: energy(:, :) + real(8), allocatable :: matrix(:, :, :) - groups = size(coeffs,dim=3) - order = size(coeffs,dim=1) + groups = size(coeffs, dim=3) + order = size(coeffs, dim=1) ! make a copy of coeffs that we can use to extract data and normalize - allocate(matrix(order,groups,groups)) - matrix = coeffs + allocate(matrix(order, groups, groups)) + matrix (:, :, :)= coeffs ! Get scattxs value allocate(this % scattxs(groups)) ! Get this by summing the un-normalized P0 coefficient in matrix ! over all outgoing groups - this % scattxs = sum(matrix(1,:,:),dim=1) + this % scattxs(:) = sum(matrix(1, :, :), dim=1) - allocate(energy(groups,groups)) - energy = ZERO + allocate(energy(groups, groups)) + energy(:, :) = ZERO ! Build energy transfer probability matrix from data in matrix ! while also normalizing matrix itself (making CDF of f(mu=1)=1) do gin = 1, groups do gout = 1, groups - norm = matrix(1,gout,gin) - energy(gout,gin) = norm + norm = matrix(1, gout, gin) + energy(gout, gin) = norm if (norm /= ZERO) then - matrix(:,gout,gin) = matrix(:,gout,gin) / norm + matrix(:, gout, gin) = matrix(:, gout, gin) / norm end if end do end do @@ -209,16 +212,16 @@ contains ! Set dist values from matrix and initialize max_val do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) - this % dist(gin) % data(:,gout) = matrix(:,gout,gin) + this % dist(gin) % data(:, gout) = matrix(:, gout, gin) end do allocate(this % max_val(gin) % data(this % gmin(gin):this % gmax(gin))) - this % max_val(gin) % data = ZERO + this % max_val(gin) % data(:) = ZERO end do ! Step through the polynomial with fixed number of points to identify ! the maximal value. Nmu = 1001 - dmu = TWO / real(Nmu - 1,8) + dmu = TWO / real(Nmu - 1, 8) do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) do imu = 1, Nmu @@ -228,7 +231,7 @@ contains else if (imu == Nmu) then mu = ONE else - mu = -ONE + real(imu - 1,8) * dmu + mu = -ONE + real(imu - 1, 8) * dmu end if ! Calculate probability f = this % calc_f(gin,gout,mu) @@ -245,37 +248,37 @@ contains subroutine scattdatahistogram_init(this, mult, coeffs) class(ScattDataHistogram), intent(inout) :: this ! Object to work on - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: mult(:, :) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:, :, :) ! Coefficients to use integer :: imu, gin, gout, groups, order real(8) :: norm - real(8), allocatable :: energy(:,:) - real(8), allocatable :: matrix(:,:,:) + real(8), allocatable :: energy(:, :) + real(8), allocatable :: matrix(:, :, :) - groups = size(coeffs,dim=3) - order = size(coeffs,dim=1) + groups = size(coeffs, dim=3) + order = size(coeffs, dim=1) ! make a copy of coeffs that we can use to extract data and normalize - allocate(matrix(order,groups,groups)) - matrix = coeffs + allocate(matrix(order, groups, groups)) + matrix(:, :, :) = coeffs ! Get scattxs value allocate(this % scattxs(groups)) ! Get this by summing the un-normalized P0 coefficient in matrix ! over all outgoing groups - this % scattxs = sum(sum(matrix(:,:,:),dim=1),dim=1) + this % scattxs(:) = sum(sum(matrix(:, :, :), dim=1), dim=1) - allocate(energy(groups,groups)) - energy = ZERO + allocate(energy(groups, groups)) + energy(:, :) = ZERO ! Build energy transfer probability matrix from data in matrix ! while also normalizing matrix itself (making CDF of f(mu=1)=1) do gin = 1, groups do gout = 1, groups - norm = sum(matrix(:,gout,gin)) - energy(gout,gin) = norm + norm = sum(matrix(:, gout, gin)) + energy(gout, gin) = norm if (norm /= ZERO) then - matrix(:,gout,gin) = matrix(:,gout,gin) / norm + matrix(:, gout, gin) = matrix(:, gout, gin) / norm end if end do end do @@ -283,10 +286,10 @@ contains call scattdata_init(this, order, energy, mult) allocate(this % mu(order)) - this % dmu = TWO / real(order,8) + this % dmu = TWO / real(order, 8) this % mu(1) = -ONE do imu = 2, order - this % mu(imu) = -ONE + real(imu - 1,8) * this % dmu + this % mu(imu) = -ONE + real(imu - 1, 8) * this % dmu end do ! Integrate this histogram so we can avoid rejection sampling while @@ -297,21 +300,23 @@ contains this % gmin(gin):this % gmax(gin))) do gout = this % gmin(gin), this % gmax(gin) ! Store the histogram - this % fmu(gin) % data(:,gout) = matrix(:,gout,gin) + this % fmu(gin) % data(:, gout) = matrix(:, gout, gin) ! Integrate the histogram - this % dist(gin) % data(1,gout) = this % dmu * matrix(1,gout,gin) + this % dist(gin) % data(1, gout) = & + this % dmu * matrix(1, gout, gin) do imu = 2, order - this % dist(gin) % data(imu,gout) = this % dmu * matrix(imu,gout,gin) + & - this % dist(gin) % data(imu - 1,gout) + this % dist(gin) % data(imu, gout) = & + this % dmu * matrix(imu, gout, gin) + & + this % dist(gin) % data(imu - 1, gout) end do ! Now make sure integral norms to zero - norm = this % dist(gin) % data(order,gout) + norm = this % dist(gin) % data(order, gout) if (norm > ZERO) then - this % fmu(gin) % data(:,gout) = & - this % fmu(gin) % data(:,gout) / norm - this % dist(gin) % data(:,gout) = & - this % dist(gin) % data(:,gout) / norm + this % fmu(gin) % data(:, gout) = & + this % fmu(gin) % data(:, gout) / norm + this % dist(gin) % data(:, gout) = & + this % dist(gin) % data(:, gout) / norm end if end do end do @@ -320,27 +325,27 @@ contains subroutine scattdatatabular_init(this, mult, coeffs) class(ScattDataTabular), intent(inout) :: this ! Object to work on - real(8), intent(in) :: mult(:,:) ! Scatter Prod'n Matrix - real(8), intent(in) :: coeffs(:,:,:) ! Coefficients to use + real(8), intent(in) :: mult(:, :) ! Scatter Prod'n Matrix + real(8), intent(in) :: coeffs(:, :, :) ! Coefficients to use integer :: imu, gin, gout, groups, order real(8) :: norm - real(8), allocatable :: energy(:,:) - real(8), allocatable :: matrix(:,:,:) + real(8), allocatable :: energy(:, :) + real(8), allocatable :: matrix(:, :, :) - groups = size(coeffs,dim=3) - order = size(coeffs,dim=1) + groups = size(coeffs, dim=3) + order = size(coeffs, dim=1) ! make a copy of coeffs that we can use to extract data and normalize - allocate(matrix(order,groups,groups)) - matrix = coeffs + allocate(matrix(order, groups, groups)) + matrix(:, :, :) = coeffs ! Build the angular distribution mu values allocate(this % mu(order)) - this % dmu = TWO / real(order - 1,8) + this % dmu = TWO / real(order - 1, 8) this % mu(1) = -ONE do imu = 2, order - 1 - this % mu(imu) = -ONE + real(imu - 1,8) * this % dmu + this % mu(imu) = -ONE + real(imu - 1, 8) * this % dmu end do this % mu(order) = ONE @@ -353,24 +358,24 @@ contains norm = ZERO do gout = 1, groups do imu = 2, order - norm = norm + HALF * this % dmu * (matrix(imu - 1,gout,gin) + & - matrix(imu,gout,gin)) + norm = norm + HALF * this % dmu * (matrix(imu - 1, gout, gin) + & + matrix(imu, gout, gin)) end do end do this % scattxs(gin) = norm end do - allocate(energy(groups,groups)) - energy = ZERO + allocate(energy(groups, groups)) + energy(:, :) = ZERO ! Build energy transfer probability matrix from data in matrix do gin = 1, groups do gout = 1, groups norm = ZERO do imu = 2, order norm = norm + HALF * this % dmu * & - (matrix(imu - 1,gout,gin) + matrix(imu,gout,gin)) + (matrix(imu - 1, gout, gin) + matrix(imu, gout, gin)) end do - energy(gout,gin) = norm + energy(gout, gin) = norm end do end do call scattdata_init(this, order, energy, mult) @@ -383,12 +388,12 @@ contains do gout = this % gmin(gin), this % gmax(gin) ! Coeffs contain f(mu), put in f(mu) as that is where the ! PDF lives - this % fmu(gin) % data(:,gout) = matrix(:,gout,gin) + this % fmu(gin) % data(:, gout) = matrix(:, gout, gin) ! Force positivity do imu = 1, order - if (this % fmu(gin) % data(imu,gout) < ZERO) then - this % fmu(gin) % data(imu,gout) = ZERO + if (this % fmu(gin) % data(imu, gout) < ZERO) then + this % fmu(gin) % data(imu, gout) = ZERO end if end do @@ -397,27 +402,27 @@ contains norm = ZERO do imu = 2, order norm = norm + HALF * this % dmu * & - (this % fmu(gin) % data(imu - 1,gout) + & - this % fmu(gin) % data(imu,gout)) + (this % fmu(gin) % data(imu - 1, gout) + & + this % fmu(gin) % data(imu, gout)) end do if (norm > ZERO) then - this % fmu(gin) % data(:,gout) = & - this % fmu(gin) % data(:,gout) / norm + this % fmu(gin) % data(:, gout) = & + this % fmu(gin) % data(:, gout) / norm end if ! Now create CDF from fmu with trapezoidal rule - this % dist(gin) % data(1,gout) = ZERO + this % dist(gin) % data(1, gout) = ZERO do imu = 2, order - this % dist(gin) % data(imu,gout) = & - this % dist(gin) % data(imu - 1,gout) + & - HALF * this % dmu * (this % fmu(gin) % data(imu - 1,gout) + & - this % fmu(gin) % data(imu,gout)) + this % dist(gin) % data(imu, gout) = & + this % dist(gin) % data(imu - 1, gout) + & + HALF * this % dmu * (this % fmu(gin) % data(imu - 1, gout) + & + this % fmu(gin) % data(imu, gout)) end do ! Ensure we normalize to 1 still - norm = this % dist(gin) % data(order,gout) + norm = this % dist(gin) % data(order, gout) if (norm > ZERO) then - this % dist(gin) % data(:,gout) = & - this % dist(gin) % data(:,gout) / norm + this % dist(gin) % data(:, gout) = & + this % dist(gin) % data(:, gout) / norm end if end do end do @@ -438,7 +443,7 @@ contains if (gout < this % gmin(gin) .or. gout > this % gmax(gin)) then f = ZERO else - f = evaluate_legendre(this % dist(gin) % data(:,gout),mu) + f = evaluate_legendre(this % dist(gin) % data(:, gout), mu) end if end function scattdatalegendre_calc_f @@ -457,12 +462,12 @@ contains else ! Find mu bin if (mu == ONE) then - imu = size(this % fmu(gin) % data,dim=1) + imu = size(this % fmu(gin) % data, dim=1) else - imu = floor((mu + ONE)/ this % dmu + ONE) + imu = floor((mu + ONE) / this % dmu + ONE) end if - f = this % fmu(gin) % data(imu,gout) + f = this % fmu(gin) % data(imu, gout) end if end function scattdatahistogram_calc_f @@ -482,15 +487,15 @@ contains else ! Find mu bin if (mu == ONE) then - imu = size(this % fmu(gin) % data,dim=1) - 1 + imu = size(this % fmu(gin) % data, dim=1) - 1 else - imu = floor((mu + ONE)/ this % dmu + ONE) + imu = floor((mu + ONE) / this % dmu + ONE) end if ! Now interpolate to find f(mu) r = (mu - this % mu(imu)) / (this % mu(imu + 1) - this % mu(imu)) - f = (ONE - r) * this % fmu(gin) % data(imu,gout) + & - r * this % fmu(gin) % data(imu + 1,gout) + f = (ONE - r) * this % fmu(gin) % data(imu, gout) + & + r * this % fmu(gin) % data(imu + 1, gout) end if end function scattdatatabular_calc_f @@ -529,7 +534,7 @@ contains samples = 0 do mu = TWO * prn() - ONE - f = this % calc_f(gin,gout,mu) + f = this % calc_f(gin, gout, mu) if (f > ZERO) then u = prn() * M if (u <= f) then @@ -567,11 +572,11 @@ contains end do xi = prn() - if (xi < this % dist(gin) % data(1,gout)) then + if (xi < this % dist(gin) % data(1, gout)) then imu = 1 else - imu = binary_search(this % dist(gin) % data(:,gout), & - size(this % dist(gin) % data(:,gout)), xi) + imu = binary_search(this % dist(gin) % data(:, gout), & + size(this % dist(gin) % data(:, gout)), xi) end if ! Randomly select a mu in this bin. @@ -604,12 +609,12 @@ contains end do ! determine outgoing cosine bin - NP = size(this % dist(gin) % data(:,gout)) + NP = size(this % dist(gin) % data(:, gout)) xi = prn() - c_k = this % dist(gin) % data(1,gout) + c_k = this % dist(gin) % data(1, gout) do k = 1, NP - 1 - c_k1 = this % dist(gin) % data(k + 1,gout) + c_k1 = this % dist(gin) % data(k + 1, gout) if (xi < c_k1) exit c_k = c_k1 end do @@ -617,18 +622,19 @@ contains ! check to make sure k is <= NP - 1 k = min(k, NP - 1) - p0 = this % fmu(gin) % data(k,gout) + p0 = this % fmu(gin) % data(k, gout) mu0 = this % mu(k) ! Linear-linear interpolation to find mu value w/in bin. - p1 = this % fmu(gin) % data(k + 1,gout) + p1 = this % fmu(gin) % data(k + 1, gout) mu1 = this % mu(k + 1) - frac = (p1 - p0)/(mu1 - mu0) + frac = (p1 - p0) / (mu1 - mu0) if (frac == ZERO) then - mu = mu0 + (xi - c_k)/p0 + mu = mu0 + (xi - c_k) / p0 else - mu = mu0 + (sqrt(max(ZERO, p0 * p0 + TWO * frac * (xi - c_k))) - p0) / frac + mu = mu0 + & + (sqrt(max(ZERO, p0 * p0 + TWO * frac * (xi - c_k))) - p0) / frac end if if (mu <= -ONE) then @@ -649,23 +655,24 @@ contains pure function scattdata_get_matrix(this, req_order) result(matrix) class(ScattData), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: req_order ! Requested order of matrix - real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + real(8), allocatable :: matrix(:, :, :) ! Resultant matrix just built integer :: order, groups, gin, gout groups = size(this % energy) - order = min(req_order,size(this % dist(1) % data(:,1))) + ! Set gin and gout for getting the order + order = min(req_order, size(this % dist(1) % data, dim=1)) - allocate(matrix(order,groups,groups)) + allocate(matrix(order, groups, groups)) ! Initialize to 0; this way the zero entries in the dense matrix dont ! need to be explicitly set, requiring a significant increase in the ! lines of code. - matrix = ZERO + matrix(:, :, :) = ZERO do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) - matrix(:,gout,gin) = this % scattxs(gin) * & + matrix(:, gout, gin) = this % scattxs(gin) * & this % energy(gin) % data(gout) * & - this % dist(gin) % data(1:order,gout) + this % dist(gin) % data(1:order, gout) end do end do end function scattdata_get_matrix @@ -673,23 +680,23 @@ contains pure function scattdatahistogram_get_matrix(this, req_order) result(matrix) class(ScattDataHistogram), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: req_order ! Requested order of matrix - real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + real(8), allocatable :: matrix(:, :, :) ! Resultant matrix just built integer :: order, groups, gin, gout groups = size(this % energy) - order = min(req_order,size(this % dist(1) % data(:,1))) + order = min(req_order, size(this % dist(1) % data, dim=1)) - allocate(matrix(order,groups,groups)) + allocate(matrix(order, groups, groups)) ! Initialize to 0; this way the zero entries in the dense matrix dont ! need to be explicitly set, requiring a significant increase in the ! lines of code. - matrix = ZERO + matrix(:, :, :) = ZERO do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) - matrix(:,gout,gin) = this % scattxs(gin) * & + matrix(:, gout, gin) = this % scattxs(gin) * & this % energy(gin) % data(gout) * & - this % fmu(gin) % data(1:order,gout) + this % fmu(gin) % data(1:order, gout) end do end do end function scattdatahistogram_get_matrix @@ -697,23 +704,23 @@ contains pure function scattdatatabular_get_matrix(this, req_order) result(matrix) class(ScattDataTabular), intent(in) :: this ! Scattering Object to work with integer, intent(in) :: req_order ! Requested order of matrix - real(8), allocatable :: matrix(:,:,:) ! Resultant matrix just built + real(8), allocatable :: matrix(:, :, :) ! Resultant matrix just built integer :: order, groups, gin, gout groups = size(this % energy) - order = min(req_order,size(this % dist(1) % data(:,1))) + order = min(req_order, size(this % dist(1) % data, dim=1)) - allocate(matrix(order,groups,groups)) + allocate(matrix(order, groups, groups)) ! Initialize to 0; this way the zero entries in the dense matrix dont ! need to be explicitly set, requiring a significant increase in the ! lines of code. - matrix = ZERO + matrix(:, :, :) = ZERO do gin = 1, groups do gout = this % gmin(gin), this % gmax(gin) - matrix(:,gout,gin) = this % scattxs(gin) * & + matrix(:, gout, gin) = this % scattxs(gin) * & this % energy(gin) % data(gout) * & - this % fmu(gin) % data(1:order,gout) + this % fmu(gin) % data(1:order, gout) end do end do end function scattdatatabular_get_matrix diff --git a/src/tally.F90 b/src/tally.F90 index 86e108c3d..c4eaf30c8 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -961,9 +961,9 @@ contains if (i_nuclide > 0) then score = score * atom_density * & nucxs % get_xs('scatter*f_mu/mult', p % last_g, p % g, & - UVW=p_uvw,MU=p % mu) / & + UVW=p_uvw, MU=p % mu) / & matxs % get_xs('scatter*f_mu/mult', p % last_g, p % g, & - UVW=p_uvw,MU=p % mu) + UVW=p_uvw, MU=p % mu) end if else @@ -1080,11 +1080,11 @@ contains end if if (i_nuclide > 0) then score = score * atom_density * & - nucxs % get_xs('fission', p_g, UVW=p_uvw) / & + nucxs % get_xs('fission', p_g, UVW=p_uvw) / & matxs % get_xs('absorption', p_g, UVW=p_uvw) else score = score * & - matxs % get_xs('fission', p_g, UVW=p_uvw) / & + matxs % get_xs('fission', p_g, UVW=p_uvw) / & matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else @@ -1170,11 +1170,11 @@ contains if (i_nuclide > 0) then score = score * atom_density * & nucxs % get_xs('kappa_fission', p_g, UVW=p_uvw) / & - matxs % get_xs('absorption', p_g, UVW=p_uvw) + matxs % get_xs('absorption', p_g, UVW=p_uvw) else score = score * & matxs % get_xs('kappa_fission', p_g, UVW=p_uvw) / & - matxs % get_xs('absorption', p_g, UVW=p_uvw) + matxs % get_xs('absorption', p_g, UVW=p_uvw) end if else if (i_nuclide > 0) then From 8e4422ae1fb24355b4298bdf57e5a92ff5094b65 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 10:36:43 -0500 Subject: [PATCH 106/147] Add HexLattice.show_indices staticmethod and clarify universes description --- openmc/lattice.py | 125 +++++++++++++++++++++++++++++++++++++++++++--- 1 file changed, 118 insertions(+), 7 deletions(-) diff --git a/openmc/lattice.py b/openmc/lattice.py index f78ec8e90..af6c14a6a 100644 --- a/openmc/lattice.py +++ b/openmc/lattice.py @@ -30,8 +30,8 @@ class Lattice(object): Unique identifier for the lattice name : str Name of the lattice - pitch : float - Pitch of the lattice in cm + pitch : Iterable of float + Pitch of the lattice in each direction in cm outer : openmc.Universe A universe to fill all space outside the lattice universes : Iterable of Iterable of openmc.Universe @@ -259,8 +259,9 @@ class RectLattice(Lattice): lower_left : Iterable of float The coordinates of the lower-left corner of the lattice. If the lattice is two-dimensional, only the x- and y-coordinates are specified. - pitch : float - Pitch of the lattice in cm + pitch : Iterable of float + Pitch of the lattice in the x, y, and (if applicable) z directions in + cm. outer : openmc.Universe A universe to fill all space outside the lattice universes : Iterable of Iterable of openmc.Universe @@ -512,13 +513,19 @@ class HexLattice(Lattice): center : Iterable of float Coordinates of the center of the lattice. If the lattice does not have axial sections then only the x- and y-coordinates are specified - pitch : float - Pitch of the lattice in cm + pitch : Iterable of float + Pitch of the lattice in cm. The first item in the iterable specifies the + pitch in the radial direction and, if the lattice is 3D, the second item + in the iterable specifies the pitch in the axial direction. outer : openmc.Universe A universe to fill all space outside the lattice universes : Iterable of Iterable of openmc.Universe A two- or three-dimensional list/array of universes filling each element - of the lattice + of the lattice. Each sub-list corresponds to one ring of universes and + should be ordered from outermost ring to innermost ring. The universes + within each sub-list are ordered from the "top" and proceed in a + clockwise fashion. The :meth:`HexLattice.show_indices` method can be + used to help figure out indices for this property. """ @@ -882,3 +889,107 @@ class HexLattice(Lattice): # Join the rows together and return the string. universe_ids = '\n'.join(rows) return universe_ids + + @staticmethod + def show_indices(num_rings): + """Return a diagram of the hexagonal lattice layout with indices. + + This method can be used to show the proper indices to be used when + setting the :attr:`HexLattice.universes` property. For example, running + this method with num_rings=3 will return the following diagram:: + + (0, 0) + (0,11) (0, 1) + (0,10) (1, 0) (0, 2) + (1, 5) (1, 1) + (0, 9) (2, 0) (0, 3) + (1, 4) (1, 2) + (0, 8) (1, 3) (0, 4) + (0, 7) (0, 5) + (0, 6) + + Parameters + ---------- + num_rings : int + Number of rings in the hexagonal lattice + + Returns + ------- + str + Diagram of the hexagonal lattice showing indices + + """ + + # Find the largest string and count the number of digits so we can + # properly pad the output string later + largest_index = 6*(num_rings - 1) + n_digits_index = len(str(largest_index)) + n_digits_ring = len(str(num_rings - 1)) + str_form = '({{:{}}},{{:{}}})'.format(n_digits_ring, n_digits_index) + pad = ' '*(n_digits_index + n_digits_ring + 3) + + # Initialize the list for each row. + rows = [[] for i in range(1 + 4 * (num_rings-1))] + middle = 2 * (num_rings - 1) + + # Start with the degenerate first ring. + rows[middle] = [str_form.format(num_rings - 1, 0)] + + # Add universes one ring at a time. + for r in range(1, num_rings): + # r_prime increments down while r increments up. + r_prime = num_rings - 1 - r + theta = 0 + y = middle + 2*r + + for i in range(r): + # Climb down the top-right. + rows[y].append(str_form.format(r_prime, theta)) + y -= 1 + theta += 1 + + for i in range(r): + # Climb down the right. + rows[y].append(str_form.format(r_prime, theta)) + y -= 2 + theta += 1 + + for i in range(r): + # Climb down the bottom-right. + rows[y].append(str_form.format(r_prime, theta)) + y -= 1 + theta += 1 + + for i in range(r): + # Climb up the bottom-left. + rows[y].insert(0, str_form.format(r_prime, theta)) + y += 1 + theta += 1 + + for i in range(r): + # Climb up the left. + rows[y].insert(0, str_form.format(r_prime, theta)) + y += 2 + theta += 1 + + for i in range(r): + # Climb up the top-left. + rows[y].insert(0, str_form.format(r_prime, theta)) + y += 1 + theta += 1 + + # Flip the rows and join each row into a single string. + rows = [pad.join(x) for x in rows[::-1]] + + # Pad the beginning of the rows so they line up properly. + for y in range(num_rings - 1): + rows[y] = (num_rings - 1 - y)*pad + rows[y] + rows[-1 - y] = (num_rings - 1 - y)*pad + rows[-1 - y] + + for y in range(num_rings % 2, num_rings, 2): + rows[middle + y] = pad + rows[middle + y] + if y != 0: + rows[middle - y] = pad + rows[middle - y] + + # Join the rows together and return the string. + return '\n'.join(rows) From 17c96c497c33fd19309d4ec1f7dee52d7bd83b3a Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 10:37:07 -0500 Subject: [PATCH 107/147] Add xyz default for openmc.stats.Point constructor --- openmc/stats/multivariate.py | 6 +++--- 1 file changed, 3 insertions(+), 3 deletions(-) diff --git a/openmc/stats/multivariate.py b/openmc/stats/multivariate.py index 4ce34a071..e4eadd7aa 100644 --- a/openmc/stats/multivariate.py +++ b/openmc/stats/multivariate.py @@ -328,8 +328,8 @@ class Point(Spatial): Parameters ---------- - xyz : Iterable of float - Cartesian coordinates of location + xyz : Iterable of float, optional + Cartesian coordinates of location. Defaults to (0., 0., 0.). Attributes ---------- @@ -338,7 +338,7 @@ class Point(Spatial): """ - def __init__(self, xyz): + def __init__(self, xyz=(0., 0., 0.)): super(Point, self).__init__() self.xyz = xyz From 8ff23e9f9808a0efbf990be4bb2355dd111f2220 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 10:37:40 -0500 Subject: [PATCH 108/147] Clarify documentation regarding cell rotation --- docs/source/usersguide/input.rst | 14 ++++++++++++++ openmc/cell.py | 21 +++++++++++++++++---- 2 files changed, 31 insertions(+), 4 deletions(-) diff --git a/docs/source/usersguide/input.rst b/docs/source/usersguide/input.rst index 775407d70..8493ac480 100644 --- a/docs/source/usersguide/input.rst +++ b/docs/source/usersguide/input.rst @@ -1033,6 +1033,20 @@ Each ```` element can have the following attributes or sub-elements: + The rotation applied is an intrinsic rotation whose Tait-Bryan angles are + given as those specified about the x, y, and z axes respectively. That is to + say, if the angles are :math:`(\phi, \theta, \psi)`, then the rotation + matrix applied is :math:`R_z(\psi) R_y(\theta) R_x(\phi)` or + + .. math:: + + \left [ \begin{array}{ccc} \cos\theta \cos\psi & -\cos\theta \sin\psi + + \sin\phi \sin\theta \cos\psi & \sin\phi \sin\psi + \cos\phi \sin\theta + \cos\psi \\ \cos\theta \sin\psi & \cos\phi \cos\psi + \sin\phi \sin\theta + \sin\psi & -\sin\phi \cos\psi + \cos\phi \sin\theta \sin\psi \\ + -\sin\theta & \sin\phi \cos\theta & \cos\phi \cos\theta \end{array} + \right ] + *Default*: None :translation: diff --git a/openmc/cell.py b/openmc/cell.py index 37828d8fc..806f3f32f 100644 --- a/openmc/cell.py +++ b/openmc/cell.py @@ -23,7 +23,7 @@ def reset_auto_cell_id(): class Cell(object): - """A region of space defined as the intersection of half-space created by + r"""A region of space defined as the intersection of half-space created by quadric surfaces. Parameters @@ -48,11 +48,24 @@ class Cell(object): Indicates what the region of space is filled with region : openmc.Region Region of space that is assigned to the cell. - rotation : numpy.ndarray + rotation : Iterable of float If the cell is filled with a universe, this array specifies the angles in degrees about the x, y, and z axes that the filled universe should be - rotated. - translation : numpy.ndarray + rotated. The rotation applied is an intrinsic rotation with specified + Tait-Bryan angles. That is to say, if the angles are :math:`(\phi, + \theta, \psi)`, then the rotation matrix applied is :math:`R_z(\psi) + R_y(\theta) R_x(\phi)` or + + .. math:: + + \left [ \begin{array}{ccc} \cos\theta \cos\psi & -\cos\theta \sin\psi + + \sin\phi \sin\theta \cos\psi & \sin\phi \sin\psi + \cos\phi + \sin\theta \cos\psi \\ \cos\theta \sin\psi & \cos\phi \cos\psi + + \sin\phi \sin\theta \sin\psi & -\sin\phi \cos\psi + \cos\phi + \sin\theta \sin\psi \\ -\sin\theta & \sin\phi \cos\theta & \cos\phi + \cos\theta \end{array} \right ] + + translation : Iterable of float If the cell is filled with a universe, this array specifies a vector that is used to translate (shift) the universe. offsets : ndarray From 962d592d2e262206dcde01207100e14cf26a91b0 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 11:21:48 -0500 Subject: [PATCH 109/147] Restrict the Cell.rotation property to cells filled with a Universe --- openmc/cell.py | 4 ++++ 1 file changed, 4 insertions(+) diff --git a/openmc/cell.py b/openmc/cell.py index 806f3f32f..8ddae6371 100644 --- a/openmc/cell.py +++ b/openmc/cell.py @@ -243,6 +243,10 @@ class Cell(object): @rotation.setter def rotation(self, rotation): + if not isinstance(self.fill, openmc.Universe): + raise RuntimeError('Cell rotation can only be applied if the cell ' + 'is filled with a Universe') + cv.check_type('cell rotation', rotation, Iterable, Real) cv.check_length('cell rotation', rotation, 3) self._rotation = rotation From 10f498177e5528001b9e4b8a3c93b4ad0c5533d3 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 11:55:38 -0500 Subject: [PATCH 110/147] Allow rotation to be set without fill assigned when reading summary file --- openmc/summary.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/summary.py b/openmc/summary.py index 34c51bc51..c9aa08f15 100644 --- a/openmc/summary.py +++ b/openmc/summary.py @@ -267,7 +267,7 @@ class Summary(object): rotation = \ self._f['geometry/cells'][key]['rotation'][...] rotation = np.asarray(rotation, dtype=np.int) - cell.rotation = rotation + cell._rotation = rotation # Store Cell fill information for after Universe/Lattice creation self._cell_fills[index] = (fill_type, fill) From 03828594fbceaa4f00edc144d5d4bb39608033d8 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Tue, 10 May 2016 21:04:00 -0400 Subject: [PATCH 111/147] Reverted to dropping scores from MGXS Pandas DF --- .../pythonapi/examples/mgxs-part-i.ipynb | 35 +- .../pythonapi/examples/mgxs-part-iii.ipynb | 78 +- openmc/mgxs/mgxs.py | 15 +- .../results_true.dat | 98 +- .../results_true.dat | 10 +- .../results_true.dat | 242 +- .../results_true.dat | 3942 ++++++++--------- 7 files changed, 2212 insertions(+), 2208 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index a97a0c02e..e4c976718 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -508,10 +508,11 @@ " 888\n", "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", - " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n", - " Date/Time: 2016-05-05 13:43:54\n", + " Git SHA1: 502482dcf630ee6e290c15b8535e6e850a351c88\n", + " Date/Time: 2016-05-10 20:52:19\n", + " MPI Processes: 1\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -596,20 +597,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.7300E-01 seconds\n", - " Reading cross sections = 1.7600E-01 seconds\n", - " Total time in simulation = 2.1188E+01 seconds\n", - " Time in transport only = 2.1173E+01 seconds\n", - " Time in inactive batches = 2.6880E+00 seconds\n", - " Time in active batches = 1.8500E+01 seconds\n", - " Time synchronizing fission bank = 3.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", + " Total time for initialization = 5.3200E-01 seconds\n", + " Reading cross sections = 1.3300E-01 seconds\n", + " Total time in simulation = 2.3438E+01 seconds\n", + " Time in transport only = 2.3419E+01 seconds\n", + " Time in inactive batches = 2.9490E+00 seconds\n", + " Time in active batches = 2.0489E+01 seconds\n", + " Time synchronizing fission bank = 6.0000E-03 seconds\n", + " Sampling source sites = 3.0000E-03 seconds\n", " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.1776E+01 seconds\n", - " Calculation Rate (inactive) = 9300.60 neutrons/second\n", - " Calculation Rate (active) = 5405.41 neutrons/second\n", + " Total time elapsed = 2.3985E+01 seconds\n", + " Calculation Rate (inactive) = 8477.45 neutrons/second\n", + " Calculation Rate (active) = 4880.67 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1120,7 +1121,7 @@ " 6.250000e-07\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1.0\n", + " 1\n", " 0.007763\n", " \n", " \n", @@ -1130,7 +1131,7 @@ " 2.000000e+01\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1.0\n", + " 1\n", " 0.003739\n", " \n", " \n", @@ -1177,7 +1178,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython2", - "version": "2.7.6" + "version": "2.7.11" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 21aae7e40..b807ab4a9 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -32,7 +32,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", + "/home/wboyd/anaconda2/lib/python2.7/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -725,8 +725,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 7b20f8ad4aa9e6f02f8b1d51e002f9f56ba7aa15\n", - " Date/Time: 2016-05-09 13:39:11\n", + " Git SHA1: 502482dcf630ee6e290c15b8535e6e850a351c88\n", + " Date/Time: 2016-05-10 20:53:35\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -813,20 +813,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.0300E-01 seconds\n", - " Reading cross sections = 1.0400E-01 seconds\n", - " Total time in simulation = 4.8096E+01 seconds\n", - " Time in transport only = 4.8074E+01 seconds\n", - " Time in inactive batches = 4.1080E+00 seconds\n", - " Time in active batches = 4.3988E+01 seconds\n", - " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for initialization = 5.8400E-01 seconds\n", + " Reading cross sections = 1.4100E-01 seconds\n", + " Total time in simulation = 7.7003E+01 seconds\n", + " Time in transport only = 7.6958E+01 seconds\n", + " Time in inactive batches = 6.4820E+00 seconds\n", + " Time in active batches = 7.0521E+01 seconds\n", + " Time synchronizing fission bank = 8.0000E-03 seconds\n", + " Sampling source sites = 6.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", + " Time accumulating tallies = 6.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 4.8613E+01 seconds\n", - " Calculation Rate (inactive) = 6085.69 neutrons/second\n", - " Calculation Rate (active) = 2273.35 neutrons/second\n", + " Total time elapsed = 7.7616E+01 seconds\n", + " Calculation Rate (inactive) = 3856.83 neutrons/second\n", + " Calculation Rate (active) = 1418.02 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -952,7 +952,8 @@ "name": "stderr", "output_type": "stream", "text": [ - "/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n" + "/home/wboyd/Documents/NSE-CRPG-Codes/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", + " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n" ] }, { @@ -966,7 +967,6 @@ " cell\n", " group in\n", " nuclide\n", - " score\n", " mean\n", " std. dev.\n", " \n", @@ -977,7 +977,6 @@ " 10000\n", " 1\n", " U-235\n", - " (nu-fission / flux)\n", " 8.055246e-03\n", " 2.857567e-05\n", " \n", @@ -986,7 +985,6 @@ " 10000\n", " 1\n", " U-238\n", - " (nu-fission / flux)\n", " 7.339215e-03\n", " 4.349466e-05\n", " \n", @@ -995,7 +993,6 @@ " 10000\n", " 1\n", " O-16\n", - " (nu-fission / flux)\n", " 0.000000e+00\n", " 0.000000e+00\n", " \n", @@ -1004,7 +1001,6 @@ " 10000\n", " 2\n", " U-235\n", - " (nu-fission / flux)\n", " 3.615565e-01\n", " 2.050486e-03\n", " \n", @@ -1013,7 +1009,6 @@ " 10000\n", " 2\n", " U-238\n", - " (nu-fission / flux)\n", " 6.742638e-07\n", " 3.795256e-09\n", " \n", @@ -1022,7 +1017,6 @@ " 10000\n", " 2\n", " O-16\n", - " (nu-fission / flux)\n", " 0.000000e+00\n", " 0.000000e+00\n", " \n", @@ -1031,13 +1025,13 @@ "" ], "text/plain": [ - " cell group in nuclide score mean std. dev.\n", - "3 10000 1 U-235 (nu-fission / flux) 8.06e-03 2.86e-05\n", - "4 10000 1 U-238 (nu-fission / flux) 7.34e-03 4.35e-05\n", - "5 10000 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00\n", - "0 10000 2 U-235 (nu-fission / flux) 3.62e-01 2.05e-03\n", - "1 10000 2 U-238 (nu-fission / flux) 6.74e-07 3.80e-09\n", - "2 10000 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00" + " cell group in nuclide mean std. dev.\n", + "3 10000 1 U-235 8.055246e-03 2.857567e-05\n", + "4 10000 1 U-238 7.339215e-03 4.349466e-05\n", + "5 10000 1 O-16 0.000000e+00 0.000000e+00\n", + "0 10000 2 U-235 3.615565e-01 2.050486e-03\n", + "1 10000 2 U-238 6.742638e-07 3.795256e-09\n", + "2 10000 2 O-16 0.000000e+00 0.000000e+00" ] }, "execution_count": 30, @@ -1186,7 +1180,6 @@ " cell\n", " group in\n", " nuclide\n", - " score\n", " mean\n", " std. dev.\n", " \n", @@ -1197,7 +1190,6 @@ " 10000\n", " 1\n", " U-235\n", - " (nu-fission / flux)\n", " 0.074860\n", " 0.000303\n", " \n", @@ -1206,7 +1198,6 @@ " 10000\n", " 1\n", " U-238\n", - " (nu-fission / flux)\n", " 0.005952\n", " 0.000035\n", " \n", @@ -1215,7 +1206,6 @@ " 10000\n", " 1\n", " O-16\n", - " (nu-fission / flux)\n", " 0.000000\n", " 0.000000\n", " \n", @@ -1224,10 +1214,10 @@ "" ], "text/plain": [ - " cell group in nuclide score mean std. dev.\n", - "0 10000 1 U-235 (nu-fission / flux) 7.49e-02 3.03e-04\n", - "1 10000 1 U-238 (nu-fission / flux) 5.95e-03 3.52e-05\n", - "2 10000 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00" + " cell group in nuclide mean std. dev.\n", + "0 10000 1 U-235 0.074860 0.000303\n", + "1 10000 1 U-238 0.005952 0.000035\n", + "2 10000 1 O-16 0.000000 0.000000" ] }, "execution_count": 36, @@ -1568,7 +1558,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 43, @@ -1577,9 +1567,9 @@ }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1619,7 +1609,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython2", - "version": "2.7.6" + "version": "2.7.11" } }, "nbformat": 4, diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 1479f7241..dc3d0d127 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1418,6 +1418,9 @@ class MGXS(object): else: df = self.xs_tally.get_pandas_dataframe(summary=summary) + # Remove the score column since it is homogeneous and redundant + df = df.drop('score', axis=1) + # Override energy groups bounds with indices all_groups = np.arange(self.num_groups, 0, -1, dtype=np.int) all_groups = np.repeat(all_groups, self.num_nuclides) @@ -2228,13 +2231,23 @@ class ScatterMatrixXS(MGXS): df = super(ScatterMatrixXS, self).get_pandas_dataframe( groups, nuclides, xs_type, summary) + # Add a moment column to dataframe + moments = np.array(['P{}'.format(i) for i in range(self.legendre_order+1)]) + moments = np.tile(moments, df.shape[0] / moments.size) + df['moment'] = moments + + # Place the moment column before the mean column + mean_index = df.columns.get_loc('mean') + columns = df.columns.tolist() + df = df[columns[:mean_index] + ['moment'] + columns[mean_index:]] + # Select rows corresponding to requested scattering moment if moment != 'all': cv.check_type('moment', moment, Integral) cv.check_greater_than('moment', moment, 0, equality=True) cv.check_less_than( 'moment', moment, self.legendre_order, equality=True) - df = df[df['score'] == str(self.xs_tally.scores[moment])] + df = df.iloc[moment:self.legendre_order:] return df diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 7e8a49673..2afa47d6f 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,49 +1,49 @@ - material group in nuclide score mean std. dev. -0 1 1 total ((total - scatter-1) / flux) 4.12e-01 2.36e-02 material group in nuclide score mean std. dev. -0 1 1 total (nu-fission / flux) 7.64e-02 3.69e-03 material group in group out nuclide score mean std. dev. -0 1 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.46e-01 2.15e-02 material group out nuclide score mean std. dev. -0 1 1 total nu-fission 1.00e+00 5.53e-02 material group in nuclide score mean std. dev. -0 2 1 total ((total - scatter-1) / flux) 2.41e-01 8.41e-03 material group in nuclide score mean std. dev. -0 2 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 2 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.41e-01 8.41e-03 material group out nuclide score mean std. dev. -0 2 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 3 1 total ((total - scatter-1) / flux) 4.00e-01 3.47e-02 material group in nuclide score mean std. dev. -0 3 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 3 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.93e-01 3.36e-02 material group out nuclide score mean std. dev. -0 3 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 4 1 total ((total - scatter-1) / flux) 3.77e-01 7.29e-02 material group in nuclide score mean std. dev. -0 4 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 4 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.71e-01 7.12e-02 material group out nuclide score mean std. dev. -0 4 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 5 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 5 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 5 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -0 5 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 6 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 6 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 6 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -0 6 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 7 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 7 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 7 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -0 7 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 8 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 8 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 8 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -0 8 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 9 1 total ((total - scatter-1) / flux) 6.01e-01 7.49e-01 material group in nuclide score mean std. dev. -0 9 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 9 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.01e-01 7.49e-01 material group out nuclide score mean std. dev. -0 9 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 10 1 total ((total - scatter-1) / flux) 2.36e-01 6.14e-01 material group in nuclide score mean std. dev. -0 10 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 10 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.36e-01 6.14e-01 material group out nuclide score mean std. dev. -0 10 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 11 1 total ((total - scatter-1) / flux) 5.10e-01 7.42e-01 material group in nuclide score mean std. dev. -0 11 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 11 1 1 total ((nu-scatter-0 - scatter-1) / flux) 4.92e-01 7.16e-01 material group out nuclide score mean std. dev. -0 11 1 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -0 12 1 total ((total - scatter-1) / flux) 7.38e-01 8.26e-01 material group in nuclide score mean std. dev. -0 12 1 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -0 12 1 1 total ((nu-scatter-0 - scatter-1) / flux) 7.23e-01 8.08e-01 material group out nuclide score mean std. dev. -0 12 1 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file + material group in nuclide mean std. dev. +0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. +0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev. moment +0 1 1 1 total P0 0.345643 0.021487 P0 material group out nuclide mean std. dev. +0 1 1 total 1 0.055333 material group in nuclide mean std. dev. +0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. +0 2 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 2 1 1 total P0 0.241262 0.00841 P0 material group out nuclide mean std. dev. +0 2 1 total 0 0 material group in nuclide mean std. dev. +0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. +0 3 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 3 1 1 total P0 0.393462 0.033646 P0 material group out nuclide mean std. dev. +0 3 1 total 0 0 material group in nuclide mean std. dev. +0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. +0 4 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 4 1 1 total P0 0.371473 0.071226 P0 material group out nuclide mean std. dev. +0 4 1 total 0 0 material group in nuclide mean std. dev. +0 5 1 total 0 0 material group in nuclide mean std. dev. +0 5 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 5 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. +0 5 1 total 0 0 material group in nuclide mean std. dev. +0 6 1 total 0 0 material group in nuclide mean std. dev. +0 6 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 6 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. +0 6 1 total 0 0 material group in nuclide mean std. dev. +0 7 1 total 0 0 material group in nuclide mean std. dev. +0 7 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 7 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. +0 7 1 total 0 0 material group in nuclide mean std. dev. +0 8 1 total 0 0 material group in nuclide mean std. dev. +0 8 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 8 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. +0 8 1 total 0 0 material group in nuclide mean std. dev. +0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. +0 9 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 9 1 1 total P0 0.600536 0.748875 P0 material group out nuclide mean std. dev. +0 9 1 total 0 0 material group in nuclide mean std. dev. +0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. +0 10 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 10 1 1 total P0 0.235515 0.613974 P0 material group out nuclide mean std. dev. +0 10 1 total 0 0 material group in nuclide mean std. dev. +0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. +0 11 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 11 1 1 total P0 0.491857 0.715554 P0 material group out nuclide mean std. dev. +0 11 1 total 0 0 material group in nuclide mean std. dev. +0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. +0 12 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 12 1 1 total P0 0.723265 0.808231 P0 material group out nuclide mean std. dev. +0 12 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index a23417d92..4daa6cd97 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,5 +1,5 @@ - avg(distribcell) group in nuclide score mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total ((total - scatter-1) / flux) 7.19e-01 5.21e-01 avg(distribcell) group in nuclide score mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total (nu-fission / flux) 0.00e+00 0.00e+00 avg(distribcell) group in group out nuclide score mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.95e-01 5.11e-01 avg(distribcell) group out nuclide score mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file + avg(distribcell) group in nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean std. dev. moment +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 0.695166 0.510606 P0 avg(distribcell) group out nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index c279653e5..a4b08dd4a 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -1,121 +1,121 @@ - material group in nuclide score mean std. dev. -1 1 1 total ((total - scatter-1) / flux) 3.73e-01 2.43e-02 -0 1 2 total ((total - scatter-1) / flux) 8.62e-01 3.23e-02 material group in nuclide score mean std. dev. -1 1 1 total (nu-fission / flux) 2.18e-02 1.18e-03 -0 1 2 total (nu-fission / flux) 7.14e-01 4.06e-02 material group in group out nuclide score mean std. dev. -3 1 1 1 total ((nu-scatter-0 - scatter-1) / flux) 3.37e-01 2.30e-02 -2 1 1 2 total ((nu-scatter-0 - scatter-1) / flux) 1.56e-03 5.10e-04 -1 1 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 1 2 2 total ((nu-scatter-0 - scatter-1) / flux) 4.22e-01 2.16e-02 material group out nuclide score mean std. dev. -1 1 1 total nu-fission 1.00e+00 5.53e-02 -0 1 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 2 1 total ((total - scatter-1) / flux) 2.37e-01 8.18e-03 -0 2 2 total ((total - scatter-1) / flux) 2.86e-01 4.88e-02 material group in nuclide score mean std. dev. -1 2 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 2 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 2 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.37e-01 8.18e-03 -2 2 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 2 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 2 2 2 total ((nu-scatter-0 - scatter-1) / flux) 2.86e-01 4.88e-02 material group out nuclide score mean std. dev. -1 2 1 total nu-fission 0.00e+00 0.00e+00 -0 2 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 3 1 total ((total - scatter-1) / flux) 2.87e-01 2.74e-02 -0 3 2 total ((total - scatter-1) / flux) 1.42e+00 2.65e-01 material group in nuclide score mean std. dev. -1 3 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 3 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 3 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.60e-01 2.61e-02 -2 3 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.62e-02 1.66e-03 -1 3 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 3 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.36e+00 2.59e-01 material group out nuclide score mean std. dev. -1 3 1 total nu-fission 0.00e+00 0.00e+00 -0 3 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 4 1 total ((total - scatter-1) / flux) 2.42e-01 6.10e-02 -0 4 2 total ((total - scatter-1) / flux) 1.25e+00 3.88e-01 material group in nuclide score mean std. dev. -1 4 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 4 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 4 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.18e-01 5.86e-02 -2 4 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.37e-02 3.08e-03 -1 4 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 4 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.22e+00 3.81e-01 material group out nuclide score mean std. dev. -1 4 1 total nu-fission 0.00e+00 0.00e+00 -0 4 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 5 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 5 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 5 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 5 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 5 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 5 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 5 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 5 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 5 1 total nu-fission 0.00e+00 0.00e+00 -0 5 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 6 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 6 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 6 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 6 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 6 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 6 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 6 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 6 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 6 1 total nu-fission 0.00e+00 0.00e+00 -0 6 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 7 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 7 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 7 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 7 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 7 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 7 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 7 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 7 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 7 1 total nu-fission 0.00e+00 0.00e+00 -0 7 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 8 1 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 8 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 8 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 8 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 8 1 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 8 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 8 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 8 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 8 1 total nu-fission 0.00e+00 0.00e+00 -0 8 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 9 1 total ((total - scatter-1) / flux) 6.01e-01 7.49e-01 -0 9 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 9 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 9 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 9 1 1 total ((nu-scatter-0 - scatter-1) / flux) 6.01e-01 7.49e-01 -2 9 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 9 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 9 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 9 1 total nu-fission 0.00e+00 0.00e+00 -0 9 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 10 1 total ((total - scatter-1) / flux) 2.36e-01 6.14e-01 -0 10 2 total ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 10 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 10 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 10 1 1 total ((nu-scatter-0 - scatter-1) / flux) 2.36e-01 6.14e-01 -2 10 1 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 10 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 10 2 2 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -1 10 1 total nu-fission 0.00e+00 0.00e+00 -0 10 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 11 1 total ((total - scatter-1) / flux) 1.86e-01 6.32e-01 -0 11 2 total ((total - scatter-1) / flux) 9.46e-01 1.59e+00 material group in nuclide score mean std. dev. -1 11 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 11 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 11 1 1 total ((nu-scatter-0 - scatter-1) / flux) 1.54e-01 5.98e-01 -2 11 1 2 total ((nu-scatter-0 - scatter-1) / flux) 3.19e-02 4.51e-02 -1 11 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 11 2 2 total ((nu-scatter-0 - scatter-1) / flux) 9.03e-01 1.53e+00 material group out nuclide score mean std. dev. -1 11 1 total nu-fission 0.00e+00 0.00e+00 -0 11 2 total nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -1 12 1 total ((total - scatter-1) / flux) 2.13e-01 2.71e-01 -0 12 2 total ((total - scatter-1) / flux) 1.39e+00 2.14e+00 material group in nuclide score mean std. dev. -1 12 1 total (nu-fission / flux) 0.00e+00 0.00e+00 -0 12 2 total (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -3 12 1 1 total ((nu-scatter-0 - scatter-1) / flux) 1.86e-01 2.58e-01 -2 12 1 2 total ((nu-scatter-0 - scatter-1) / flux) 2.72e-02 2.96e-02 -1 12 2 1 total ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 12 2 2 total ((nu-scatter-0 - scatter-1) / flux) 1.36e+00 2.09e+00 material group out nuclide score mean std. dev. -1 12 1 total nu-fission 0.00e+00 0.00e+00 -0 12 2 total nu-fission 0.00e+00 0.00e+00 \ No newline at end of file + material group in nuclide mean std. dev. +1 1 1 total 0.372745 0.024269 +0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. +1 1 1 total 0.021789 0.001182 +0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean std. dev. moment +3 1 1 1 total P0 0.337397 0.023039 P0 +2 1 1 2 total P0 0.001559 0.000510 P0 +1 1 2 1 total P0 0.000000 0.000000 P0 +0 1 2 2 total P0 0.422051 0.021617 P0 material group out nuclide mean std. dev. +1 1 1 total 1 0.055333 +0 1 2 total 0 0.000000 material group in nuclide mean std. dev. +1 2 1 total 0.237254 0.008184 +0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. +1 2 1 total 0 0 +0 2 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 2 1 1 total P0 0.237254 0.008184 P0 +2 2 1 2 total P0 0.000000 0.000000 P0 +1 2 2 1 total P0 0.000000 0.000000 P0 +0 2 2 2 total P0 0.285930 0.048796 P0 material group out nuclide mean std. dev. +1 2 1 total 0 0 +0 2 2 total 0 0 material group in nuclide mean std. dev. +1 3 1 total 0.286906 0.027401 +0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. +1 3 1 total 0 0 +0 3 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 3 1 1 total P0 0.259937 0.026115 P0 +2 3 1 2 total P0 0.026187 0.001665 P0 +1 3 2 1 total P0 0.000000 0.000000 P0 +0 3 2 2 total P0 1.359521 0.258505 P0 material group out nuclide mean std. dev. +1 3 1 total 0 0 +0 3 2 total 0 0 material group in nuclide mean std. dev. +1 4 1 total 0.242447 0.061031 +0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. +1 4 1 total 0 0 +0 4 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 4 1 1 total P0 0.217930 0.058565 P0 +2 4 1 2 total P0 0.023662 0.003083 P0 +1 4 2 1 total P0 0.000000 0.000000 P0 +0 4 2 2 total P0 1.215074 0.381025 P0 material group out nuclide mean std. dev. +1 4 1 total 0 0 +0 4 2 total 0 0 material group in nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 5 1 1 total P0 0 0 P0 +2 5 1 2 total P0 0 0 P0 +1 5 2 1 total P0 0 0 P0 +0 5 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 6 1 1 total P0 0 0 P0 +2 6 1 2 total P0 0 0 P0 +1 6 2 1 total P0 0 0 P0 +0 6 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 7 1 1 total P0 0 0 P0 +2 7 1 2 total P0 0 0 P0 +1 7 2 1 total P0 0 0 P0 +0 7 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 8 1 1 total P0 0 0 P0 +2 8 1 2 total P0 0 0 P0 +1 8 2 1 total P0 0 0 P0 +0 8 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in nuclide mean std. dev. +1 9 1 total 0.600536 0.748875 +0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. +1 9 1 total 0 0 +0 9 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 9 1 1 total P0 0.600536 0.748875 P0 +2 9 1 2 total P0 0.000000 0.000000 P0 +1 9 2 1 total P0 0.000000 0.000000 P0 +0 9 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +1 9 1 total 0 0 +0 9 2 total 0 0 material group in nuclide mean std. dev. +1 10 1 total 0.235515 0.613974 +0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. +1 10 1 total 0 0 +0 10 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 10 1 1 total P0 0.235515 0.613974 P0 +2 10 1 2 total P0 0.000000 0.000000 P0 +1 10 2 1 total P0 0.000000 0.000000 P0 +0 10 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +1 10 1 total 0 0 +0 10 2 total 0 0 material group in nuclide mean std. dev. +1 11 1 total 0.186324 0.632129 +0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. +1 11 1 total 0 0 +0 11 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 11 1 1 total P0 0.154449 0.597686 P0 +2 11 1 2 total P0 0.031875 0.045078 P0 +1 11 2 1 total P0 0.000000 0.000000 P0 +0 11 2 2 total P0 0.903085 1.532144 P0 material group out nuclide mean std. dev. +1 11 1 total 0 0 +0 11 2 total 0 0 material group in nuclide mean std. dev. +1 12 1 total 0.213292 0.271444 +0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. +1 12 1 total 0 0 +0 12 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +3 12 1 1 total P0 0.186052 0.257633 P0 +2 12 1 2 total P0 0.027240 0.029555 P0 +1 12 2 1 total P0 0.000000 0.000000 P0 +0 12 2 2 total P0 1.357118 2.089846 P0 material group out nuclide mean std. dev. +1 12 1 total 0 0 +0 12 2 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index 99582fa7d..aac5ff1ef 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -1,1971 +1,1971 @@ - material group in nuclide score mean std. dev. -34 1 1 U-234 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 -35 1 1 U-235 ((total - scatter-1) / flux) 1.07e-02 1.89e-03 -36 1 1 U-236 ((total - scatter-1) / flux) 2.39e-03 1.06e-03 -37 1 1 U-238 ((total - scatter-1) / flux) 2.14e-01 1.33e-02 -38 1 1 Np-237 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 1 1 Pu-238 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 1 1 Pu-239 ((total - scatter-1) / flux) 2.91e-03 6.39e-04 -41 1 1 Pu-240 ((total - scatter-1) / flux) 4.43e-03 8.06e-04 -42 1 1 Pu-241 ((total - scatter-1) / flux) 6.90e-04 3.87e-04 -43 1 1 Pu-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -44 1 1 Am-241 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 -45 1 1 Am-242m ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -46 1 1 Am-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -47 1 1 Cm-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -48 1 1 Cm-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -49 1 1 Cm-244 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -50 1 1 Cm-245 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -51 1 1 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -52 1 1 Tc-99 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 -53 1 1 Ru-101 ((total - scatter-1) / flux) 2.38e-04 2.54e-04 -54 1 1 Ru-103 ((total - scatter-1) / flux) 2.26e-06 2.43e-04 -55 1 1 Ag-109 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -56 1 1 Xe-135 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -57 1 1 Cs-133 ((total - scatter-1) / flux) 3.47e-04 2.13e-04 -58 1 1 Nd-143 ((total - scatter-1) / flux) 4.47e-04 2.92e-04 -59 1 1 Nd-145 ((total - scatter-1) / flux) 5.64e-04 2.94e-04 -60 1 1 Sm-147 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -61 1 1 Sm-149 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -62 1 1 Sm-150 ((total - scatter-1) / flux) 4.72e-04 2.39e-04 -63 1 1 Sm-151 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -64 1 1 Sm-152 ((total - scatter-1) / flux) 4.92e-04 3.52e-04 -65 1 1 Eu-153 ((total - scatter-1) / flux) 1.73e-04 1.73e-04 -66 1 1 Gd-155 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -67 1 1 O-16 ((total - scatter-1) / flux) 1.35e-01 9.80e-03 -0 1 2 U-234 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 1 2 U-235 ((total - scatter-1) / flux) 2.00e-01 7.78e-03 -2 1 2 U-236 ((total - scatter-1) / flux) 1.50e-03 2.04e-03 -3 1 2 U-238 ((total - scatter-1) / flux) 2.55e-01 2.97e-02 -4 1 2 Np-237 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 1 2 Pu-238 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 1 2 Pu-239 ((total - scatter-1) / flux) 1.60e-01 1.14e-02 -7 1 2 Pu-240 ((total - scatter-1) / flux) 7.92e-03 3.71e-03 -8 1 2 Pu-241 ((total - scatter-1) / flux) 1.78e-02 3.73e-03 -9 1 2 Pu-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 1 2 Am-241 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 1 2 Am-242m ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 1 2 Am-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 1 2 Cm-242 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 1 2 Cm-243 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 1 2 Cm-244 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 1 2 Cm-245 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 1 2 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 1 2 Tc-99 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 1 2 Ru-101 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 1 2 Ru-103 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -21 1 2 Ag-109 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -22 1 2 Xe-135 ((total - scatter-1) / flux) 1.39e-02 3.98e-03 -23 1 2 Cs-133 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 1 2 Nd-143 ((total - scatter-1) / flux) 3.96e-03 2.43e-03 -25 1 2 Nd-145 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 1 2 Sm-147 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -27 1 2 Sm-149 ((total - scatter-1) / flux) 1.98e-03 1.98e-03 -28 1 2 Sm-150 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 1 2 Sm-151 ((total - scatter-1) / flux) 1.98e-03 1.98e-03 -30 1 2 Sm-152 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 1 2 Eu-153 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 1 2 Gd-155 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 1 2 O-16 ((total - scatter-1) / flux) 1.97e-01 1.47e-02 material group in nuclide score mean std. dev. -34 1 1 U-234 (nu-fission / flux) 7.27e-06 4.42e-07 -35 1 1 U-235 (nu-fission / flux) 9.59e-03 5.94e-04 -36 1 1 U-236 (nu-fission / flux) 7.57e-05 7.52e-06 -37 1 1 U-238 (nu-fission / flux) 7.18e-03 6.51e-04 -38 1 1 Np-237 (nu-fission / flux) 1.32e-05 8.04e-07 -39 1 1 Pu-238 (nu-fission / flux) 7.75e-06 3.99e-07 -40 1 1 Pu-239 (nu-fission / flux) 3.81e-03 3.64e-04 -41 1 1 Pu-240 (nu-fission / flux) 6.94e-05 4.73e-06 -42 1 1 Pu-241 (nu-fission / flux) 1.03e-03 9.08e-05 -43 1 1 Pu-242 (nu-fission / flux) 6.00e-06 3.82e-07 -44 1 1 Am-241 (nu-fission / flux) 1.15e-06 8.27e-08 -45 1 1 Am-242m (nu-fission / flux) 1.10e-06 6.16e-08 -46 1 1 Am-243 (nu-fission / flux) 8.32e-07 5.84e-08 -47 1 1 Cm-242 (nu-fission / flux) 5.09e-07 5.26e-08 -48 1 1 Cm-243 (nu-fission / flux) 2.25e-07 1.46e-08 -49 1 1 Cm-244 (nu-fission / flux) 2.99e-07 2.75e-08 -50 1 1 Cm-245 (nu-fission / flux) 3.06e-07 3.06e-08 -51 1 1 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 -52 1 1 Tc-99 (nu-fission / flux) 0.00e+00 0.00e+00 -53 1 1 Ru-101 (nu-fission / flux) 0.00e+00 0.00e+00 -54 1 1 Ru-103 (nu-fission / flux) 0.00e+00 0.00e+00 -55 1 1 Ag-109 (nu-fission / flux) 0.00e+00 0.00e+00 -56 1 1 Xe-135 (nu-fission / flux) 0.00e+00 0.00e+00 -57 1 1 Cs-133 (nu-fission / flux) 0.00e+00 0.00e+00 -58 1 1 Nd-143 (nu-fission / flux) 0.00e+00 0.00e+00 -59 1 1 Nd-145 (nu-fission / flux) 0.00e+00 0.00e+00 -60 1 1 Sm-147 (nu-fission / flux) 0.00e+00 0.00e+00 -61 1 1 Sm-149 (nu-fission / flux) 0.00e+00 0.00e+00 -62 1 1 Sm-150 (nu-fission / flux) 0.00e+00 0.00e+00 -63 1 1 Sm-151 (nu-fission / flux) 0.00e+00 0.00e+00 -64 1 1 Sm-152 (nu-fission / flux) 0.00e+00 0.00e+00 -65 1 1 Eu-153 (nu-fission / flux) 0.00e+00 0.00e+00 -66 1 1 Gd-155 (nu-fission / flux) 0.00e+00 0.00e+00 -67 1 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -0 1 2 U-234 (nu-fission / flux) 4.41e-07 2.83e-08 -1 1 2 U-235 (nu-fission / flux) 3.77e-01 2.45e-02 -2 1 2 U-236 (nu-fission / flux) 6.10e-06 3.73e-07 -3 1 2 U-238 (nu-fission / flux) 5.35e-07 3.31e-08 -4 1 2 Np-237 (nu-fission / flux) 2.70e-07 2.10e-08 -5 1 2 Pu-238 (nu-fission / flux) 3.46e-05 2.64e-06 -6 1 2 Pu-239 (nu-fission / flux) 2.89e-01 1.38e-02 -7 1 2 Pu-240 (nu-fission / flux) 4.53e-06 2.54e-07 -8 1 2 Pu-241 (nu-fission / flux) 4.81e-02 2.78e-03 -9 1 2 Pu-242 (nu-fission / flux) 8.72e-08 5.46e-09 -10 1 2 Am-241 (nu-fission / flux) 4.61e-06 2.16e-07 -11 1 2 Am-242m (nu-fission / flux) 1.43e-04 8.44e-06 -12 1 2 Am-243 (nu-fission / flux) 7.88e-08 4.73e-09 -13 1 2 Cm-242 (nu-fission / flux) 9.73e-07 6.14e-08 -14 1 2 Cm-243 (nu-fission / flux) 1.83e-06 1.07e-07 -15 1 2 Cm-244 (nu-fission / flux) 1.58e-07 9.94e-09 -16 1 2 Cm-245 (nu-fission / flux) 1.21e-05 8.81e-07 -17 1 2 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 -18 1 2 Tc-99 (nu-fission / flux) 0.00e+00 0.00e+00 -19 1 2 Ru-101 (nu-fission / flux) 0.00e+00 0.00e+00 -20 1 2 Ru-103 (nu-fission / flux) 0.00e+00 0.00e+00 -21 1 2 Ag-109 (nu-fission / flux) 0.00e+00 0.00e+00 -22 1 2 Xe-135 (nu-fission / flux) 0.00e+00 0.00e+00 -23 1 2 Cs-133 (nu-fission / flux) 0.00e+00 0.00e+00 -24 1 2 Nd-143 (nu-fission / flux) 0.00e+00 0.00e+00 -25 1 2 Nd-145 (nu-fission / flux) 0.00e+00 0.00e+00 -26 1 2 Sm-147 (nu-fission / flux) 0.00e+00 0.00e+00 -27 1 2 Sm-149 (nu-fission / flux) 0.00e+00 0.00e+00 -28 1 2 Sm-150 (nu-fission / flux) 0.00e+00 0.00e+00 -29 1 2 Sm-151 (nu-fission / flux) 0.00e+00 0.00e+00 -30 1 2 Sm-152 (nu-fission / flux) 0.00e+00 0.00e+00 -31 1 2 Eu-153 (nu-fission / flux) 0.00e+00 0.00e+00 -32 1 2 Gd-155 (nu-fission / flux) 0.00e+00 0.00e+00 -33 1 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -102 1 1 1 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -103 1 1 1 U-235 ((nu-scatter-0 - scatter-1) / flux) 3.23e-03 1.14e-03 -104 1 1 1 U-236 ((nu-scatter-0 - scatter-1) / flux) 1.70e-03 9.23e-04 -105 1 1 1 U-238 ((nu-scatter-0 - scatter-1) / flux) 1.95e-01 1.33e-02 -106 1 1 1 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -107 1 1 1 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -108 1 1 1 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 1.01e-03 4.77e-04 -109 1 1 1 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 1.31e-03 2.95e-04 -110 1 1 1 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 3.44e-04 2.44e-04 -111 1 1 1 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -112 1 1 1 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -113 1 1 1 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -114 1 1 1 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -115 1 1 1 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -116 1 1 1 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -117 1 1 1 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -118 1 1 1 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -119 1 1 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -120 1 1 1 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -121 1 1 1 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 2.38e-04 2.54e-04 -122 1 1 1 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 2.26e-06 2.43e-04 -123 1 1 1 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -124 1 1 1 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -125 1 1 1 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -126 1 1 1 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 4.47e-04 2.92e-04 -127 1 1 1 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 5.64e-04 2.94e-04 -128 1 1 1 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -129 1 1 1 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -130 1 1 1 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 2.99e-04 2.38e-04 -131 1 1 1 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -132 1 1 1 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 4.92e-04 3.52e-04 -133 1 1 1 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -134 1 1 1 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -135 1 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.33e-01 9.82e-03 -68 1 1 2 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 1 1 2 U-235 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 1 1 2 U-236 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 1 1 2 U-238 ((nu-scatter-0 - scatter-1) / flux) 1.73e-04 1.73e-04 -72 1 1 2 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 1 1 2 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 1 1 2 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 1 1 2 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 1 1 2 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 1 1 2 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 1 1 2 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 1 1 2 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 1 1 2 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -81 1 1 2 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 1 1 2 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 1 1 2 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -84 1 1 2 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -85 1 1 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -86 1 1 2 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -87 1 1 2 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -88 1 1 2 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -89 1 1 2 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -90 1 1 2 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -91 1 1 2 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -92 1 1 2 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -93 1 1 2 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -94 1 1 2 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -95 1 1 2 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -96 1 1 2 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -97 1 1 2 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -98 1 1 2 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -99 1 1 2 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -100 1 1 2 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -101 1 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.39e-03 4.46e-04 -34 1 2 1 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 1 2 1 U-235 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 1 2 1 U-236 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 1 2 1 U-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 1 2 1 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 1 2 1 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 1 2 1 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 1 2 1 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 1 2 1 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 1 2 1 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 1 2 1 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 1 2 1 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 1 2 1 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 1 2 1 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 1 2 1 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 1 2 1 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 1 2 1 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 1 2 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 1 2 1 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 1 2 1 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 1 2 1 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 1 2 1 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 1 2 1 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 1 2 1 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 1 2 1 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 1 2 1 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 1 2 1 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 1 2 1 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 1 2 1 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -63 1 2 1 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -64 1 2 1 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 1 2 1 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 1 2 1 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 1 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 1 2 2 U-234 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 1 2 2 U-235 ((nu-scatter-0 - scatter-1) / flux) 3.89e-03 3.96e-03 -2 1 2 2 U-236 ((nu-scatter-0 - scatter-1) / flux) 1.50e-03 2.04e-03 -3 1 2 2 U-238 ((nu-scatter-0 - scatter-1) / flux) 2.20e-01 2.60e-02 -4 1 2 2 Np-237 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 1 2 2 Pu-238 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 1 2 2 Pu-239 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 1 2 2 Pu-240 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 1 2 2 Pu-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 1 2 2 Pu-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 1 2 2 Am-241 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 1 2 2 Am-242m ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 1 2 2 Am-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 1 2 2 Cm-242 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 1 2 2 Cm-243 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 1 2 2 Cm-244 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 1 2 2 Cm-245 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 1 2 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 1 2 2 Tc-99 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 1 2 2 Ru-101 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 1 2 2 Ru-103 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 1 2 2 Ag-109 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 1 2 2 Xe-135 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 1 2 2 Cs-133 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 1 2 2 Nd-143 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 1 2 2 Nd-145 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 1 2 2 Sm-147 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 1 2 2 Sm-149 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 1 2 2 Sm-150 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 1 2 2 Sm-151 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 1 2 2 Sm-152 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 1 2 2 Eu-153 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 1 2 2 Gd-155 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 1 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.97e-01 1.47e-02 material group out nuclide score mean std. dev. -34 1 1 U-234 nu-fission 0.00e+00 0.00e+00 -35 1 1 U-235 nu-fission 1.00e+00 6.64e-02 -36 1 1 U-236 nu-fission 0.00e+00 0.00e+00 -37 1 1 U-238 nu-fission 1.00e+00 9.31e-02 -38 1 1 Np-237 nu-fission 0.00e+00 0.00e+00 -39 1 1 Pu-238 nu-fission 0.00e+00 0.00e+00 -40 1 1 Pu-239 nu-fission 1.00e+00 1.05e-01 -41 1 1 Pu-240 nu-fission 0.00e+00 0.00e+00 -42 1 1 Pu-241 nu-fission 1.00e+00 2.64e-01 -43 1 1 Pu-242 nu-fission 0.00e+00 0.00e+00 -44 1 1 Am-241 nu-fission 0.00e+00 0.00e+00 -45 1 1 Am-242m nu-fission 0.00e+00 0.00e+00 -46 1 1 Am-243 nu-fission 0.00e+00 0.00e+00 -47 1 1 Cm-242 nu-fission 0.00e+00 0.00e+00 -48 1 1 Cm-243 nu-fission 0.00e+00 0.00e+00 -49 1 1 Cm-244 nu-fission 0.00e+00 0.00e+00 -50 1 1 Cm-245 nu-fission 0.00e+00 0.00e+00 -51 1 1 Mo-95 nu-fission 0.00e+00 0.00e+00 -52 1 1 Tc-99 nu-fission 0.00e+00 0.00e+00 -53 1 1 Ru-101 nu-fission 0.00e+00 0.00e+00 -54 1 1 Ru-103 nu-fission 0.00e+00 0.00e+00 -55 1 1 Ag-109 nu-fission 0.00e+00 0.00e+00 -56 1 1 Xe-135 nu-fission 0.00e+00 0.00e+00 -57 1 1 Cs-133 nu-fission 0.00e+00 0.00e+00 -58 1 1 Nd-143 nu-fission 0.00e+00 0.00e+00 -59 1 1 Nd-145 nu-fission 0.00e+00 0.00e+00 -60 1 1 Sm-147 nu-fission 0.00e+00 0.00e+00 -61 1 1 Sm-149 nu-fission 0.00e+00 0.00e+00 -62 1 1 Sm-150 nu-fission 0.00e+00 0.00e+00 -63 1 1 Sm-151 nu-fission 0.00e+00 0.00e+00 -64 1 1 Sm-152 nu-fission 0.00e+00 0.00e+00 -65 1 1 Eu-153 nu-fission 0.00e+00 0.00e+00 -66 1 1 Gd-155 nu-fission 0.00e+00 0.00e+00 -67 1 1 O-16 nu-fission 0.00e+00 0.00e+00 -0 1 2 U-234 nu-fission 0.00e+00 0.00e+00 -1 1 2 U-235 nu-fission 0.00e+00 0.00e+00 -2 1 2 U-236 nu-fission 0.00e+00 0.00e+00 -3 1 2 U-238 nu-fission 0.00e+00 0.00e+00 -4 1 2 Np-237 nu-fission 0.00e+00 0.00e+00 -5 1 2 Pu-238 nu-fission 0.00e+00 0.00e+00 -6 1 2 Pu-239 nu-fission 0.00e+00 0.00e+00 -7 1 2 Pu-240 nu-fission 0.00e+00 0.00e+00 -8 1 2 Pu-241 nu-fission 0.00e+00 0.00e+00 -9 1 2 Pu-242 nu-fission 0.00e+00 0.00e+00 -10 1 2 Am-241 nu-fission 0.00e+00 0.00e+00 -11 1 2 Am-242m nu-fission 0.00e+00 0.00e+00 -12 1 2 Am-243 nu-fission 0.00e+00 0.00e+00 -13 1 2 Cm-242 nu-fission 0.00e+00 0.00e+00 -14 1 2 Cm-243 nu-fission 0.00e+00 0.00e+00 -15 1 2 Cm-244 nu-fission 0.00e+00 0.00e+00 -16 1 2 Cm-245 nu-fission 0.00e+00 0.00e+00 -17 1 2 Mo-95 nu-fission 0.00e+00 0.00e+00 -18 1 2 Tc-99 nu-fission 0.00e+00 0.00e+00 -19 1 2 Ru-101 nu-fission 0.00e+00 0.00e+00 -20 1 2 Ru-103 nu-fission 0.00e+00 0.00e+00 -21 1 2 Ag-109 nu-fission 0.00e+00 0.00e+00 -22 1 2 Xe-135 nu-fission 0.00e+00 0.00e+00 -23 1 2 Cs-133 nu-fission 0.00e+00 0.00e+00 -24 1 2 Nd-143 nu-fission 0.00e+00 0.00e+00 -25 1 2 Nd-145 nu-fission 0.00e+00 0.00e+00 -26 1 2 Sm-147 nu-fission 0.00e+00 0.00e+00 -27 1 2 Sm-149 nu-fission 0.00e+00 0.00e+00 -28 1 2 Sm-150 nu-fission 0.00e+00 0.00e+00 -29 1 2 Sm-151 nu-fission 0.00e+00 0.00e+00 -30 1 2 Sm-152 nu-fission 0.00e+00 0.00e+00 -31 1 2 Eu-153 nu-fission 0.00e+00 0.00e+00 -32 1 2 Gd-155 nu-fission 0.00e+00 0.00e+00 -33 1 2 O-16 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -5 2 1 Zr-90 ((total - scatter-1) / flux) 1.05e-01 8.92e-03 -6 2 1 Zr-91 ((total - scatter-1) / flux) 3.62e-02 3.74e-03 -7 2 1 Zr-92 ((total - scatter-1) / flux) 4.24e-02 3.03e-03 -8 2 1 Zr-94 ((total - scatter-1) / flux) 4.61e-02 6.25e-03 -9 2 1 Zr-96 ((total - scatter-1) / flux) 7.79e-03 1.54e-03 -0 2 2 Zr-90 ((total - scatter-1) / flux) 1.22e-01 3.49e-02 -1 2 2 Zr-91 ((total - scatter-1) / flux) 6.18e-02 2.43e-02 -2 2 2 Zr-92 ((total - scatter-1) / flux) 4.16e-02 1.63e-02 -3 2 2 Zr-94 ((total - scatter-1) / flux) 6.08e-02 2.15e-02 -4 2 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -5 2 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -6 2 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -7 2 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -8 2 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -9 2 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 -0 2 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -1 2 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -2 2 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -3 2 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -4 2 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -15 2 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 1.05e-01 8.92e-03 -16 2 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 3.62e-02 3.74e-03 -17 2 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 4.24e-02 3.03e-03 -18 2 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.61e-02 6.25e-03 -19 2 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 7.79e-03 1.54e-03 -10 2 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 2 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 2 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 2 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 2 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 2 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 2 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 2 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 2 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 2 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 2 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 1.22e-01 3.49e-02 -1 2 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 6.18e-02 2.43e-02 -2 2 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 4.16e-02 1.63e-02 -3 2 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 6.08e-02 2.15e-02 -4 2 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -5 2 1 Zr-90 nu-fission 0.00e+00 0.00e+00 -6 2 1 Zr-91 nu-fission 0.00e+00 0.00e+00 -7 2 1 Zr-92 nu-fission 0.00e+00 0.00e+00 -8 2 1 Zr-94 nu-fission 0.00e+00 0.00e+00 -9 2 1 Zr-96 nu-fission 0.00e+00 0.00e+00 -0 2 2 Zr-90 nu-fission 0.00e+00 0.00e+00 -1 2 2 Zr-91 nu-fission 0.00e+00 0.00e+00 -2 2 2 Zr-92 nu-fission 0.00e+00 0.00e+00 -3 2 2 Zr-94 nu-fission 0.00e+00 0.00e+00 -4 2 2 Zr-96 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -4 3 1 H-1 ((total - scatter-1) / flux) 2.07e-01 2.30e-02 -5 3 1 O-16 ((total - scatter-1) / flux) 7.93e-02 5.20e-03 -6 3 1 B-10 ((total - scatter-1) / flux) 5.21e-04 2.44e-04 -7 3 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 3 2 H-1 ((total - scatter-1) / flux) 1.28e+00 2.51e-01 -1 3 2 O-16 ((total - scatter-1) / flux) 8.54e-02 1.40e-02 -2 3 2 B-10 ((total - scatter-1) / flux) 4.92e-02 8.23e-03 -3 3 2 B-11 ((total - scatter-1) / flux) 1.95e-04 1.53e-03 material group in nuclide score mean std. dev. -4 3 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -5 3 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -6 3 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -7 3 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -0 3 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 3 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 3 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 3 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -12 3 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.81e-01 2.21e-02 -13 3 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 7.86e-02 5.04e-03 -14 3 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 3 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 3 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.57e-02 1.58e-03 -9 3 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 5.21e-04 1.31e-04 -10 3 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 3 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 3 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 3 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 3 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 3 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 3 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.27e+00 2.51e-01 -1 3 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 8.54e-02 1.40e-02 -2 3 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 3 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 1.95e-04 1.53e-03 material group out nuclide score mean std. dev. -4 3 1 H-1 nu-fission 0.00e+00 0.00e+00 -5 3 1 O-16 nu-fission 0.00e+00 0.00e+00 -6 3 1 B-10 nu-fission 0.00e+00 0.00e+00 -7 3 1 B-11 nu-fission 0.00e+00 0.00e+00 -0 3 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 3 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 3 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 3 2 B-11 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -4 4 1 H-1 ((total - scatter-1) / flux) 1.75e-01 5.37e-02 -5 4 1 O-16 ((total - scatter-1) / flux) 6.65e-02 1.01e-02 -6 4 1 B-10 ((total - scatter-1) / flux) 5.70e-04 3.52e-04 -7 4 1 B-11 ((total - scatter-1) / flux) 8.88e-05 3.46e-04 -0 4 2 H-1 ((total - scatter-1) / flux) 1.14e+00 3.65e-01 -1 4 2 O-16 ((total - scatter-1) / flux) 8.51e-02 2.81e-02 -2 4 2 B-10 ((total - scatter-1) / flux) 2.59e-02 7.28e-03 -3 4 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -4 4 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -5 4 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -6 4 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -7 4 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -0 4 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 4 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 4 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 4 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -12 4 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.51e-01 5.15e-02 -13 4 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 6.65e-02 1.01e-02 -14 4 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 4 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 8.88e-05 3.46e-04 -8 4 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.37e-02 3.08e-03 -9 4 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 4 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 4 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 4 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 4 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 4 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 4 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 4 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.13e+00 3.62e-01 -1 4 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 8.51e-02 2.81e-02 -2 4 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 4 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -4 4 1 H-1 nu-fission 0.00e+00 0.00e+00 -5 4 1 O-16 nu-fission 0.00e+00 0.00e+00 -6 4 1 B-10 nu-fission 0.00e+00 0.00e+00 -7 4 1 B-11 nu-fission 0.00e+00 0.00e+00 -0 4 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 4 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 4 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 4 2 B-11 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -27 5 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 5 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 5 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 5 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 5 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 5 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 5 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 5 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 5 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 5 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 5 1 Mo-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 5 1 Mo-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 5 1 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 5 1 Mo-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -41 5 1 Mo-97 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -42 5 1 Mo-98 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -43 5 1 Mo-100 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -44 5 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -45 5 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -46 5 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -47 5 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -48 5 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -49 5 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -50 5 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -51 5 1 C-Nat ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -52 5 1 Cu-63 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -53 5 1 Cu-65 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 5 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 5 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 5 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 5 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 5 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 5 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 5 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 5 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 5 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 5 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 5 2 Mo-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 5 2 Mo-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 5 2 Mo-95 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 5 2 Mo-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 5 2 Mo-97 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 5 2 Mo-98 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 5 2 Mo-100 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 5 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 5 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 5 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 5 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -21 5 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -22 5 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -23 5 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 5 2 C-Nat ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 5 2 Cu-63 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 5 2 Cu-65 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -27 5 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -28 5 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -29 5 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -30 5 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -31 5 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -32 5 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -33 5 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -34 5 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -35 5 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -36 5 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -37 5 1 Mo-92 (nu-fission / flux) 0.00e+00 0.00e+00 -38 5 1 Mo-94 (nu-fission / flux) 0.00e+00 0.00e+00 -39 5 1 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 -40 5 1 Mo-96 (nu-fission / flux) 0.00e+00 0.00e+00 -41 5 1 Mo-97 (nu-fission / flux) 0.00e+00 0.00e+00 -42 5 1 Mo-98 (nu-fission / flux) 0.00e+00 0.00e+00 -43 5 1 Mo-100 (nu-fission / flux) 0.00e+00 0.00e+00 -44 5 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -45 5 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -46 5 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -47 5 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -48 5 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -49 5 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -50 5 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -51 5 1 C-Nat (nu-fission / flux) 0.00e+00 0.00e+00 -52 5 1 Cu-63 (nu-fission / flux) 0.00e+00 0.00e+00 -53 5 1 Cu-65 (nu-fission / flux) 0.00e+00 0.00e+00 -0 5 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -1 5 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -2 5 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -3 5 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -4 5 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -5 5 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -6 5 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -7 5 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -8 5 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -9 5 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -10 5 2 Mo-92 (nu-fission / flux) 0.00e+00 0.00e+00 -11 5 2 Mo-94 (nu-fission / flux) 0.00e+00 0.00e+00 -12 5 2 Mo-95 (nu-fission / flux) 0.00e+00 0.00e+00 -13 5 2 Mo-96 (nu-fission / flux) 0.00e+00 0.00e+00 -14 5 2 Mo-97 (nu-fission / flux) 0.00e+00 0.00e+00 -15 5 2 Mo-98 (nu-fission / flux) 0.00e+00 0.00e+00 -16 5 2 Mo-100 (nu-fission / flux) 0.00e+00 0.00e+00 -17 5 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -18 5 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -19 5 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -20 5 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -21 5 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -22 5 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -23 5 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -24 5 2 C-Nat (nu-fission / flux) 0.00e+00 0.00e+00 -25 5 2 Cu-63 (nu-fission / flux) 0.00e+00 0.00e+00 -26 5 2 Cu-65 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -81 5 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 5 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 5 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -84 5 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -85 5 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -86 5 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -87 5 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -88 5 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -89 5 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -90 5 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -91 5 1 1 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -92 5 1 1 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -93 5 1 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -94 5 1 1 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -95 5 1 1 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -96 5 1 1 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -97 5 1 1 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -98 5 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -99 5 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -100 5 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -101 5 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -102 5 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -103 5 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -104 5 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -105 5 1 1 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -106 5 1 1 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -107 5 1 1 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 5 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 5 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 5 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 5 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 5 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 5 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 5 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 5 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 5 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -63 5 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -64 5 1 2 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 5 1 2 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 5 1 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 5 1 2 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 5 1 2 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 5 1 2 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 5 1 2 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 5 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 5 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 5 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 5 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 5 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 5 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 5 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 5 1 2 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 5 1 2 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 5 1 2 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 5 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 5 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 5 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 5 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 5 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 5 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 5 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 5 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 5 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 5 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 5 2 1 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 5 2 1 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 5 2 1 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 5 2 1 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 5 2 1 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 5 2 1 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 5 2 1 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 5 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 5 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 5 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 5 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 5 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 5 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 5 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 5 2 1 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 5 2 1 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 5 2 1 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 5 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 5 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 5 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 5 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 5 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 5 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 5 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 5 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 5 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 5 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 5 2 2 Mo-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 5 2 2 Mo-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 5 2 2 Mo-95 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 5 2 2 Mo-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 5 2 2 Mo-97 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 5 2 2 Mo-98 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 5 2 2 Mo-100 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 5 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 5 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 5 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 5 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 5 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 5 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 5 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 5 2 2 C-Nat ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 5 2 2 Cu-63 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 5 2 2 Cu-65 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -27 5 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -28 5 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -29 5 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -30 5 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -31 5 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -32 5 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -33 5 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -34 5 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -35 5 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -36 5 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -37 5 1 Mo-92 nu-fission 0.00e+00 0.00e+00 -38 5 1 Mo-94 nu-fission 0.00e+00 0.00e+00 -39 5 1 Mo-95 nu-fission 0.00e+00 0.00e+00 -40 5 1 Mo-96 nu-fission 0.00e+00 0.00e+00 -41 5 1 Mo-97 nu-fission 0.00e+00 0.00e+00 -42 5 1 Mo-98 nu-fission 0.00e+00 0.00e+00 -43 5 1 Mo-100 nu-fission 0.00e+00 0.00e+00 -44 5 1 Si-28 nu-fission 0.00e+00 0.00e+00 -45 5 1 Si-29 nu-fission 0.00e+00 0.00e+00 -46 5 1 Si-30 nu-fission 0.00e+00 0.00e+00 -47 5 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -48 5 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -49 5 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -50 5 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -51 5 1 C-Nat nu-fission 0.00e+00 0.00e+00 -52 5 1 Cu-63 nu-fission 0.00e+00 0.00e+00 -53 5 1 Cu-65 nu-fission 0.00e+00 0.00e+00 -0 5 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -1 5 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -2 5 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -3 5 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -4 5 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -5 5 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -6 5 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -7 5 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -8 5 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -9 5 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -10 5 2 Mo-92 nu-fission 0.00e+00 0.00e+00 -11 5 2 Mo-94 nu-fission 0.00e+00 0.00e+00 -12 5 2 Mo-95 nu-fission 0.00e+00 0.00e+00 -13 5 2 Mo-96 nu-fission 0.00e+00 0.00e+00 -14 5 2 Mo-97 nu-fission 0.00e+00 0.00e+00 -15 5 2 Mo-98 nu-fission 0.00e+00 0.00e+00 -16 5 2 Mo-100 nu-fission 0.00e+00 0.00e+00 -17 5 2 Si-28 nu-fission 0.00e+00 0.00e+00 -18 5 2 Si-29 nu-fission 0.00e+00 0.00e+00 -19 5 2 Si-30 nu-fission 0.00e+00 0.00e+00 -20 5 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -21 5 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -22 5 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -23 5 2 Cr-54 nu-fission 0.00e+00 0.00e+00 -24 5 2 C-Nat nu-fission 0.00e+00 0.00e+00 -25 5 2 Cu-63 nu-fission 0.00e+00 0.00e+00 -26 5 2 Cu-65 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 6 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -22 6 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -23 6 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 6 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 6 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 6 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -27 6 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 6 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 6 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 6 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 6 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 6 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 6 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 6 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 6 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 6 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 6 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 6 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 6 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 6 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -41 6 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 6 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 6 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 6 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 6 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 6 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 6 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 6 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 6 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 6 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 6 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 6 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 6 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 6 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 6 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 6 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 6 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 6 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 6 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 6 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 6 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 6 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 6 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -22 6 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -23 6 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -24 6 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -25 6 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -26 6 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -27 6 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -28 6 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -29 6 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -30 6 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -31 6 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -32 6 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -33 6 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -34 6 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -35 6 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -36 6 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -37 6 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -38 6 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -39 6 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -40 6 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -41 6 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -0 6 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 6 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 6 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 6 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 6 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -5 6 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -6 6 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -7 6 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -8 6 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -9 6 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -10 6 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -11 6 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -12 6 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -13 6 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -14 6 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -15 6 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -16 6 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -17 6 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -18 6 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -19 6 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -20 6 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -63 6 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -64 6 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 6 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 6 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 6 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 6 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 6 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 6 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 6 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 6 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 6 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 6 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 6 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 6 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 6 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 6 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 6 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 6 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -81 6 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 6 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 6 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 6 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 6 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 6 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 6 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 6 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 6 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 6 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 6 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 6 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 6 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 6 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 6 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 6 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 6 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 6 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 6 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 6 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 6 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 6 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 6 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 6 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 6 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 6 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 6 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 6 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 6 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 6 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 6 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 6 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 6 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 6 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 6 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 6 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 6 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 6 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 6 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 6 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 6 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 6 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 6 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 6 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 6 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 6 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 6 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 6 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 6 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 6 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 6 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 6 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 6 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 6 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 6 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 6 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 6 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 6 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 6 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 6 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 6 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 6 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 6 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 6 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 6 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 6 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -21 6 1 H-1 nu-fission 0.00e+00 0.00e+00 -22 6 1 O-16 nu-fission 0.00e+00 0.00e+00 -23 6 1 B-10 nu-fission 0.00e+00 0.00e+00 -24 6 1 B-11 nu-fission 0.00e+00 0.00e+00 -25 6 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -26 6 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -27 6 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -28 6 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -29 6 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -30 6 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -31 6 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -32 6 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -33 6 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -34 6 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -35 6 1 Si-28 nu-fission 0.00e+00 0.00e+00 -36 6 1 Si-29 nu-fission 0.00e+00 0.00e+00 -37 6 1 Si-30 nu-fission 0.00e+00 0.00e+00 -38 6 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -39 6 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -40 6 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -41 6 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -0 6 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 6 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 6 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 6 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 6 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -5 6 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -6 6 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -7 6 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -8 6 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -9 6 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -10 6 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -11 6 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -12 6 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -13 6 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -14 6 2 Si-28 nu-fission 0.00e+00 0.00e+00 -15 6 2 Si-29 nu-fission 0.00e+00 0.00e+00 -16 6 2 Si-30 nu-fission 0.00e+00 0.00e+00 -17 6 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -18 6 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -19 6 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -20 6 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 7 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -22 7 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -23 7 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 7 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 7 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 7 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -27 7 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 7 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 7 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 7 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 7 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 7 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 7 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 7 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 7 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 7 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 7 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 7 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 7 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 7 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -41 7 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 7 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 7 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 7 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 7 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 7 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 7 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 7 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 7 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 7 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 7 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 7 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 7 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 7 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 7 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 7 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 7 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 7 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 7 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 7 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 7 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 7 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 7 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -22 7 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -23 7 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -24 7 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -25 7 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -26 7 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -27 7 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -28 7 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -29 7 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -30 7 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -31 7 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -32 7 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -33 7 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -34 7 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -35 7 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -36 7 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -37 7 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -38 7 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -39 7 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -40 7 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -41 7 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -0 7 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 7 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 7 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 7 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 7 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -5 7 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -6 7 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -7 7 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -8 7 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -9 7 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -10 7 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -11 7 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -12 7 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -13 7 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -14 7 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -15 7 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -16 7 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -17 7 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -18 7 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -19 7 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -20 7 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -63 7 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -64 7 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 7 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 7 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 7 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 7 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 7 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 7 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 7 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 7 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 7 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 7 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 7 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 7 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 7 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 7 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 7 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 7 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -81 7 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 7 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 7 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 7 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 7 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 7 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 7 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 7 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 7 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 7 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 7 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 7 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 7 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 7 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 7 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 7 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 7 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 7 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 7 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 7 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 7 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 7 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 7 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 7 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 7 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 7 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 7 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 7 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 7 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 7 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 7 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 7 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 7 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 7 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 7 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 7 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 7 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 7 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 7 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 7 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 7 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 7 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 7 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 7 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 7 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 7 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 7 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 7 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 7 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 7 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 7 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 7 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 7 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 7 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 7 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 7 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 7 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 7 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 7 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 7 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 7 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 7 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 7 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 7 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 7 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 7 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -21 7 1 H-1 nu-fission 0.00e+00 0.00e+00 -22 7 1 O-16 nu-fission 0.00e+00 0.00e+00 -23 7 1 B-10 nu-fission 0.00e+00 0.00e+00 -24 7 1 B-11 nu-fission 0.00e+00 0.00e+00 -25 7 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -26 7 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -27 7 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -28 7 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -29 7 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -30 7 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -31 7 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -32 7 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -33 7 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -34 7 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -35 7 1 Si-28 nu-fission 0.00e+00 0.00e+00 -36 7 1 Si-29 nu-fission 0.00e+00 0.00e+00 -37 7 1 Si-30 nu-fission 0.00e+00 0.00e+00 -38 7 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -39 7 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -40 7 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -41 7 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -0 7 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 7 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 7 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 7 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 7 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -5 7 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -6 7 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -7 7 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -8 7 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -9 7 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -10 7 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -11 7 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -12 7 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -13 7 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -14 7 2 Si-28 nu-fission 0.00e+00 0.00e+00 -15 7 2 Si-29 nu-fission 0.00e+00 0.00e+00 -16 7 2 Si-30 nu-fission 0.00e+00 0.00e+00 -17 7 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -18 7 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -19 7 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -20 7 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 8 1 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -22 8 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -23 8 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 8 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 8 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 8 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -27 8 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 8 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 8 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 8 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 8 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 8 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 8 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 8 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 8 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 8 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 8 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 8 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 8 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 8 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -41 8 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 8 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 8 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 8 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 8 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 8 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 8 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 8 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 8 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 8 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 8 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 8 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 8 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 8 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 8 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 8 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 8 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 8 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 8 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 8 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 8 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 8 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 8 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -22 8 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -23 8 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -24 8 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -25 8 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -26 8 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -27 8 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -28 8 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -29 8 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -30 8 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -31 8 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -32 8 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -33 8 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -34 8 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -35 8 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -36 8 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -37 8 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -38 8 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -39 8 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -40 8 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -41 8 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -0 8 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 8 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 8 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 8 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 8 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -5 8 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -6 8 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -7 8 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -8 8 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -9 8 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -10 8 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -11 8 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -12 8 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -13 8 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -14 8 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -15 8 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -16 8 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -17 8 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -18 8 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -19 8 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -20 8 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -63 8 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -64 8 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 8 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 8 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 8 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 8 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 8 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 8 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 8 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 8 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 8 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 8 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 8 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 8 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 8 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 8 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 8 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 8 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -81 8 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 8 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 8 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 8 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 8 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 8 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 8 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 8 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 8 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 8 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 8 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 8 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 8 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 8 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 8 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 8 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 8 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 8 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 8 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 8 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 8 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 8 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 8 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 8 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 8 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 8 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 8 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 8 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 8 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 8 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 8 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 8 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 8 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 8 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 8 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 8 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 8 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 8 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 8 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 8 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 8 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 8 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 8 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 8 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 8 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 8 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 8 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 8 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 8 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 8 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 8 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 8 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 8 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 8 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 8 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 8 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 8 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 8 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 8 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 8 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 8 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 8 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 8 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 8 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 8 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 8 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -21 8 1 H-1 nu-fission 0.00e+00 0.00e+00 -22 8 1 O-16 nu-fission 0.00e+00 0.00e+00 -23 8 1 B-10 nu-fission 0.00e+00 0.00e+00 -24 8 1 B-11 nu-fission 0.00e+00 0.00e+00 -25 8 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -26 8 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -27 8 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -28 8 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -29 8 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -30 8 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -31 8 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -32 8 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -33 8 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -34 8 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -35 8 1 Si-28 nu-fission 0.00e+00 0.00e+00 -36 8 1 Si-29 nu-fission 0.00e+00 0.00e+00 -37 8 1 Si-30 nu-fission 0.00e+00 0.00e+00 -38 8 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -39 8 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -40 8 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -41 8 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -0 8 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 8 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 8 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 8 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 8 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -5 8 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -6 8 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -7 8 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -8 8 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -9 8 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -10 8 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -11 8 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -12 8 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -13 8 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -14 8 2 Si-28 nu-fission 0.00e+00 0.00e+00 -15 8 2 Si-29 nu-fission 0.00e+00 0.00e+00 -16 8 2 Si-30 nu-fission 0.00e+00 0.00e+00 -17 8 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -18 8 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -19 8 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -20 8 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 9 1 H-1 ((total - scatter-1) / flux) 1.51e-01 4.81e-01 -22 9 1 O-16 ((total - scatter-1) / flux) 1.16e-01 1.14e-01 -23 9 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 9 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 9 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 9 1 Fe-56 ((total - scatter-1) / flux) 1.86e-01 2.00e-01 -27 9 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 9 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 9 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 9 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 9 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 9 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 9 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 9 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 9 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 9 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 9 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 9 1 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -39 9 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 9 1 Cr-53 ((total - scatter-1) / flux) 1.47e-01 1.40e-01 -41 9 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 9 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 9 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 9 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 9 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 9 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 9 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 9 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 9 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 9 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 9 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 9 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 9 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 9 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 9 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 9 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 9 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 9 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 9 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 9 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 9 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 9 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 9 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -22 9 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -23 9 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -24 9 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -25 9 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -26 9 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -27 9 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -28 9 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -29 9 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -30 9 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -31 9 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -32 9 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -33 9 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -34 9 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -35 9 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -36 9 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -37 9 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -38 9 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -39 9 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -40 9 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -41 9 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -0 9 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 9 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 9 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 9 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 9 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -5 9 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -6 9 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -7 9 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -8 9 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -9 9 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -10 9 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -11 9 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -12 9 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -13 9 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -14 9 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -15 9 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -16 9 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -17 9 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -18 9 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -19 9 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -20 9 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -63 9 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.51e-01 4.81e-01 -64 9 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.16e-01 1.14e-01 -65 9 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 9 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 9 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 9 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 1.86e-01 2.00e-01 -69 9 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 9 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 9 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 9 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 9 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 9 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 9 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 9 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 9 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 9 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 9 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 9 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -81 9 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 9 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 1.47e-01 1.40e-01 -83 9 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 9 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 9 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 9 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 9 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 9 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 9 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 9 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 9 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 9 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 9 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 9 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 9 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 9 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 9 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 9 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 9 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 9 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 9 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 9 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 9 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 9 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 9 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 9 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 9 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 9 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 9 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 9 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 9 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 9 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 9 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 9 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 9 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 9 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 9 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 9 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 9 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 9 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 9 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 9 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 9 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 9 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 9 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 9 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 9 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 9 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 9 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 9 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 9 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 9 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 9 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 9 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 9 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 9 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 9 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 9 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 9 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 9 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 9 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 9 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 9 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 9 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 9 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 9 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -21 9 1 H-1 nu-fission 0.00e+00 0.00e+00 -22 9 1 O-16 nu-fission 0.00e+00 0.00e+00 -23 9 1 B-10 nu-fission 0.00e+00 0.00e+00 -24 9 1 B-11 nu-fission 0.00e+00 0.00e+00 -25 9 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -26 9 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -27 9 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -28 9 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -29 9 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -30 9 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -31 9 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -32 9 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -33 9 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -34 9 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -35 9 1 Si-28 nu-fission 0.00e+00 0.00e+00 -36 9 1 Si-29 nu-fission 0.00e+00 0.00e+00 -37 9 1 Si-30 nu-fission 0.00e+00 0.00e+00 -38 9 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -39 9 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -40 9 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -41 9 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -0 9 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 9 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 9 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 9 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 9 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -5 9 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -6 9 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -7 9 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -8 9 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -9 9 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -10 9 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -11 9 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -12 9 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -13 9 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -14 9 2 Si-28 nu-fission 0.00e+00 0.00e+00 -15 9 2 Si-29 nu-fission 0.00e+00 0.00e+00 -16 9 2 Si-30 nu-fission 0.00e+00 0.00e+00 -17 9 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -18 9 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -19 9 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -20 9 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 10 1 H-1 ((total - scatter-1) / flux) 1.24e-01 5.41e-01 -22 10 1 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -23 10 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -24 10 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -25 10 1 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -26 10 1 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -27 10 1 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -28 10 1 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -29 10 1 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -30 10 1 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -31 10 1 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -32 10 1 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -33 10 1 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -34 10 1 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -35 10 1 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -36 10 1 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -37 10 1 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -38 10 1 Cr-50 ((total - scatter-1) / flux) 1.12e-01 1.38e-01 -39 10 1 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -40 10 1 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -41 10 1 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 10 2 H-1 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -1 10 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 10 2 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -3 10 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 10 2 Fe-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 10 2 Fe-56 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 10 2 Fe-57 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 10 2 Fe-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 10 2 Ni-58 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -9 10 2 Ni-60 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -10 10 2 Ni-61 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -11 10 2 Ni-62 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 10 2 Ni-64 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 10 2 Mn-55 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -14 10 2 Si-28 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 10 2 Si-29 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 10 2 Si-30 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -17 10 2 Cr-50 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -18 10 2 Cr-52 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -19 10 2 Cr-53 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -20 10 2 Cr-54 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -21 10 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -22 10 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -23 10 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -24 10 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -25 10 1 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -26 10 1 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -27 10 1 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -28 10 1 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -29 10 1 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -30 10 1 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -31 10 1 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -32 10 1 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -33 10 1 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -34 10 1 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -35 10 1 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -36 10 1 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -37 10 1 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -38 10 1 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -39 10 1 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -40 10 1 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -41 10 1 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 -0 10 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 10 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 10 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 10 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 10 2 Fe-54 (nu-fission / flux) 0.00e+00 0.00e+00 -5 10 2 Fe-56 (nu-fission / flux) 0.00e+00 0.00e+00 -6 10 2 Fe-57 (nu-fission / flux) 0.00e+00 0.00e+00 -7 10 2 Fe-58 (nu-fission / flux) 0.00e+00 0.00e+00 -8 10 2 Ni-58 (nu-fission / flux) 0.00e+00 0.00e+00 -9 10 2 Ni-60 (nu-fission / flux) 0.00e+00 0.00e+00 -10 10 2 Ni-61 (nu-fission / flux) 0.00e+00 0.00e+00 -11 10 2 Ni-62 (nu-fission / flux) 0.00e+00 0.00e+00 -12 10 2 Ni-64 (nu-fission / flux) 0.00e+00 0.00e+00 -13 10 2 Mn-55 (nu-fission / flux) 0.00e+00 0.00e+00 -14 10 2 Si-28 (nu-fission / flux) 0.00e+00 0.00e+00 -15 10 2 Si-29 (nu-fission / flux) 0.00e+00 0.00e+00 -16 10 2 Si-30 (nu-fission / flux) 0.00e+00 0.00e+00 -17 10 2 Cr-50 (nu-fission / flux) 0.00e+00 0.00e+00 -18 10 2 Cr-52 (nu-fission / flux) 0.00e+00 0.00e+00 -19 10 2 Cr-53 (nu-fission / flux) 0.00e+00 0.00e+00 -20 10 2 Cr-54 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -63 10 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.24e-01 5.41e-01 -64 10 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -65 10 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -66 10 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -67 10 1 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -68 10 1 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -69 10 1 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -70 10 1 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -71 10 1 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -72 10 1 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -73 10 1 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -74 10 1 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -75 10 1 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -76 10 1 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -77 10 1 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -78 10 1 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -79 10 1 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -80 10 1 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 1.12e-01 1.38e-01 -81 10 1 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -82 10 1 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -83 10 1 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -42 10 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -43 10 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -44 10 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -45 10 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -46 10 1 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -47 10 1 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -48 10 1 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -49 10 1 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -50 10 1 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -51 10 1 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -52 10 1 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -53 10 1 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -54 10 1 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -55 10 1 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -56 10 1 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -57 10 1 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -58 10 1 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -59 10 1 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -60 10 1 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -61 10 1 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -62 10 1 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 10 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 10 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 10 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 10 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 10 2 1 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 10 2 1 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -27 10 2 1 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -28 10 2 1 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -29 10 2 1 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 10 2 1 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 10 2 1 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -32 10 2 1 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 10 2 1 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 10 2 1 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -35 10 2 1 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -36 10 2 1 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -37 10 2 1 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -38 10 2 1 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -39 10 2 1 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -40 10 2 1 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -41 10 2 1 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 10 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -1 10 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 10 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 10 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 10 2 2 Fe-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 10 2 2 Fe-56 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 10 2 2 Fe-57 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 10 2 2 Fe-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 10 2 2 Ni-58 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 10 2 2 Ni-60 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 10 2 2 Ni-61 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 10 2 2 Ni-62 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 10 2 2 Ni-64 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 10 2 2 Mn-55 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 10 2 2 Si-28 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 10 2 2 Si-29 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 10 2 2 Si-30 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 10 2 2 Cr-50 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 10 2 2 Cr-52 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -19 10 2 2 Cr-53 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 10 2 2 Cr-54 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -21 10 1 H-1 nu-fission 0.00e+00 0.00e+00 -22 10 1 O-16 nu-fission 0.00e+00 0.00e+00 -23 10 1 B-10 nu-fission 0.00e+00 0.00e+00 -24 10 1 B-11 nu-fission 0.00e+00 0.00e+00 -25 10 1 Fe-54 nu-fission 0.00e+00 0.00e+00 -26 10 1 Fe-56 nu-fission 0.00e+00 0.00e+00 -27 10 1 Fe-57 nu-fission 0.00e+00 0.00e+00 -28 10 1 Fe-58 nu-fission 0.00e+00 0.00e+00 -29 10 1 Ni-58 nu-fission 0.00e+00 0.00e+00 -30 10 1 Ni-60 nu-fission 0.00e+00 0.00e+00 -31 10 1 Ni-61 nu-fission 0.00e+00 0.00e+00 -32 10 1 Ni-62 nu-fission 0.00e+00 0.00e+00 -33 10 1 Ni-64 nu-fission 0.00e+00 0.00e+00 -34 10 1 Mn-55 nu-fission 0.00e+00 0.00e+00 -35 10 1 Si-28 nu-fission 0.00e+00 0.00e+00 -36 10 1 Si-29 nu-fission 0.00e+00 0.00e+00 -37 10 1 Si-30 nu-fission 0.00e+00 0.00e+00 -38 10 1 Cr-50 nu-fission 0.00e+00 0.00e+00 -39 10 1 Cr-52 nu-fission 0.00e+00 0.00e+00 -40 10 1 Cr-53 nu-fission 0.00e+00 0.00e+00 -41 10 1 Cr-54 nu-fission 0.00e+00 0.00e+00 -0 10 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 10 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 10 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 10 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 10 2 Fe-54 nu-fission 0.00e+00 0.00e+00 -5 10 2 Fe-56 nu-fission 0.00e+00 0.00e+00 -6 10 2 Fe-57 nu-fission 0.00e+00 0.00e+00 -7 10 2 Fe-58 nu-fission 0.00e+00 0.00e+00 -8 10 2 Ni-58 nu-fission 0.00e+00 0.00e+00 -9 10 2 Ni-60 nu-fission 0.00e+00 0.00e+00 -10 10 2 Ni-61 nu-fission 0.00e+00 0.00e+00 -11 10 2 Ni-62 nu-fission 0.00e+00 0.00e+00 -12 10 2 Ni-64 nu-fission 0.00e+00 0.00e+00 -13 10 2 Mn-55 nu-fission 0.00e+00 0.00e+00 -14 10 2 Si-28 nu-fission 0.00e+00 0.00e+00 -15 10 2 Si-29 nu-fission 0.00e+00 0.00e+00 -16 10 2 Si-30 nu-fission 0.00e+00 0.00e+00 -17 10 2 Cr-50 nu-fission 0.00e+00 0.00e+00 -18 10 2 Cr-52 nu-fission 0.00e+00 0.00e+00 -19 10 2 Cr-53 nu-fission 0.00e+00 0.00e+00 -20 10 2 Cr-54 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -9 11 1 H-1 ((total - scatter-1) / flux) 1.31e-01 4.76e-01 -10 11 1 O-16 ((total - scatter-1) / flux) 2.87e-02 4.30e-02 -11 11 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 11 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 11 1 Zr-90 ((total - scatter-1) / flux) 2.20e-02 4.00e-02 -14 11 1 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 11 1 Zr-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -16 11 1 Zr-94 ((total - scatter-1) / flux) 4.19e-03 8.73e-02 -17 11 1 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -0 11 2 H-1 ((total - scatter-1) / flux) 6.87e-01 1.24e+00 -1 11 2 O-16 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -2 11 2 B-10 ((total - scatter-1) / flux) 4.29e-02 6.07e-02 -3 11 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 11 2 Zr-90 ((total - scatter-1) / flux) 3.96e-02 1.05e-01 -5 11 2 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -6 11 2 Zr-92 ((total - scatter-1) / flux) 8.42e-02 1.03e-01 -7 11 2 Zr-94 ((total - scatter-1) / flux) 9.20e-02 1.26e-01 -8 11 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -9 11 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -10 11 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -11 11 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -12 11 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -13 11 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -14 11 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -15 11 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -16 11 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -17 11 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 -0 11 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 11 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 11 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 11 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 11 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -5 11 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -6 11 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -7 11 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -8 11 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -27 11 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 9.96e-02 4.43e-01 -28 11 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 2.87e-02 4.30e-02 -29 11 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 11 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 11 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 2.20e-02 4.00e-02 -32 11 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 11 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -34 11 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.19e-03 8.73e-02 -35 11 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -18 11 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 3.19e-02 4.51e-02 -19 11 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 11 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 11 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 11 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 11 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 11 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 11 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 11 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 11 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 11 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 11 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 11 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 11 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 11 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 11 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 11 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 11 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 11 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 6.87e-01 1.24e+00 -1 11 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -2 11 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 11 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 11 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 3.96e-02 1.05e-01 -5 11 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -6 11 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 8.42e-02 1.03e-01 -7 11 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 9.20e-02 1.26e-01 -8 11 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -9 11 1 H-1 nu-fission 0.00e+00 0.00e+00 -10 11 1 O-16 nu-fission 0.00e+00 0.00e+00 -11 11 1 B-10 nu-fission 0.00e+00 0.00e+00 -12 11 1 B-11 nu-fission 0.00e+00 0.00e+00 -13 11 1 Zr-90 nu-fission 0.00e+00 0.00e+00 -14 11 1 Zr-91 nu-fission 0.00e+00 0.00e+00 -15 11 1 Zr-92 nu-fission 0.00e+00 0.00e+00 -16 11 1 Zr-94 nu-fission 0.00e+00 0.00e+00 -17 11 1 Zr-96 nu-fission 0.00e+00 0.00e+00 -0 11 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 11 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 11 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 11 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 11 2 Zr-90 nu-fission 0.00e+00 0.00e+00 -5 11 2 Zr-91 nu-fission 0.00e+00 0.00e+00 -6 11 2 Zr-92 nu-fission 0.00e+00 0.00e+00 -7 11 2 Zr-94 nu-fission 0.00e+00 0.00e+00 -8 11 2 Zr-96 nu-fission 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -9 12 1 H-1 ((total - scatter-1) / flux) 9.89e-02 1.79e-01 -10 12 1 O-16 ((total - scatter-1) / flux) 1.33e-02 2.04e-02 -11 12 1 B-10 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -12 12 1 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -13 12 1 Zr-90 ((total - scatter-1) / flux) 9.00e-02 7.55e-02 -14 12 1 Zr-91 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -15 12 1 Zr-92 ((total - scatter-1) / flux) 3.50e-03 1.70e-02 -16 12 1 Zr-94 ((total - scatter-1) / flux) 4.85e-03 1.63e-02 -17 12 1 Zr-96 ((total - scatter-1) / flux) 2.73e-03 1.75e-02 -0 12 2 H-1 ((total - scatter-1) / flux) 1.26e+00 1.98e+00 -1 12 2 O-16 ((total - scatter-1) / flux) 7.92e-02 1.05e-01 -2 12 2 B-10 ((total - scatter-1) / flux) 1.69e-02 2.39e-02 -3 12 2 B-11 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -4 12 2 Zr-90 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -5 12 2 Zr-91 ((total - scatter-1) / flux) 3.32e-02 4.07e-02 -6 12 2 Zr-92 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -7 12 2 Zr-94 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 -8 12 2 Zr-96 ((total - scatter-1) / flux) 0.00e+00 0.00e+00 material group in nuclide score mean std. dev. -9 12 1 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -10 12 1 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -11 12 1 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -12 12 1 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -13 12 1 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -14 12 1 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -15 12 1 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -16 12 1 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -17 12 1 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 -0 12 2 H-1 (nu-fission / flux) 0.00e+00 0.00e+00 -1 12 2 O-16 (nu-fission / flux) 0.00e+00 0.00e+00 -2 12 2 B-10 (nu-fission / flux) 0.00e+00 0.00e+00 -3 12 2 B-11 (nu-fission / flux) 0.00e+00 0.00e+00 -4 12 2 Zr-90 (nu-fission / flux) 0.00e+00 0.00e+00 -5 12 2 Zr-91 (nu-fission / flux) 0.00e+00 0.00e+00 -6 12 2 Zr-92 (nu-fission / flux) 0.00e+00 0.00e+00 -7 12 2 Zr-94 (nu-fission / flux) 0.00e+00 0.00e+00 -8 12 2 Zr-96 (nu-fission / flux) 0.00e+00 0.00e+00 material group in group out nuclide score mean std. dev. -27 12 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 7.17e-02 1.68e-01 -28 12 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 1.33e-02 2.04e-02 -29 12 1 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -30 12 1 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -31 12 1 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 9.00e-02 7.55e-02 -32 12 1 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -33 12 1 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 3.50e-03 1.70e-02 -34 12 1 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 4.85e-03 1.63e-02 -35 12 1 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 2.73e-03 1.75e-02 -18 12 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 2.72e-02 2.96e-02 -19 12 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -20 12 1 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -21 12 1 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -22 12 1 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -23 12 1 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -24 12 1 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -25 12 1 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -26 12 1 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -9 12 2 1 H-1 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -10 12 2 1 O-16 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -11 12 2 1 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -12 12 2 1 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -13 12 2 1 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -14 12 2 1 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -15 12 2 1 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -16 12 2 1 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -17 12 2 1 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -0 12 2 2 H-1 ((nu-scatter-0 - scatter-1) / flux) 1.24e+00 1.96e+00 -1 12 2 2 O-16 ((nu-scatter-0 - scatter-1) / flux) 7.92e-02 1.05e-01 -2 12 2 2 B-10 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -3 12 2 2 B-11 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -4 12 2 2 Zr-90 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -5 12 2 2 Zr-91 ((nu-scatter-0 - scatter-1) / flux) 3.32e-02 4.07e-02 -6 12 2 2 Zr-92 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -7 12 2 2 Zr-94 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 -8 12 2 2 Zr-96 ((nu-scatter-0 - scatter-1) / flux) 0.00e+00 0.00e+00 material group out nuclide score mean std. dev. -9 12 1 H-1 nu-fission 0.00e+00 0.00e+00 -10 12 1 O-16 nu-fission 0.00e+00 0.00e+00 -11 12 1 B-10 nu-fission 0.00e+00 0.00e+00 -12 12 1 B-11 nu-fission 0.00e+00 0.00e+00 -13 12 1 Zr-90 nu-fission 0.00e+00 0.00e+00 -14 12 1 Zr-91 nu-fission 0.00e+00 0.00e+00 -15 12 1 Zr-92 nu-fission 0.00e+00 0.00e+00 -16 12 1 Zr-94 nu-fission 0.00e+00 0.00e+00 -17 12 1 Zr-96 nu-fission 0.00e+00 0.00e+00 -0 12 2 H-1 nu-fission 0.00e+00 0.00e+00 -1 12 2 O-16 nu-fission 0.00e+00 0.00e+00 -2 12 2 B-10 nu-fission 0.00e+00 0.00e+00 -3 12 2 B-11 nu-fission 0.00e+00 0.00e+00 -4 12 2 Zr-90 nu-fission 0.00e+00 0.00e+00 -5 12 2 Zr-91 nu-fission 0.00e+00 0.00e+00 -6 12 2 Zr-92 nu-fission 0.00e+00 0.00e+00 -7 12 2 Zr-94 nu-fission 0.00e+00 0.00e+00 -8 12 2 Zr-96 nu-fission 0.00e+00 0.00e+00 \ No newline at end of file + material group in nuclide mean std. dev. +34 1 1 U-234 0.000173 0.000173 +35 1 1 U-235 0.010677 0.001889 +36 1 1 U-236 0.002390 0.001055 +37 1 1 U-238 0.213680 0.013272 +38 1 1 Np-237 0.000000 0.000000 +39 1 1 Pu-238 0.000000 0.000000 +40 1 1 Pu-239 0.002911 0.000639 +41 1 1 Pu-240 0.004426 0.000806 +42 1 1 Pu-241 0.000690 0.000387 +43 1 1 Pu-242 0.000000 0.000000 +44 1 1 Am-241 0.000173 0.000173 +45 1 1 Am-242m 0.000000 0.000000 +46 1 1 Am-243 0.000000 0.000000 +47 1 1 Cm-242 0.000000 0.000000 +48 1 1 Cm-243 0.000000 0.000000 +49 1 1 Cm-244 0.000000 0.000000 +50 1 1 Cm-245 0.000000 0.000000 +51 1 1 Mo-95 0.000000 0.000000 +52 1 1 Tc-99 0.000173 0.000173 +53 1 1 Ru-101 0.000238 0.000254 +54 1 1 Ru-103 0.000002 0.000243 +55 1 1 Ag-109 0.000000 0.000000 +56 1 1 Xe-135 0.000000 0.000000 +57 1 1 Cs-133 0.000347 0.000213 +58 1 1 Nd-143 0.000447 0.000292 +59 1 1 Nd-145 0.000564 0.000294 +60 1 1 Sm-147 0.000000 0.000000 +61 1 1 Sm-149 0.000000 0.000000 +62 1 1 Sm-150 0.000472 0.000239 +63 1 1 Sm-151 0.000000 0.000000 +64 1 1 Sm-152 0.000492 0.000352 +65 1 1 Eu-153 0.000173 0.000173 +66 1 1 Gd-155 0.000000 0.000000 +67 1 1 O-16 0.134715 0.009801 +0 1 2 U-234 0.000000 0.000000 +1 1 2 U-235 0.199907 0.007776 +2 1 2 U-236 0.001501 0.002037 +3 1 2 U-238 0.255355 0.029743 +4 1 2 Np-237 0.000000 0.000000 +5 1 2 Pu-238 0.000000 0.000000 +6 1 2 Pu-239 0.160378 0.011366 +7 1 2 Pu-240 0.007920 0.003710 +8 1 2 Pu-241 0.017820 0.003733 +9 1 2 Pu-242 0.000000 0.000000 +10 1 2 Am-241 0.000000 0.000000 +11 1 2 Am-242m 0.000000 0.000000 +12 1 2 Am-243 0.000000 0.000000 +13 1 2 Cm-242 0.000000 0.000000 +14 1 2 Cm-243 0.000000 0.000000 +15 1 2 Cm-244 0.000000 0.000000 +16 1 2 Cm-245 0.000000 0.000000 +17 1 2 Mo-95 0.000000 0.000000 +18 1 2 Tc-99 0.000000 0.000000 +19 1 2 Ru-101 0.000000 0.000000 +20 1 2 Ru-103 0.000000 0.000000 +21 1 2 Ag-109 0.000000 0.000000 +22 1 2 Xe-135 0.013860 0.003976 +23 1 2 Cs-133 0.000000 0.000000 +24 1 2 Nd-143 0.003960 0.002427 +25 1 2 Nd-145 0.000000 0.000000 +26 1 2 Sm-147 0.000000 0.000000 +27 1 2 Sm-149 0.001980 0.001981 +28 1 2 Sm-150 0.000000 0.000000 +29 1 2 Sm-151 0.001980 0.001981 +30 1 2 Sm-152 0.000000 0.000000 +31 1 2 Eu-153 0.000000 0.000000 +32 1 2 Gd-155 0.000000 0.000000 +33 1 2 O-16 0.196946 0.014729 material group in nuclide mean std. dev. +34 1 1 U-234 7.274440e-06 4.419477e-07 +35 1 1 U-235 9.587803e-03 5.936922e-04 +36 1 1 U-236 7.566099e-05 7.523935e-06 +37 1 1 U-238 7.178367e-03 6.505680e-04 +38 1 1 Np-237 1.315682e-05 8.036501e-07 +39 1 1 Pu-238 7.746151e-06 3.992835e-07 +40 1 1 Pu-239 3.805294e-03 3.637600e-04 +41 1 1 Pu-240 6.941319e-05 4.729737e-06 +42 1 1 Pu-241 1.033844e-03 9.083913e-05 +43 1 1 Pu-242 5.995332e-06 3.821721e-07 +44 1 1 Am-241 1.148585e-06 8.271648e-08 +45 1 1 Am-242m 1.100215e-06 6.159956e-08 +46 1 1 Am-243 8.323826e-07 5.841792e-08 +47 1 1 Cm-242 5.088970e-07 5.258007e-08 +48 1 1 Cm-243 2.245435e-07 1.459025e-08 +49 1 1 Cm-244 2.993206e-07 2.746129e-08 +50 1 1 Cm-245 3.063611e-07 3.057751e-08 +51 1 1 Mo-95 0.000000e+00 0.000000e+00 +52 1 1 Tc-99 0.000000e+00 0.000000e+00 +53 1 1 Ru-101 0.000000e+00 0.000000e+00 +54 1 1 Ru-103 0.000000e+00 0.000000e+00 +55 1 1 Ag-109 0.000000e+00 0.000000e+00 +56 1 1 Xe-135 0.000000e+00 0.000000e+00 +57 1 1 Cs-133 0.000000e+00 0.000000e+00 +58 1 1 Nd-143 0.000000e+00 0.000000e+00 +59 1 1 Nd-145 0.000000e+00 0.000000e+00 +60 1 1 Sm-147 0.000000e+00 0.000000e+00 +61 1 1 Sm-149 0.000000e+00 0.000000e+00 +62 1 1 Sm-150 0.000000e+00 0.000000e+00 +63 1 1 Sm-151 0.000000e+00 0.000000e+00 +64 1 1 Sm-152 0.000000e+00 0.000000e+00 +65 1 1 Eu-153 0.000000e+00 0.000000e+00 +66 1 1 Gd-155 0.000000e+00 0.000000e+00 +67 1 1 O-16 0.000000e+00 0.000000e+00 +0 1 2 U-234 4.408576e-07 2.828309e-08 +1 1 2 U-235 3.768094e-01 2.445671e-02 +2 1 2 U-236 6.097538e-06 3.733038e-07 +3 1 2 U-238 5.353074e-07 3.310544e-08 +4 1 2 Np-237 2.702971e-07 2.098939e-08 +5 1 2 Pu-238 3.463109e-05 2.638394e-06 +6 1 2 Pu-239 2.889643e-01 1.376004e-02 +7 1 2 Pu-240 4.533642e-06 2.544289e-07 +8 1 2 Pu-241 4.809366e-02 2.778345e-03 +9 1 2 Pu-242 8.715325e-08 5.460893e-09 +10 1 2 Am-241 4.611736e-06 2.155039e-07 +11 1 2 Am-242m 1.428047e-04 8.436437e-06 +12 1 2 Am-243 7.883895e-08 4.734503e-09 +13 1 2 Cm-242 9.731025e-07 6.143750e-08 +14 1 2 Cm-243 1.825830e-06 1.074849e-07 +15 1 2 Cm-244 1.581823e-07 9.938064e-09 +16 1 2 Cm-245 1.213386e-05 8.812019e-07 +17 1 2 Mo-95 0.000000e+00 0.000000e+00 +18 1 2 Tc-99 0.000000e+00 0.000000e+00 +19 1 2 Ru-101 0.000000e+00 0.000000e+00 +20 1 2 Ru-103 0.000000e+00 0.000000e+00 +21 1 2 Ag-109 0.000000e+00 0.000000e+00 +22 1 2 Xe-135 0.000000e+00 0.000000e+00 +23 1 2 Cs-133 0.000000e+00 0.000000e+00 +24 1 2 Nd-143 0.000000e+00 0.000000e+00 +25 1 2 Nd-145 0.000000e+00 0.000000e+00 +26 1 2 Sm-147 0.000000e+00 0.000000e+00 +27 1 2 Sm-149 0.000000e+00 0.000000e+00 +28 1 2 Sm-150 0.000000e+00 0.000000e+00 +29 1 2 Sm-151 0.000000e+00 0.000000e+00 +30 1 2 Sm-152 0.000000e+00 0.000000e+00 +31 1 2 Eu-153 0.000000e+00 0.000000e+00 +32 1 2 Gd-155 0.000000e+00 0.000000e+00 +33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide moment mean std. dev. moment +102 1 1 1 U-234 P0 0.000000 0.000000 P0 +103 1 1 1 U-235 P0 0.003226 0.001139 P0 +104 1 1 1 U-236 P0 0.001697 0.000923 P0 +105 1 1 1 U-238 P0 0.194620 0.013297 P0 +106 1 1 1 Np-237 P0 0.000000 0.000000 P0 +107 1 1 1 Pu-238 P0 0.000000 0.000000 P0 +108 1 1 1 Pu-239 P0 0.001005 0.000477 P0 +109 1 1 1 Pu-240 P0 0.001307 0.000295 P0 +110 1 1 1 Pu-241 P0 0.000344 0.000244 P0 +111 1 1 1 Pu-242 P0 0.000000 0.000000 P0 +112 1 1 1 Am-241 P0 0.000000 0.000000 P0 +113 1 1 1 Am-242m P0 0.000000 0.000000 P0 +114 1 1 1 Am-243 P0 0.000000 0.000000 P0 +115 1 1 1 Cm-242 P0 0.000000 0.000000 P0 +116 1 1 1 Cm-243 P0 0.000000 0.000000 P0 +117 1 1 1 Cm-244 P0 0.000000 0.000000 P0 +118 1 1 1 Cm-245 P0 0.000000 0.000000 P0 +119 1 1 1 Mo-95 P0 0.000000 0.000000 P0 +120 1 1 1 Tc-99 P0 0.000000 0.000000 P0 +121 1 1 1 Ru-101 P0 0.000238 0.000254 P0 +122 1 1 1 Ru-103 P0 0.000002 0.000243 P0 +123 1 1 1 Ag-109 P0 0.000000 0.000000 P0 +124 1 1 1 Xe-135 P0 0.000000 0.000000 P0 +125 1 1 1 Cs-133 P0 0.000000 0.000000 P0 +126 1 1 1 Nd-143 P0 0.000447 0.000292 P0 +127 1 1 1 Nd-145 P0 0.000564 0.000294 P0 +128 1 1 1 Sm-147 P0 0.000000 0.000000 P0 +129 1 1 1 Sm-149 P0 0.000000 0.000000 P0 +130 1 1 1 Sm-150 P0 0.000299 0.000238 P0 +131 1 1 1 Sm-151 P0 0.000000 0.000000 P0 +132 1 1 1 Sm-152 P0 0.000492 0.000352 P0 +133 1 1 1 Eu-153 P0 0.000000 0.000000 P0 +134 1 1 1 Gd-155 P0 0.000000 0.000000 P0 +135 1 1 1 O-16 P0 0.133156 0.009821 P0 +68 1 1 2 U-234 P0 0.000000 0.000000 P0 +69 1 1 2 U-235 P0 0.000000 0.000000 P0 +70 1 1 2 U-236 P0 0.000000 0.000000 P0 +71 1 1 2 U-238 P0 0.000173 0.000173 P0 +72 1 1 2 Np-237 P0 0.000000 0.000000 P0 +73 1 1 2 Pu-238 P0 0.000000 0.000000 P0 +74 1 1 2 Pu-239 P0 0.000000 0.000000 P0 +75 1 1 2 Pu-240 P0 0.000000 0.000000 P0 +76 1 1 2 Pu-241 P0 0.000000 0.000000 P0 +77 1 1 2 Pu-242 P0 0.000000 0.000000 P0 +78 1 1 2 Am-241 P0 0.000000 0.000000 P0 +79 1 1 2 Am-242m P0 0.000000 0.000000 P0 +80 1 1 2 Am-243 P0 0.000000 0.000000 P0 +81 1 1 2 Cm-242 P0 0.000000 0.000000 P0 +82 1 1 2 Cm-243 P0 0.000000 0.000000 P0 +83 1 1 2 Cm-244 P0 0.000000 0.000000 P0 +84 1 1 2 Cm-245 P0 0.000000 0.000000 P0 +85 1 1 2 Mo-95 P0 0.000000 0.000000 P0 +86 1 1 2 Tc-99 P0 0.000000 0.000000 P0 +87 1 1 2 Ru-101 P0 0.000000 0.000000 P0 +88 1 1 2 Ru-103 P0 0.000000 0.000000 P0 +89 1 1 2 Ag-109 P0 0.000000 0.000000 P0 +90 1 1 2 Xe-135 P0 0.000000 0.000000 P0 +91 1 1 2 Cs-133 P0 0.000000 0.000000 P0 +92 1 1 2 Nd-143 P0 0.000000 0.000000 P0 +93 1 1 2 Nd-145 P0 0.000000 0.000000 P0 +94 1 1 2 Sm-147 P0 0.000000 0.000000 P0 +95 1 1 2 Sm-149 P0 0.000000 0.000000 P0 +96 1 1 2 Sm-150 P0 0.000000 0.000000 P0 +97 1 1 2 Sm-151 P0 0.000000 0.000000 P0 +98 1 1 2 Sm-152 P0 0.000000 0.000000 P0 +99 1 1 2 Eu-153 P0 0.000000 0.000000 P0 +100 1 1 2 Gd-155 P0 0.000000 0.000000 P0 +101 1 1 2 O-16 P0 0.001386 0.000446 P0 +34 1 2 1 U-234 P0 0.000000 0.000000 P0 +35 1 2 1 U-235 P0 0.000000 0.000000 P0 +36 1 2 1 U-236 P0 0.000000 0.000000 P0 +37 1 2 1 U-238 P0 0.000000 0.000000 P0 +38 1 2 1 Np-237 P0 0.000000 0.000000 P0 +39 1 2 1 Pu-238 P0 0.000000 0.000000 P0 +40 1 2 1 Pu-239 P0 0.000000 0.000000 P0 +41 1 2 1 Pu-240 P0 0.000000 0.000000 P0 +42 1 2 1 Pu-241 P0 0.000000 0.000000 P0 +43 1 2 1 Pu-242 P0 0.000000 0.000000 P0 +44 1 2 1 Am-241 P0 0.000000 0.000000 P0 +45 1 2 1 Am-242m P0 0.000000 0.000000 P0 +46 1 2 1 Am-243 P0 0.000000 0.000000 P0 +47 1 2 1 Cm-242 P0 0.000000 0.000000 P0 +48 1 2 1 Cm-243 P0 0.000000 0.000000 P0 +49 1 2 1 Cm-244 P0 0.000000 0.000000 P0 +50 1 2 1 Cm-245 P0 0.000000 0.000000 P0 +51 1 2 1 Mo-95 P0 0.000000 0.000000 P0 +52 1 2 1 Tc-99 P0 0.000000 0.000000 P0 +53 1 2 1 Ru-101 P0 0.000000 0.000000 P0 +54 1 2 1 Ru-103 P0 0.000000 0.000000 P0 +55 1 2 1 Ag-109 P0 0.000000 0.000000 P0 +56 1 2 1 Xe-135 P0 0.000000 0.000000 P0 +57 1 2 1 Cs-133 P0 0.000000 0.000000 P0 +58 1 2 1 Nd-143 P0 0.000000 0.000000 P0 +59 1 2 1 Nd-145 P0 0.000000 0.000000 P0 +60 1 2 1 Sm-147 P0 0.000000 0.000000 P0 +61 1 2 1 Sm-149 P0 0.000000 0.000000 P0 +62 1 2 1 Sm-150 P0 0.000000 0.000000 P0 +63 1 2 1 Sm-151 P0 0.000000 0.000000 P0 +64 1 2 1 Sm-152 P0 0.000000 0.000000 P0 +65 1 2 1 Eu-153 P0 0.000000 0.000000 P0 +66 1 2 1 Gd-155 P0 0.000000 0.000000 P0 +67 1 2 1 O-16 P0 0.000000 0.000000 P0 +0 1 2 2 U-234 P0 0.000000 0.000000 P0 +1 1 2 2 U-235 P0 0.003889 0.003962 P0 +2 1 2 2 U-236 P0 0.001501 0.002037 P0 +3 1 2 2 U-238 P0 0.219715 0.025984 P0 +4 1 2 2 Np-237 P0 0.000000 0.000000 P0 +5 1 2 2 Pu-238 P0 0.000000 0.000000 P0 +6 1 2 2 Pu-239 P0 0.000000 0.000000 P0 +7 1 2 2 Pu-240 P0 0.000000 0.000000 P0 +8 1 2 2 Pu-241 P0 0.000000 0.000000 P0 +9 1 2 2 Pu-242 P0 0.000000 0.000000 P0 +10 1 2 2 Am-241 P0 0.000000 0.000000 P0 +11 1 2 2 Am-242m P0 0.000000 0.000000 P0 +12 1 2 2 Am-243 P0 0.000000 0.000000 P0 +13 1 2 2 Cm-242 P0 0.000000 0.000000 P0 +14 1 2 2 Cm-243 P0 0.000000 0.000000 P0 +15 1 2 2 Cm-244 P0 0.000000 0.000000 P0 +16 1 2 2 Cm-245 P0 0.000000 0.000000 P0 +17 1 2 2 Mo-95 P0 0.000000 0.000000 P0 +18 1 2 2 Tc-99 P0 0.000000 0.000000 P0 +19 1 2 2 Ru-101 P0 0.000000 0.000000 P0 +20 1 2 2 Ru-103 P0 0.000000 0.000000 P0 +21 1 2 2 Ag-109 P0 0.000000 0.000000 P0 +22 1 2 2 Xe-135 P0 0.000000 0.000000 P0 +23 1 2 2 Cs-133 P0 0.000000 0.000000 P0 +24 1 2 2 Nd-143 P0 0.000000 0.000000 P0 +25 1 2 2 Nd-145 P0 0.000000 0.000000 P0 +26 1 2 2 Sm-147 P0 0.000000 0.000000 P0 +27 1 2 2 Sm-149 P0 0.000000 0.000000 P0 +28 1 2 2 Sm-150 P0 0.000000 0.000000 P0 +29 1 2 2 Sm-151 P0 0.000000 0.000000 P0 +30 1 2 2 Sm-152 P0 0.000000 0.000000 P0 +31 1 2 2 Eu-153 P0 0.000000 0.000000 P0 +32 1 2 2 Gd-155 P0 0.000000 0.000000 P0 +33 1 2 2 O-16 P0 0.196946 0.014729 P0 material group out nuclide mean std. dev. +34 1 1 U-234 0 0.000000 +35 1 1 U-235 1 0.066362 +36 1 1 U-236 0 0.000000 +37 1 1 U-238 1 0.093082 +38 1 1 Np-237 0 0.000000 +39 1 1 Pu-238 0 0.000000 +40 1 1 Pu-239 1 0.104567 +41 1 1 Pu-240 0 0.000000 +42 1 1 Pu-241 1 0.263696 +43 1 1 Pu-242 0 0.000000 +44 1 1 Am-241 0 0.000000 +45 1 1 Am-242m 0 0.000000 +46 1 1 Am-243 0 0.000000 +47 1 1 Cm-242 0 0.000000 +48 1 1 Cm-243 0 0.000000 +49 1 1 Cm-244 0 0.000000 +50 1 1 Cm-245 0 0.000000 +51 1 1 Mo-95 0 0.000000 +52 1 1 Tc-99 0 0.000000 +53 1 1 Ru-101 0 0.000000 +54 1 1 Ru-103 0 0.000000 +55 1 1 Ag-109 0 0.000000 +56 1 1 Xe-135 0 0.000000 +57 1 1 Cs-133 0 0.000000 +58 1 1 Nd-143 0 0.000000 +59 1 1 Nd-145 0 0.000000 +60 1 1 Sm-147 0 0.000000 +61 1 1 Sm-149 0 0.000000 +62 1 1 Sm-150 0 0.000000 +63 1 1 Sm-151 0 0.000000 +64 1 1 Sm-152 0 0.000000 +65 1 1 Eu-153 0 0.000000 +66 1 1 Gd-155 0 0.000000 +67 1 1 O-16 0 0.000000 +0 1 2 U-234 0 0.000000 +1 1 2 U-235 0 0.000000 +2 1 2 U-236 0 0.000000 +3 1 2 U-238 0 0.000000 +4 1 2 Np-237 0 0.000000 +5 1 2 Pu-238 0 0.000000 +6 1 2 Pu-239 0 0.000000 +7 1 2 Pu-240 0 0.000000 +8 1 2 Pu-241 0 0.000000 +9 1 2 Pu-242 0 0.000000 +10 1 2 Am-241 0 0.000000 +11 1 2 Am-242m 0 0.000000 +12 1 2 Am-243 0 0.000000 +13 1 2 Cm-242 0 0.000000 +14 1 2 Cm-243 0 0.000000 +15 1 2 Cm-244 0 0.000000 +16 1 2 Cm-245 0 0.000000 +17 1 2 Mo-95 0 0.000000 +18 1 2 Tc-99 0 0.000000 +19 1 2 Ru-101 0 0.000000 +20 1 2 Ru-103 0 0.000000 +21 1 2 Ag-109 0 0.000000 +22 1 2 Xe-135 0 0.000000 +23 1 2 Cs-133 0 0.000000 +24 1 2 Nd-143 0 0.000000 +25 1 2 Nd-145 0 0.000000 +26 1 2 Sm-147 0 0.000000 +27 1 2 Sm-149 0 0.000000 +28 1 2 Sm-150 0 0.000000 +29 1 2 Sm-151 0 0.000000 +30 1 2 Sm-152 0 0.000000 +31 1 2 Eu-153 0 0.000000 +32 1 2 Gd-155 0 0.000000 +33 1 2 O-16 0 0.000000 material group in nuclide mean std. dev. +5 2 1 Zr-90 0.104734 0.008915 +6 2 1 Zr-91 0.036155 0.003735 +7 2 1 Zr-92 0.042422 0.003029 +8 2 1 Zr-94 0.046148 0.006251 +9 2 1 Zr-96 0.007794 0.001536 +0 2 2 Zr-90 0.121688 0.034934 +1 2 2 Zr-91 0.061792 0.024317 +2 2 2 Zr-92 0.041633 0.016323 +3 2 2 Zr-94 0.060818 0.021483 +4 2 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. +5 2 1 Zr-90 0 0 +6 2 1 Zr-91 0 0 +7 2 1 Zr-92 0 0 +8 2 1 Zr-94 0 0 +9 2 1 Zr-96 0 0 +0 2 2 Zr-90 0 0 +1 2 2 Zr-91 0 0 +2 2 2 Zr-92 0 0 +3 2 2 Zr-94 0 0 +4 2 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +15 2 1 1 Zr-90 P0 0.104734 0.008915 P0 +16 2 1 1 Zr-91 P0 0.036155 0.003735 P0 +17 2 1 1 Zr-92 P0 0.042422 0.003029 P0 +18 2 1 1 Zr-94 P0 0.046148 0.006251 P0 +19 2 1 1 Zr-96 P0 0.007794 0.001536 P0 +10 2 1 2 Zr-90 P0 0.000000 0.000000 P0 +11 2 1 2 Zr-91 P0 0.000000 0.000000 P0 +12 2 1 2 Zr-92 P0 0.000000 0.000000 P0 +13 2 1 2 Zr-94 P0 0.000000 0.000000 P0 +14 2 1 2 Zr-96 P0 0.000000 0.000000 P0 +5 2 2 1 Zr-90 P0 0.000000 0.000000 P0 +6 2 2 1 Zr-91 P0 0.000000 0.000000 P0 +7 2 2 1 Zr-92 P0 0.000000 0.000000 P0 +8 2 2 1 Zr-94 P0 0.000000 0.000000 P0 +9 2 2 1 Zr-96 P0 0.000000 0.000000 P0 +0 2 2 2 Zr-90 P0 0.121688 0.034934 P0 +1 2 2 2 Zr-91 P0 0.061792 0.024317 P0 +2 2 2 2 Zr-92 P0 0.041633 0.016323 P0 +3 2 2 2 Zr-94 P0 0.060818 0.021483 P0 +4 2 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +5 2 1 Zr-90 0 0 +6 2 1 Zr-91 0 0 +7 2 1 Zr-92 0 0 +8 2 1 Zr-94 0 0 +9 2 1 Zr-96 0 0 +0 2 2 Zr-90 0 0 +1 2 2 Zr-91 0 0 +2 2 2 Zr-92 0 0 +3 2 2 Zr-94 0 0 +4 2 2 Zr-96 0 0 material group in nuclide mean std. dev. +4 3 1 H-1 0.207103 0.023028 +5 3 1 O-16 0.079282 0.005197 +6 3 1 B-10 0.000521 0.000244 +7 3 1 B-11 0.000000 0.000000 +0 3 2 H-1 1.283344 0.250946 +1 3 2 O-16 0.085363 0.014001 +2 3 2 B-10 0.049249 0.008232 +3 3 2 B-11 0.000195 0.001527 material group in nuclide mean std. dev. +4 3 1 H-1 0 0 +5 3 1 O-16 0 0 +6 3 1 B-10 0 0 +7 3 1 B-11 0 0 +0 3 2 H-1 0 0 +1 3 2 O-16 0 0 +2 3 2 B-10 0 0 +3 3 2 B-11 0 0 material group in group out nuclide moment mean std. dev. moment +12 3 1 1 H-1 P0 0.181306 0.022102 P0 +13 3 1 1 O-16 P0 0.078631 0.005044 P0 +14 3 1 1 B-10 P0 0.000000 0.000000 P0 +15 3 1 1 B-11 P0 0.000000 0.000000 P0 +8 3 1 2 H-1 P0 0.025666 0.001582 P0 +9 3 1 2 O-16 P0 0.000521 0.000131 P0 +10 3 1 2 B-10 P0 0.000000 0.000000 P0 +11 3 1 2 B-11 P0 0.000000 0.000000 P0 +4 3 2 1 H-1 P0 0.000000 0.000000 P0 +5 3 2 1 O-16 P0 0.000000 0.000000 P0 +6 3 2 1 B-10 P0 0.000000 0.000000 P0 +7 3 2 1 B-11 P0 0.000000 0.000000 P0 +0 3 2 2 H-1 P0 1.273963 0.250623 P0 +1 3 2 2 O-16 P0 0.085363 0.014001 P0 +2 3 2 2 B-10 P0 0.000000 0.000000 P0 +3 3 2 2 B-11 P0 0.000195 0.001527 P0 material group out nuclide mean std. dev. +4 3 1 H-1 0 0 +5 3 1 O-16 0 0 +6 3 1 B-10 0 0 +7 3 1 B-11 0 0 +0 3 2 H-1 0 0 +1 3 2 O-16 0 0 +2 3 2 B-10 0 0 +3 3 2 B-11 0 0 material group in nuclide mean std. dev. +4 4 1 H-1 0.175242 0.053715 +5 4 1 O-16 0.066545 0.010083 +6 4 1 B-10 0.000570 0.000352 +7 4 1 B-11 0.000089 0.000346 +0 4 2 H-1 1.142895 0.365140 +1 4 2 O-16 0.085141 0.028073 +2 4 2 B-10 0.025923 0.007276 +3 4 2 B-11 0.000000 0.000000 material group in nuclide mean std. dev. +4 4 1 H-1 0 0 +5 4 1 O-16 0 0 +6 4 1 B-10 0 0 +7 4 1 B-11 0 0 +0 4 2 H-1 0 0 +1 4 2 O-16 0 0 +2 4 2 B-10 0 0 +3 4 2 B-11 0 0 material group in group out nuclide moment mean std. dev. moment +12 4 1 1 H-1 P0 0.151295 0.051491 P0 +13 4 1 1 O-16 P0 0.066545 0.010083 P0 +14 4 1 1 B-10 P0 0.000000 0.000000 P0 +15 4 1 1 B-11 P0 0.000089 0.000346 P0 +8 4 1 2 H-1 P0 0.023662 0.003083 P0 +9 4 1 2 O-16 P0 0.000000 0.000000 P0 +10 4 1 2 B-10 P0 0.000000 0.000000 P0 +11 4 1 2 B-11 P0 0.000000 0.000000 P0 +4 4 2 1 H-1 P0 0.000000 0.000000 P0 +5 4 2 1 O-16 P0 0.000000 0.000000 P0 +6 4 2 1 B-10 P0 0.000000 0.000000 P0 +7 4 2 1 B-11 P0 0.000000 0.000000 P0 +0 4 2 2 H-1 P0 1.129933 0.361681 P0 +1 4 2 2 O-16 P0 0.085141 0.028073 P0 +2 4 2 2 B-10 P0 0.000000 0.000000 P0 +3 4 2 2 B-11 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +4 4 1 H-1 0 0 +5 4 1 O-16 0 0 +6 4 1 B-10 0 0 +7 4 1 B-11 0 0 +0 4 2 H-1 0 0 +1 4 2 O-16 0 0 +2 4 2 B-10 0 0 +3 4 2 B-11 0 0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in group out nuclide moment mean std. dev. moment +81 5 1 1 Fe-54 P0 0 0 P0 +82 5 1 1 Fe-56 P0 0 0 P0 +83 5 1 1 Fe-57 P0 0 0 P0 +84 5 1 1 Fe-58 P0 0 0 P0 +85 5 1 1 Ni-58 P0 0 0 P0 +86 5 1 1 Ni-60 P0 0 0 P0 +87 5 1 1 Ni-61 P0 0 0 P0 +88 5 1 1 Ni-62 P0 0 0 P0 +89 5 1 1 Ni-64 P0 0 0 P0 +90 5 1 1 Mn-55 P0 0 0 P0 +91 5 1 1 Mo-92 P0 0 0 P0 +92 5 1 1 Mo-94 P0 0 0 P0 +93 5 1 1 Mo-95 P0 0 0 P0 +94 5 1 1 Mo-96 P0 0 0 P0 +95 5 1 1 Mo-97 P0 0 0 P0 +96 5 1 1 Mo-98 P0 0 0 P0 +97 5 1 1 Mo-100 P0 0 0 P0 +98 5 1 1 Si-28 P0 0 0 P0 +99 5 1 1 Si-29 P0 0 0 P0 +100 5 1 1 Si-30 P0 0 0 P0 +101 5 1 1 Cr-50 P0 0 0 P0 +102 5 1 1 Cr-52 P0 0 0 P0 +103 5 1 1 Cr-53 P0 0 0 P0 +104 5 1 1 Cr-54 P0 0 0 P0 +105 5 1 1 C-Nat P0 0 0 P0 +106 5 1 1 Cu-63 P0 0 0 P0 +107 5 1 1 Cu-65 P0 0 0 P0 +54 5 1 2 Fe-54 P0 0 0 P0 +55 5 1 2 Fe-56 P0 0 0 P0 +56 5 1 2 Fe-57 P0 0 0 P0 +57 5 1 2 Fe-58 P0 0 0 P0 +58 5 1 2 Ni-58 P0 0 0 P0 +59 5 1 2 Ni-60 P0 0 0 P0 +60 5 1 2 Ni-61 P0 0 0 P0 +61 5 1 2 Ni-62 P0 0 0 P0 +62 5 1 2 Ni-64 P0 0 0 P0 +63 5 1 2 Mn-55 P0 0 0 P0 +64 5 1 2 Mo-92 P0 0 0 P0 +65 5 1 2 Mo-94 P0 0 0 P0 +66 5 1 2 Mo-95 P0 0 0 P0 +67 5 1 2 Mo-96 P0 0 0 P0 +68 5 1 2 Mo-97 P0 0 0 P0 +69 5 1 2 Mo-98 P0 0 0 P0 +70 5 1 2 Mo-100 P0 0 0 P0 +71 5 1 2 Si-28 P0 0 0 P0 +72 5 1 2 Si-29 P0 0 0 P0 +73 5 1 2 Si-30 P0 0 0 P0 +74 5 1 2 Cr-50 P0 0 0 P0 +75 5 1 2 Cr-52 P0 0 0 P0 +76 5 1 2 Cr-53 P0 0 0 P0 +77 5 1 2 Cr-54 P0 0 0 P0 +78 5 1 2 C-Nat P0 0 0 P0 +79 5 1 2 Cu-63 P0 0 0 P0 +80 5 1 2 Cu-65 P0 0 0 P0 +27 5 2 1 Fe-54 P0 0 0 P0 +28 5 2 1 Fe-56 P0 0 0 P0 +29 5 2 1 Fe-57 P0 0 0 P0 +30 5 2 1 Fe-58 P0 0 0 P0 +31 5 2 1 Ni-58 P0 0 0 P0 +32 5 2 1 Ni-60 P0 0 0 P0 +33 5 2 1 Ni-61 P0 0 0 P0 +34 5 2 1 Ni-62 P0 0 0 P0 +35 5 2 1 Ni-64 P0 0 0 P0 +36 5 2 1 Mn-55 P0 0 0 P0 +37 5 2 1 Mo-92 P0 0 0 P0 +38 5 2 1 Mo-94 P0 0 0 P0 +39 5 2 1 Mo-95 P0 0 0 P0 +40 5 2 1 Mo-96 P0 0 0 P0 +41 5 2 1 Mo-97 P0 0 0 P0 +42 5 2 1 Mo-98 P0 0 0 P0 +43 5 2 1 Mo-100 P0 0 0 P0 +44 5 2 1 Si-28 P0 0 0 P0 +45 5 2 1 Si-29 P0 0 0 P0 +46 5 2 1 Si-30 P0 0 0 P0 +47 5 2 1 Cr-50 P0 0 0 P0 +48 5 2 1 Cr-52 P0 0 0 P0 +49 5 2 1 Cr-53 P0 0 0 P0 +50 5 2 1 Cr-54 P0 0 0 P0 +51 5 2 1 C-Nat P0 0 0 P0 +52 5 2 1 Cu-63 P0 0 0 P0 +53 5 2 1 Cu-65 P0 0 0 P0 +0 5 2 2 Fe-54 P0 0 0 P0 +1 5 2 2 Fe-56 P0 0 0 P0 +2 5 2 2 Fe-57 P0 0 0 P0 +3 5 2 2 Fe-58 P0 0 0 P0 +4 5 2 2 Ni-58 P0 0 0 P0 +5 5 2 2 Ni-60 P0 0 0 P0 +6 5 2 2 Ni-61 P0 0 0 P0 +7 5 2 2 Ni-62 P0 0 0 P0 +8 5 2 2 Ni-64 P0 0 0 P0 +9 5 2 2 Mn-55 P0 0 0 P0 +10 5 2 2 Mo-92 P0 0 0 P0 +11 5 2 2 Mo-94 P0 0 0 P0 +12 5 2 2 Mo-95 P0 0 0 P0 +13 5 2 2 Mo-96 P0 0 0 P0 +14 5 2 2 Mo-97 P0 0 0 P0 +15 5 2 2 Mo-98 P0 0 0 P0 +16 5 2 2 Mo-100 P0 0 0 P0 +17 5 2 2 Si-28 P0 0 0 P0 +18 5 2 2 Si-29 P0 0 0 P0 +19 5 2 2 Si-30 P0 0 0 P0 +20 5 2 2 Cr-50 P0 0 0 P0 +21 5 2 2 Cr-52 P0 0 0 P0 +22 5 2 2 Cr-53 P0 0 0 P0 +23 5 2 2 Cr-54 P0 0 0 P0 +24 5 2 2 C-Nat P0 0 0 P0 +25 5 2 2 Cu-63 P0 0 0 P0 +26 5 2 2 Cu-65 P0 0 0 P0 material group out nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +63 6 1 1 H-1 P0 0 0 P0 +64 6 1 1 O-16 P0 0 0 P0 +65 6 1 1 B-10 P0 0 0 P0 +66 6 1 1 B-11 P0 0 0 P0 +67 6 1 1 Fe-54 P0 0 0 P0 +68 6 1 1 Fe-56 P0 0 0 P0 +69 6 1 1 Fe-57 P0 0 0 P0 +70 6 1 1 Fe-58 P0 0 0 P0 +71 6 1 1 Ni-58 P0 0 0 P0 +72 6 1 1 Ni-60 P0 0 0 P0 +73 6 1 1 Ni-61 P0 0 0 P0 +74 6 1 1 Ni-62 P0 0 0 P0 +75 6 1 1 Ni-64 P0 0 0 P0 +76 6 1 1 Mn-55 P0 0 0 P0 +77 6 1 1 Si-28 P0 0 0 P0 +78 6 1 1 Si-29 P0 0 0 P0 +79 6 1 1 Si-30 P0 0 0 P0 +80 6 1 1 Cr-50 P0 0 0 P0 +81 6 1 1 Cr-52 P0 0 0 P0 +82 6 1 1 Cr-53 P0 0 0 P0 +83 6 1 1 Cr-54 P0 0 0 P0 +42 6 1 2 H-1 P0 0 0 P0 +43 6 1 2 O-16 P0 0 0 P0 +44 6 1 2 B-10 P0 0 0 P0 +45 6 1 2 B-11 P0 0 0 P0 +46 6 1 2 Fe-54 P0 0 0 P0 +47 6 1 2 Fe-56 P0 0 0 P0 +48 6 1 2 Fe-57 P0 0 0 P0 +49 6 1 2 Fe-58 P0 0 0 P0 +50 6 1 2 Ni-58 P0 0 0 P0 +51 6 1 2 Ni-60 P0 0 0 P0 +52 6 1 2 Ni-61 P0 0 0 P0 +53 6 1 2 Ni-62 P0 0 0 P0 +54 6 1 2 Ni-64 P0 0 0 P0 +55 6 1 2 Mn-55 P0 0 0 P0 +56 6 1 2 Si-28 P0 0 0 P0 +57 6 1 2 Si-29 P0 0 0 P0 +58 6 1 2 Si-30 P0 0 0 P0 +59 6 1 2 Cr-50 P0 0 0 P0 +60 6 1 2 Cr-52 P0 0 0 P0 +61 6 1 2 Cr-53 P0 0 0 P0 +62 6 1 2 Cr-54 P0 0 0 P0 +21 6 2 1 H-1 P0 0 0 P0 +22 6 2 1 O-16 P0 0 0 P0 +23 6 2 1 B-10 P0 0 0 P0 +24 6 2 1 B-11 P0 0 0 P0 +25 6 2 1 Fe-54 P0 0 0 P0 +26 6 2 1 Fe-56 P0 0 0 P0 +27 6 2 1 Fe-57 P0 0 0 P0 +28 6 2 1 Fe-58 P0 0 0 P0 +29 6 2 1 Ni-58 P0 0 0 P0 +30 6 2 1 Ni-60 P0 0 0 P0 +31 6 2 1 Ni-61 P0 0 0 P0 +32 6 2 1 Ni-62 P0 0 0 P0 +33 6 2 1 Ni-64 P0 0 0 P0 +34 6 2 1 Mn-55 P0 0 0 P0 +35 6 2 1 Si-28 P0 0 0 P0 +36 6 2 1 Si-29 P0 0 0 P0 +37 6 2 1 Si-30 P0 0 0 P0 +38 6 2 1 Cr-50 P0 0 0 P0 +39 6 2 1 Cr-52 P0 0 0 P0 +40 6 2 1 Cr-53 P0 0 0 P0 +41 6 2 1 Cr-54 P0 0 0 P0 +0 6 2 2 H-1 P0 0 0 P0 +1 6 2 2 O-16 P0 0 0 P0 +2 6 2 2 B-10 P0 0 0 P0 +3 6 2 2 B-11 P0 0 0 P0 +4 6 2 2 Fe-54 P0 0 0 P0 +5 6 2 2 Fe-56 P0 0 0 P0 +6 6 2 2 Fe-57 P0 0 0 P0 +7 6 2 2 Fe-58 P0 0 0 P0 +8 6 2 2 Ni-58 P0 0 0 P0 +9 6 2 2 Ni-60 P0 0 0 P0 +10 6 2 2 Ni-61 P0 0 0 P0 +11 6 2 2 Ni-62 P0 0 0 P0 +12 6 2 2 Ni-64 P0 0 0 P0 +13 6 2 2 Mn-55 P0 0 0 P0 +14 6 2 2 Si-28 P0 0 0 P0 +15 6 2 2 Si-29 P0 0 0 P0 +16 6 2 2 Si-30 P0 0 0 P0 +17 6 2 2 Cr-50 P0 0 0 P0 +18 6 2 2 Cr-52 P0 0 0 P0 +19 6 2 2 Cr-53 P0 0 0 P0 +20 6 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +63 7 1 1 H-1 P0 0 0 P0 +64 7 1 1 O-16 P0 0 0 P0 +65 7 1 1 B-10 P0 0 0 P0 +66 7 1 1 B-11 P0 0 0 P0 +67 7 1 1 Fe-54 P0 0 0 P0 +68 7 1 1 Fe-56 P0 0 0 P0 +69 7 1 1 Fe-57 P0 0 0 P0 +70 7 1 1 Fe-58 P0 0 0 P0 +71 7 1 1 Ni-58 P0 0 0 P0 +72 7 1 1 Ni-60 P0 0 0 P0 +73 7 1 1 Ni-61 P0 0 0 P0 +74 7 1 1 Ni-62 P0 0 0 P0 +75 7 1 1 Ni-64 P0 0 0 P0 +76 7 1 1 Mn-55 P0 0 0 P0 +77 7 1 1 Si-28 P0 0 0 P0 +78 7 1 1 Si-29 P0 0 0 P0 +79 7 1 1 Si-30 P0 0 0 P0 +80 7 1 1 Cr-50 P0 0 0 P0 +81 7 1 1 Cr-52 P0 0 0 P0 +82 7 1 1 Cr-53 P0 0 0 P0 +83 7 1 1 Cr-54 P0 0 0 P0 +42 7 1 2 H-1 P0 0 0 P0 +43 7 1 2 O-16 P0 0 0 P0 +44 7 1 2 B-10 P0 0 0 P0 +45 7 1 2 B-11 P0 0 0 P0 +46 7 1 2 Fe-54 P0 0 0 P0 +47 7 1 2 Fe-56 P0 0 0 P0 +48 7 1 2 Fe-57 P0 0 0 P0 +49 7 1 2 Fe-58 P0 0 0 P0 +50 7 1 2 Ni-58 P0 0 0 P0 +51 7 1 2 Ni-60 P0 0 0 P0 +52 7 1 2 Ni-61 P0 0 0 P0 +53 7 1 2 Ni-62 P0 0 0 P0 +54 7 1 2 Ni-64 P0 0 0 P0 +55 7 1 2 Mn-55 P0 0 0 P0 +56 7 1 2 Si-28 P0 0 0 P0 +57 7 1 2 Si-29 P0 0 0 P0 +58 7 1 2 Si-30 P0 0 0 P0 +59 7 1 2 Cr-50 P0 0 0 P0 +60 7 1 2 Cr-52 P0 0 0 P0 +61 7 1 2 Cr-53 P0 0 0 P0 +62 7 1 2 Cr-54 P0 0 0 P0 +21 7 2 1 H-1 P0 0 0 P0 +22 7 2 1 O-16 P0 0 0 P0 +23 7 2 1 B-10 P0 0 0 P0 +24 7 2 1 B-11 P0 0 0 P0 +25 7 2 1 Fe-54 P0 0 0 P0 +26 7 2 1 Fe-56 P0 0 0 P0 +27 7 2 1 Fe-57 P0 0 0 P0 +28 7 2 1 Fe-58 P0 0 0 P0 +29 7 2 1 Ni-58 P0 0 0 P0 +30 7 2 1 Ni-60 P0 0 0 P0 +31 7 2 1 Ni-61 P0 0 0 P0 +32 7 2 1 Ni-62 P0 0 0 P0 +33 7 2 1 Ni-64 P0 0 0 P0 +34 7 2 1 Mn-55 P0 0 0 P0 +35 7 2 1 Si-28 P0 0 0 P0 +36 7 2 1 Si-29 P0 0 0 P0 +37 7 2 1 Si-30 P0 0 0 P0 +38 7 2 1 Cr-50 P0 0 0 P0 +39 7 2 1 Cr-52 P0 0 0 P0 +40 7 2 1 Cr-53 P0 0 0 P0 +41 7 2 1 Cr-54 P0 0 0 P0 +0 7 2 2 H-1 P0 0 0 P0 +1 7 2 2 O-16 P0 0 0 P0 +2 7 2 2 B-10 P0 0 0 P0 +3 7 2 2 B-11 P0 0 0 P0 +4 7 2 2 Fe-54 P0 0 0 P0 +5 7 2 2 Fe-56 P0 0 0 P0 +6 7 2 2 Fe-57 P0 0 0 P0 +7 7 2 2 Fe-58 P0 0 0 P0 +8 7 2 2 Ni-58 P0 0 0 P0 +9 7 2 2 Ni-60 P0 0 0 P0 +10 7 2 2 Ni-61 P0 0 0 P0 +11 7 2 2 Ni-62 P0 0 0 P0 +12 7 2 2 Ni-64 P0 0 0 P0 +13 7 2 2 Mn-55 P0 0 0 P0 +14 7 2 2 Si-28 P0 0 0 P0 +15 7 2 2 Si-29 P0 0 0 P0 +16 7 2 2 Si-30 P0 0 0 P0 +17 7 2 2 Cr-50 P0 0 0 P0 +18 7 2 2 Cr-52 P0 0 0 P0 +19 7 2 2 Cr-53 P0 0 0 P0 +20 7 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +63 8 1 1 H-1 P0 0 0 P0 +64 8 1 1 O-16 P0 0 0 P0 +65 8 1 1 B-10 P0 0 0 P0 +66 8 1 1 B-11 P0 0 0 P0 +67 8 1 1 Fe-54 P0 0 0 P0 +68 8 1 1 Fe-56 P0 0 0 P0 +69 8 1 1 Fe-57 P0 0 0 P0 +70 8 1 1 Fe-58 P0 0 0 P0 +71 8 1 1 Ni-58 P0 0 0 P0 +72 8 1 1 Ni-60 P0 0 0 P0 +73 8 1 1 Ni-61 P0 0 0 P0 +74 8 1 1 Ni-62 P0 0 0 P0 +75 8 1 1 Ni-64 P0 0 0 P0 +76 8 1 1 Mn-55 P0 0 0 P0 +77 8 1 1 Si-28 P0 0 0 P0 +78 8 1 1 Si-29 P0 0 0 P0 +79 8 1 1 Si-30 P0 0 0 P0 +80 8 1 1 Cr-50 P0 0 0 P0 +81 8 1 1 Cr-52 P0 0 0 P0 +82 8 1 1 Cr-53 P0 0 0 P0 +83 8 1 1 Cr-54 P0 0 0 P0 +42 8 1 2 H-1 P0 0 0 P0 +43 8 1 2 O-16 P0 0 0 P0 +44 8 1 2 B-10 P0 0 0 P0 +45 8 1 2 B-11 P0 0 0 P0 +46 8 1 2 Fe-54 P0 0 0 P0 +47 8 1 2 Fe-56 P0 0 0 P0 +48 8 1 2 Fe-57 P0 0 0 P0 +49 8 1 2 Fe-58 P0 0 0 P0 +50 8 1 2 Ni-58 P0 0 0 P0 +51 8 1 2 Ni-60 P0 0 0 P0 +52 8 1 2 Ni-61 P0 0 0 P0 +53 8 1 2 Ni-62 P0 0 0 P0 +54 8 1 2 Ni-64 P0 0 0 P0 +55 8 1 2 Mn-55 P0 0 0 P0 +56 8 1 2 Si-28 P0 0 0 P0 +57 8 1 2 Si-29 P0 0 0 P0 +58 8 1 2 Si-30 P0 0 0 P0 +59 8 1 2 Cr-50 P0 0 0 P0 +60 8 1 2 Cr-52 P0 0 0 P0 +61 8 1 2 Cr-53 P0 0 0 P0 +62 8 1 2 Cr-54 P0 0 0 P0 +21 8 2 1 H-1 P0 0 0 P0 +22 8 2 1 O-16 P0 0 0 P0 +23 8 2 1 B-10 P0 0 0 P0 +24 8 2 1 B-11 P0 0 0 P0 +25 8 2 1 Fe-54 P0 0 0 P0 +26 8 2 1 Fe-56 P0 0 0 P0 +27 8 2 1 Fe-57 P0 0 0 P0 +28 8 2 1 Fe-58 P0 0 0 P0 +29 8 2 1 Ni-58 P0 0 0 P0 +30 8 2 1 Ni-60 P0 0 0 P0 +31 8 2 1 Ni-61 P0 0 0 P0 +32 8 2 1 Ni-62 P0 0 0 P0 +33 8 2 1 Ni-64 P0 0 0 P0 +34 8 2 1 Mn-55 P0 0 0 P0 +35 8 2 1 Si-28 P0 0 0 P0 +36 8 2 1 Si-29 P0 0 0 P0 +37 8 2 1 Si-30 P0 0 0 P0 +38 8 2 1 Cr-50 P0 0 0 P0 +39 8 2 1 Cr-52 P0 0 0 P0 +40 8 2 1 Cr-53 P0 0 0 P0 +41 8 2 1 Cr-54 P0 0 0 P0 +0 8 2 2 H-1 P0 0 0 P0 +1 8 2 2 O-16 P0 0 0 P0 +2 8 2 2 B-10 P0 0 0 P0 +3 8 2 2 B-11 P0 0 0 P0 +4 8 2 2 Fe-54 P0 0 0 P0 +5 8 2 2 Fe-56 P0 0 0 P0 +6 8 2 2 Fe-57 P0 0 0 P0 +7 8 2 2 Fe-58 P0 0 0 P0 +8 8 2 2 Ni-58 P0 0 0 P0 +9 8 2 2 Ni-60 P0 0 0 P0 +10 8 2 2 Ni-61 P0 0 0 P0 +11 8 2 2 Ni-62 P0 0 0 P0 +12 8 2 2 Ni-64 P0 0 0 P0 +13 8 2 2 Mn-55 P0 0 0 P0 +14 8 2 2 Si-28 P0 0 0 P0 +15 8 2 2 Si-29 P0 0 0 P0 +16 8 2 2 Si-30 P0 0 0 P0 +17 8 2 2 Cr-50 P0 0 0 P0 +18 8 2 2 Cr-52 P0 0 0 P0 +19 8 2 2 Cr-53 P0 0 0 P0 +20 8 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 9 1 H-1 0.150655 0.480993 +22 9 1 O-16 0.116221 0.114089 +23 9 1 B-10 0.000000 0.000000 +24 9 1 B-11 0.000000 0.000000 +25 9 1 Fe-54 0.000000 0.000000 +26 9 1 Fe-56 0.186217 0.199795 +27 9 1 Fe-57 0.000000 0.000000 +28 9 1 Fe-58 0.000000 0.000000 +29 9 1 Ni-58 0.000000 0.000000 +30 9 1 Ni-60 0.000000 0.000000 +31 9 1 Ni-61 0.000000 0.000000 +32 9 1 Ni-62 0.000000 0.000000 +33 9 1 Ni-64 0.000000 0.000000 +34 9 1 Mn-55 0.000000 0.000000 +35 9 1 Si-28 0.000000 0.000000 +36 9 1 Si-29 0.000000 0.000000 +37 9 1 Si-30 0.000000 0.000000 +38 9 1 Cr-50 0.000000 0.000000 +39 9 1 Cr-52 0.000000 0.000000 +40 9 1 Cr-53 0.147443 0.139574 +41 9 1 Cr-54 0.000000 0.000000 +0 9 2 H-1 0.000000 0.000000 +1 9 2 O-16 0.000000 0.000000 +2 9 2 B-10 0.000000 0.000000 +3 9 2 B-11 0.000000 0.000000 +4 9 2 Fe-54 0.000000 0.000000 +5 9 2 Fe-56 0.000000 0.000000 +6 9 2 Fe-57 0.000000 0.000000 +7 9 2 Fe-58 0.000000 0.000000 +8 9 2 Ni-58 0.000000 0.000000 +9 9 2 Ni-60 0.000000 0.000000 +10 9 2 Ni-61 0.000000 0.000000 +11 9 2 Ni-62 0.000000 0.000000 +12 9 2 Ni-64 0.000000 0.000000 +13 9 2 Mn-55 0.000000 0.000000 +14 9 2 Si-28 0.000000 0.000000 +15 9 2 Si-29 0.000000 0.000000 +16 9 2 Si-30 0.000000 0.000000 +17 9 2 Cr-50 0.000000 0.000000 +18 9 2 Cr-52 0.000000 0.000000 +19 9 2 Cr-53 0.000000 0.000000 +20 9 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. +21 9 1 H-1 0 0 +22 9 1 O-16 0 0 +23 9 1 B-10 0 0 +24 9 1 B-11 0 0 +25 9 1 Fe-54 0 0 +26 9 1 Fe-56 0 0 +27 9 1 Fe-57 0 0 +28 9 1 Fe-58 0 0 +29 9 1 Ni-58 0 0 +30 9 1 Ni-60 0 0 +31 9 1 Ni-61 0 0 +32 9 1 Ni-62 0 0 +33 9 1 Ni-64 0 0 +34 9 1 Mn-55 0 0 +35 9 1 Si-28 0 0 +36 9 1 Si-29 0 0 +37 9 1 Si-30 0 0 +38 9 1 Cr-50 0 0 +39 9 1 Cr-52 0 0 +40 9 1 Cr-53 0 0 +41 9 1 Cr-54 0 0 +0 9 2 H-1 0 0 +1 9 2 O-16 0 0 +2 9 2 B-10 0 0 +3 9 2 B-11 0 0 +4 9 2 Fe-54 0 0 +5 9 2 Fe-56 0 0 +6 9 2 Fe-57 0 0 +7 9 2 Fe-58 0 0 +8 9 2 Ni-58 0 0 +9 9 2 Ni-60 0 0 +10 9 2 Ni-61 0 0 +11 9 2 Ni-62 0 0 +12 9 2 Ni-64 0 0 +13 9 2 Mn-55 0 0 +14 9 2 Si-28 0 0 +15 9 2 Si-29 0 0 +16 9 2 Si-30 0 0 +17 9 2 Cr-50 0 0 +18 9 2 Cr-52 0 0 +19 9 2 Cr-53 0 0 +20 9 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +63 9 1 1 H-1 P0 0.150655 0.480993 P0 +64 9 1 1 O-16 P0 0.116221 0.114089 P0 +65 9 1 1 B-10 P0 0.000000 0.000000 P0 +66 9 1 1 B-11 P0 0.000000 0.000000 P0 +67 9 1 1 Fe-54 P0 0.000000 0.000000 P0 +68 9 1 1 Fe-56 P0 0.186217 0.199795 P0 +69 9 1 1 Fe-57 P0 0.000000 0.000000 P0 +70 9 1 1 Fe-58 P0 0.000000 0.000000 P0 +71 9 1 1 Ni-58 P0 0.000000 0.000000 P0 +72 9 1 1 Ni-60 P0 0.000000 0.000000 P0 +73 9 1 1 Ni-61 P0 0.000000 0.000000 P0 +74 9 1 1 Ni-62 P0 0.000000 0.000000 P0 +75 9 1 1 Ni-64 P0 0.000000 0.000000 P0 +76 9 1 1 Mn-55 P0 0.000000 0.000000 P0 +77 9 1 1 Si-28 P0 0.000000 0.000000 P0 +78 9 1 1 Si-29 P0 0.000000 0.000000 P0 +79 9 1 1 Si-30 P0 0.000000 0.000000 P0 +80 9 1 1 Cr-50 P0 0.000000 0.000000 P0 +81 9 1 1 Cr-52 P0 0.000000 0.000000 P0 +82 9 1 1 Cr-53 P0 0.147443 0.139574 P0 +83 9 1 1 Cr-54 P0 0.000000 0.000000 P0 +42 9 1 2 H-1 P0 0.000000 0.000000 P0 +43 9 1 2 O-16 P0 0.000000 0.000000 P0 +44 9 1 2 B-10 P0 0.000000 0.000000 P0 +45 9 1 2 B-11 P0 0.000000 0.000000 P0 +46 9 1 2 Fe-54 P0 0.000000 0.000000 P0 +47 9 1 2 Fe-56 P0 0.000000 0.000000 P0 +48 9 1 2 Fe-57 P0 0.000000 0.000000 P0 +49 9 1 2 Fe-58 P0 0.000000 0.000000 P0 +50 9 1 2 Ni-58 P0 0.000000 0.000000 P0 +51 9 1 2 Ni-60 P0 0.000000 0.000000 P0 +52 9 1 2 Ni-61 P0 0.000000 0.000000 P0 +53 9 1 2 Ni-62 P0 0.000000 0.000000 P0 +54 9 1 2 Ni-64 P0 0.000000 0.000000 P0 +55 9 1 2 Mn-55 P0 0.000000 0.000000 P0 +56 9 1 2 Si-28 P0 0.000000 0.000000 P0 +57 9 1 2 Si-29 P0 0.000000 0.000000 P0 +58 9 1 2 Si-30 P0 0.000000 0.000000 P0 +59 9 1 2 Cr-50 P0 0.000000 0.000000 P0 +60 9 1 2 Cr-52 P0 0.000000 0.000000 P0 +61 9 1 2 Cr-53 P0 0.000000 0.000000 P0 +62 9 1 2 Cr-54 P0 0.000000 0.000000 P0 +21 9 2 1 H-1 P0 0.000000 0.000000 P0 +22 9 2 1 O-16 P0 0.000000 0.000000 P0 +23 9 2 1 B-10 P0 0.000000 0.000000 P0 +24 9 2 1 B-11 P0 0.000000 0.000000 P0 +25 9 2 1 Fe-54 P0 0.000000 0.000000 P0 +26 9 2 1 Fe-56 P0 0.000000 0.000000 P0 +27 9 2 1 Fe-57 P0 0.000000 0.000000 P0 +28 9 2 1 Fe-58 P0 0.000000 0.000000 P0 +29 9 2 1 Ni-58 P0 0.000000 0.000000 P0 +30 9 2 1 Ni-60 P0 0.000000 0.000000 P0 +31 9 2 1 Ni-61 P0 0.000000 0.000000 P0 +32 9 2 1 Ni-62 P0 0.000000 0.000000 P0 +33 9 2 1 Ni-64 P0 0.000000 0.000000 P0 +34 9 2 1 Mn-55 P0 0.000000 0.000000 P0 +35 9 2 1 Si-28 P0 0.000000 0.000000 P0 +36 9 2 1 Si-29 P0 0.000000 0.000000 P0 +37 9 2 1 Si-30 P0 0.000000 0.000000 P0 +38 9 2 1 Cr-50 P0 0.000000 0.000000 P0 +39 9 2 1 Cr-52 P0 0.000000 0.000000 P0 +40 9 2 1 Cr-53 P0 0.000000 0.000000 P0 +41 9 2 1 Cr-54 P0 0.000000 0.000000 P0 +0 9 2 2 H-1 P0 0.000000 0.000000 P0 +1 9 2 2 O-16 P0 0.000000 0.000000 P0 +2 9 2 2 B-10 P0 0.000000 0.000000 P0 +3 9 2 2 B-11 P0 0.000000 0.000000 P0 +4 9 2 2 Fe-54 P0 0.000000 0.000000 P0 +5 9 2 2 Fe-56 P0 0.000000 0.000000 P0 +6 9 2 2 Fe-57 P0 0.000000 0.000000 P0 +7 9 2 2 Fe-58 P0 0.000000 0.000000 P0 +8 9 2 2 Ni-58 P0 0.000000 0.000000 P0 +9 9 2 2 Ni-60 P0 0.000000 0.000000 P0 +10 9 2 2 Ni-61 P0 0.000000 0.000000 P0 +11 9 2 2 Ni-62 P0 0.000000 0.000000 P0 +12 9 2 2 Ni-64 P0 0.000000 0.000000 P0 +13 9 2 2 Mn-55 P0 0.000000 0.000000 P0 +14 9 2 2 Si-28 P0 0.000000 0.000000 P0 +15 9 2 2 Si-29 P0 0.000000 0.000000 P0 +16 9 2 2 Si-30 P0 0.000000 0.000000 P0 +17 9 2 2 Cr-50 P0 0.000000 0.000000 P0 +18 9 2 2 Cr-52 P0 0.000000 0.000000 P0 +19 9 2 2 Cr-53 P0 0.000000 0.000000 P0 +20 9 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +21 9 1 H-1 0 0 +22 9 1 O-16 0 0 +23 9 1 B-10 0 0 +24 9 1 B-11 0 0 +25 9 1 Fe-54 0 0 +26 9 1 Fe-56 0 0 +27 9 1 Fe-57 0 0 +28 9 1 Fe-58 0 0 +29 9 1 Ni-58 0 0 +30 9 1 Ni-60 0 0 +31 9 1 Ni-61 0 0 +32 9 1 Ni-62 0 0 +33 9 1 Ni-64 0 0 +34 9 1 Mn-55 0 0 +35 9 1 Si-28 0 0 +36 9 1 Si-29 0 0 +37 9 1 Si-30 0 0 +38 9 1 Cr-50 0 0 +39 9 1 Cr-52 0 0 +40 9 1 Cr-53 0 0 +41 9 1 Cr-54 0 0 +0 9 2 H-1 0 0 +1 9 2 O-16 0 0 +2 9 2 B-10 0 0 +3 9 2 B-11 0 0 +4 9 2 Fe-54 0 0 +5 9 2 Fe-56 0 0 +6 9 2 Fe-57 0 0 +7 9 2 Fe-58 0 0 +8 9 2 Ni-58 0 0 +9 9 2 Ni-60 0 0 +10 9 2 Ni-61 0 0 +11 9 2 Ni-62 0 0 +12 9 2 Ni-64 0 0 +13 9 2 Mn-55 0 0 +14 9 2 Si-28 0 0 +15 9 2 Si-29 0 0 +16 9 2 Si-30 0 0 +17 9 2 Cr-50 0 0 +18 9 2 Cr-52 0 0 +19 9 2 Cr-53 0 0 +20 9 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 10 1 H-1 0.123944 0.541390 +22 10 1 O-16 0.000000 0.000000 +23 10 1 B-10 0.000000 0.000000 +24 10 1 B-11 0.000000 0.000000 +25 10 1 Fe-54 0.000000 0.000000 +26 10 1 Fe-56 0.000000 0.000000 +27 10 1 Fe-57 0.000000 0.000000 +28 10 1 Fe-58 0.000000 0.000000 +29 10 1 Ni-58 0.000000 0.000000 +30 10 1 Ni-60 0.000000 0.000000 +31 10 1 Ni-61 0.000000 0.000000 +32 10 1 Ni-62 0.000000 0.000000 +33 10 1 Ni-64 0.000000 0.000000 +34 10 1 Mn-55 0.000000 0.000000 +35 10 1 Si-28 0.000000 0.000000 +36 10 1 Si-29 0.000000 0.000000 +37 10 1 Si-30 0.000000 0.000000 +38 10 1 Cr-50 0.111571 0.138458 +39 10 1 Cr-52 0.000000 0.000000 +40 10 1 Cr-53 0.000000 0.000000 +41 10 1 Cr-54 0.000000 0.000000 +0 10 2 H-1 0.000000 0.000000 +1 10 2 O-16 0.000000 0.000000 +2 10 2 B-10 0.000000 0.000000 +3 10 2 B-11 0.000000 0.000000 +4 10 2 Fe-54 0.000000 0.000000 +5 10 2 Fe-56 0.000000 0.000000 +6 10 2 Fe-57 0.000000 0.000000 +7 10 2 Fe-58 0.000000 0.000000 +8 10 2 Ni-58 0.000000 0.000000 +9 10 2 Ni-60 0.000000 0.000000 +10 10 2 Ni-61 0.000000 0.000000 +11 10 2 Ni-62 0.000000 0.000000 +12 10 2 Ni-64 0.000000 0.000000 +13 10 2 Mn-55 0.000000 0.000000 +14 10 2 Si-28 0.000000 0.000000 +15 10 2 Si-29 0.000000 0.000000 +16 10 2 Si-30 0.000000 0.000000 +17 10 2 Cr-50 0.000000 0.000000 +18 10 2 Cr-52 0.000000 0.000000 +19 10 2 Cr-53 0.000000 0.000000 +20 10 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. +21 10 1 H-1 0 0 +22 10 1 O-16 0 0 +23 10 1 B-10 0 0 +24 10 1 B-11 0 0 +25 10 1 Fe-54 0 0 +26 10 1 Fe-56 0 0 +27 10 1 Fe-57 0 0 +28 10 1 Fe-58 0 0 +29 10 1 Ni-58 0 0 +30 10 1 Ni-60 0 0 +31 10 1 Ni-61 0 0 +32 10 1 Ni-62 0 0 +33 10 1 Ni-64 0 0 +34 10 1 Mn-55 0 0 +35 10 1 Si-28 0 0 +36 10 1 Si-29 0 0 +37 10 1 Si-30 0 0 +38 10 1 Cr-50 0 0 +39 10 1 Cr-52 0 0 +40 10 1 Cr-53 0 0 +41 10 1 Cr-54 0 0 +0 10 2 H-1 0 0 +1 10 2 O-16 0 0 +2 10 2 B-10 0 0 +3 10 2 B-11 0 0 +4 10 2 Fe-54 0 0 +5 10 2 Fe-56 0 0 +6 10 2 Fe-57 0 0 +7 10 2 Fe-58 0 0 +8 10 2 Ni-58 0 0 +9 10 2 Ni-60 0 0 +10 10 2 Ni-61 0 0 +11 10 2 Ni-62 0 0 +12 10 2 Ni-64 0 0 +13 10 2 Mn-55 0 0 +14 10 2 Si-28 0 0 +15 10 2 Si-29 0 0 +16 10 2 Si-30 0 0 +17 10 2 Cr-50 0 0 +18 10 2 Cr-52 0 0 +19 10 2 Cr-53 0 0 +20 10 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +63 10 1 1 H-1 P0 0.123944 0.541390 P0 +64 10 1 1 O-16 P0 0.000000 0.000000 P0 +65 10 1 1 B-10 P0 0.000000 0.000000 P0 +66 10 1 1 B-11 P0 0.000000 0.000000 P0 +67 10 1 1 Fe-54 P0 0.000000 0.000000 P0 +68 10 1 1 Fe-56 P0 0.000000 0.000000 P0 +69 10 1 1 Fe-57 P0 0.000000 0.000000 P0 +70 10 1 1 Fe-58 P0 0.000000 0.000000 P0 +71 10 1 1 Ni-58 P0 0.000000 0.000000 P0 +72 10 1 1 Ni-60 P0 0.000000 0.000000 P0 +73 10 1 1 Ni-61 P0 0.000000 0.000000 P0 +74 10 1 1 Ni-62 P0 0.000000 0.000000 P0 +75 10 1 1 Ni-64 P0 0.000000 0.000000 P0 +76 10 1 1 Mn-55 P0 0.000000 0.000000 P0 +77 10 1 1 Si-28 P0 0.000000 0.000000 P0 +78 10 1 1 Si-29 P0 0.000000 0.000000 P0 +79 10 1 1 Si-30 P0 0.000000 0.000000 P0 +80 10 1 1 Cr-50 P0 0.111571 0.138458 P0 +81 10 1 1 Cr-52 P0 0.000000 0.000000 P0 +82 10 1 1 Cr-53 P0 0.000000 0.000000 P0 +83 10 1 1 Cr-54 P0 0.000000 0.000000 P0 +42 10 1 2 H-1 P0 0.000000 0.000000 P0 +43 10 1 2 O-16 P0 0.000000 0.000000 P0 +44 10 1 2 B-10 P0 0.000000 0.000000 P0 +45 10 1 2 B-11 P0 0.000000 0.000000 P0 +46 10 1 2 Fe-54 P0 0.000000 0.000000 P0 +47 10 1 2 Fe-56 P0 0.000000 0.000000 P0 +48 10 1 2 Fe-57 P0 0.000000 0.000000 P0 +49 10 1 2 Fe-58 P0 0.000000 0.000000 P0 +50 10 1 2 Ni-58 P0 0.000000 0.000000 P0 +51 10 1 2 Ni-60 P0 0.000000 0.000000 P0 +52 10 1 2 Ni-61 P0 0.000000 0.000000 P0 +53 10 1 2 Ni-62 P0 0.000000 0.000000 P0 +54 10 1 2 Ni-64 P0 0.000000 0.000000 P0 +55 10 1 2 Mn-55 P0 0.000000 0.000000 P0 +56 10 1 2 Si-28 P0 0.000000 0.000000 P0 +57 10 1 2 Si-29 P0 0.000000 0.000000 P0 +58 10 1 2 Si-30 P0 0.000000 0.000000 P0 +59 10 1 2 Cr-50 P0 0.000000 0.000000 P0 +60 10 1 2 Cr-52 P0 0.000000 0.000000 P0 +61 10 1 2 Cr-53 P0 0.000000 0.000000 P0 +62 10 1 2 Cr-54 P0 0.000000 0.000000 P0 +21 10 2 1 H-1 P0 0.000000 0.000000 P0 +22 10 2 1 O-16 P0 0.000000 0.000000 P0 +23 10 2 1 B-10 P0 0.000000 0.000000 P0 +24 10 2 1 B-11 P0 0.000000 0.000000 P0 +25 10 2 1 Fe-54 P0 0.000000 0.000000 P0 +26 10 2 1 Fe-56 P0 0.000000 0.000000 P0 +27 10 2 1 Fe-57 P0 0.000000 0.000000 P0 +28 10 2 1 Fe-58 P0 0.000000 0.000000 P0 +29 10 2 1 Ni-58 P0 0.000000 0.000000 P0 +30 10 2 1 Ni-60 P0 0.000000 0.000000 P0 +31 10 2 1 Ni-61 P0 0.000000 0.000000 P0 +32 10 2 1 Ni-62 P0 0.000000 0.000000 P0 +33 10 2 1 Ni-64 P0 0.000000 0.000000 P0 +34 10 2 1 Mn-55 P0 0.000000 0.000000 P0 +35 10 2 1 Si-28 P0 0.000000 0.000000 P0 +36 10 2 1 Si-29 P0 0.000000 0.000000 P0 +37 10 2 1 Si-30 P0 0.000000 0.000000 P0 +38 10 2 1 Cr-50 P0 0.000000 0.000000 P0 +39 10 2 1 Cr-52 P0 0.000000 0.000000 P0 +40 10 2 1 Cr-53 P0 0.000000 0.000000 P0 +41 10 2 1 Cr-54 P0 0.000000 0.000000 P0 +0 10 2 2 H-1 P0 0.000000 0.000000 P0 +1 10 2 2 O-16 P0 0.000000 0.000000 P0 +2 10 2 2 B-10 P0 0.000000 0.000000 P0 +3 10 2 2 B-11 P0 0.000000 0.000000 P0 +4 10 2 2 Fe-54 P0 0.000000 0.000000 P0 +5 10 2 2 Fe-56 P0 0.000000 0.000000 P0 +6 10 2 2 Fe-57 P0 0.000000 0.000000 P0 +7 10 2 2 Fe-58 P0 0.000000 0.000000 P0 +8 10 2 2 Ni-58 P0 0.000000 0.000000 P0 +9 10 2 2 Ni-60 P0 0.000000 0.000000 P0 +10 10 2 2 Ni-61 P0 0.000000 0.000000 P0 +11 10 2 2 Ni-62 P0 0.000000 0.000000 P0 +12 10 2 2 Ni-64 P0 0.000000 0.000000 P0 +13 10 2 2 Mn-55 P0 0.000000 0.000000 P0 +14 10 2 2 Si-28 P0 0.000000 0.000000 P0 +15 10 2 2 Si-29 P0 0.000000 0.000000 P0 +16 10 2 2 Si-30 P0 0.000000 0.000000 P0 +17 10 2 2 Cr-50 P0 0.000000 0.000000 P0 +18 10 2 2 Cr-52 P0 0.000000 0.000000 P0 +19 10 2 2 Cr-53 P0 0.000000 0.000000 P0 +20 10 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +21 10 1 H-1 0 0 +22 10 1 O-16 0 0 +23 10 1 B-10 0 0 +24 10 1 B-11 0 0 +25 10 1 Fe-54 0 0 +26 10 1 Fe-56 0 0 +27 10 1 Fe-57 0 0 +28 10 1 Fe-58 0 0 +29 10 1 Ni-58 0 0 +30 10 1 Ni-60 0 0 +31 10 1 Ni-61 0 0 +32 10 1 Ni-62 0 0 +33 10 1 Ni-64 0 0 +34 10 1 Mn-55 0 0 +35 10 1 Si-28 0 0 +36 10 1 Si-29 0 0 +37 10 1 Si-30 0 0 +38 10 1 Cr-50 0 0 +39 10 1 Cr-52 0 0 +40 10 1 Cr-53 0 0 +41 10 1 Cr-54 0 0 +0 10 2 H-1 0 0 +1 10 2 O-16 0 0 +2 10 2 B-10 0 0 +3 10 2 B-11 0 0 +4 10 2 Fe-54 0 0 +5 10 2 Fe-56 0 0 +6 10 2 Fe-57 0 0 +7 10 2 Fe-58 0 0 +8 10 2 Ni-58 0 0 +9 10 2 Ni-60 0 0 +10 10 2 Ni-61 0 0 +11 10 2 Ni-62 0 0 +12 10 2 Ni-64 0 0 +13 10 2 Mn-55 0 0 +14 10 2 Si-28 0 0 +15 10 2 Si-29 0 0 +16 10 2 Si-30 0 0 +17 10 2 Cr-50 0 0 +18 10 2 Cr-52 0 0 +19 10 2 Cr-53 0 0 +20 10 2 Cr-54 0 0 material group in nuclide mean std. dev. +9 11 1 H-1 0.131470 0.476035 +10 11 1 O-16 0.028684 0.043000 +11 11 1 B-10 0.000000 0.000000 +12 11 1 B-11 0.000000 0.000000 +13 11 1 Zr-90 0.021980 0.039963 +14 11 1 Zr-91 0.000000 0.000000 +15 11 1 Zr-92 0.000000 0.000000 +16 11 1 Zr-94 0.004191 0.087344 +17 11 1 Zr-96 0.000000 0.000000 +0 11 2 H-1 0.687243 1.239217 +1 11 2 O-16 0.000000 0.000000 +2 11 2 B-10 0.042902 0.060672 +3 11 2 B-11 0.000000 0.000000 +4 11 2 Zr-90 0.039576 0.105193 +5 11 2 Zr-91 0.000000 0.000000 +6 11 2 Zr-92 0.084226 0.103161 +7 11 2 Zr-94 0.092039 0.125985 +8 11 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. +9 11 1 H-1 0 0 +10 11 1 O-16 0 0 +11 11 1 B-10 0 0 +12 11 1 B-11 0 0 +13 11 1 Zr-90 0 0 +14 11 1 Zr-91 0 0 +15 11 1 Zr-92 0 0 +16 11 1 Zr-94 0 0 +17 11 1 Zr-96 0 0 +0 11 2 H-1 0 0 +1 11 2 O-16 0 0 +2 11 2 B-10 0 0 +3 11 2 B-11 0 0 +4 11 2 Zr-90 0 0 +5 11 2 Zr-91 0 0 +6 11 2 Zr-92 0 0 +7 11 2 Zr-94 0 0 +8 11 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +27 11 1 1 H-1 P0 0.099594 0.442578 P0 +28 11 1 1 O-16 P0 0.028684 0.043000 P0 +29 11 1 1 B-10 P0 0.000000 0.000000 P0 +30 11 1 1 B-11 P0 0.000000 0.000000 P0 +31 11 1 1 Zr-90 P0 0.021980 0.039963 P0 +32 11 1 1 Zr-91 P0 0.000000 0.000000 P0 +33 11 1 1 Zr-92 P0 0.000000 0.000000 P0 +34 11 1 1 Zr-94 P0 0.004191 0.087344 P0 +35 11 1 1 Zr-96 P0 0.000000 0.000000 P0 +18 11 1 2 H-1 P0 0.031875 0.045078 P0 +19 11 1 2 O-16 P0 0.000000 0.000000 P0 +20 11 1 2 B-10 P0 0.000000 0.000000 P0 +21 11 1 2 B-11 P0 0.000000 0.000000 P0 +22 11 1 2 Zr-90 P0 0.000000 0.000000 P0 +23 11 1 2 Zr-91 P0 0.000000 0.000000 P0 +24 11 1 2 Zr-92 P0 0.000000 0.000000 P0 +25 11 1 2 Zr-94 P0 0.000000 0.000000 P0 +26 11 1 2 Zr-96 P0 0.000000 0.000000 P0 +9 11 2 1 H-1 P0 0.000000 0.000000 P0 +10 11 2 1 O-16 P0 0.000000 0.000000 P0 +11 11 2 1 B-10 P0 0.000000 0.000000 P0 +12 11 2 1 B-11 P0 0.000000 0.000000 P0 +13 11 2 1 Zr-90 P0 0.000000 0.000000 P0 +14 11 2 1 Zr-91 P0 0.000000 0.000000 P0 +15 11 2 1 Zr-92 P0 0.000000 0.000000 P0 +16 11 2 1 Zr-94 P0 0.000000 0.000000 P0 +17 11 2 1 Zr-96 P0 0.000000 0.000000 P0 +0 11 2 2 H-1 P0 0.687243 1.239217 P0 +1 11 2 2 O-16 P0 0.000000 0.000000 P0 +2 11 2 2 B-10 P0 0.000000 0.000000 P0 +3 11 2 2 B-11 P0 0.000000 0.000000 P0 +4 11 2 2 Zr-90 P0 0.039576 0.105193 P0 +5 11 2 2 Zr-91 P0 0.000000 0.000000 P0 +6 11 2 2 Zr-92 P0 0.084226 0.103161 P0 +7 11 2 2 Zr-94 P0 0.092039 0.125985 P0 +8 11 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +9 11 1 H-1 0 0 +10 11 1 O-16 0 0 +11 11 1 B-10 0 0 +12 11 1 B-11 0 0 +13 11 1 Zr-90 0 0 +14 11 1 Zr-91 0 0 +15 11 1 Zr-92 0 0 +16 11 1 Zr-94 0 0 +17 11 1 Zr-96 0 0 +0 11 2 H-1 0 0 +1 11 2 O-16 0 0 +2 11 2 B-10 0 0 +3 11 2 B-11 0 0 +4 11 2 Zr-90 0 0 +5 11 2 Zr-91 0 0 +6 11 2 Zr-92 0 0 +7 11 2 Zr-94 0 0 +8 11 2 Zr-96 0 0 material group in nuclide mean std. dev. +9 12 1 H-1 0.098944 0.178543 +10 12 1 O-16 0.013270 0.020403 +11 12 1 B-10 0.000000 0.000000 +12 12 1 B-11 0.000000 0.000000 +13 12 1 Zr-90 0.089997 0.075538 +14 12 1 Zr-91 0.000000 0.000000 +15 12 1 Zr-92 0.003501 0.017031 +16 12 1 Zr-94 0.004850 0.016327 +17 12 1 Zr-96 0.002730 0.017476 +0 12 2 H-1 1.261686 1.980336 +1 12 2 O-16 0.079159 0.104796 +2 12 2 B-10 0.016928 0.023940 +3 12 2 B-11 0.000000 0.000000 +4 12 2 Zr-90 0.000000 0.000000 +5 12 2 Zr-91 0.033201 0.040665 +6 12 2 Zr-92 0.000000 0.000000 +7 12 2 Zr-94 0.000000 0.000000 +8 12 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. +9 12 1 H-1 0 0 +10 12 1 O-16 0 0 +11 12 1 B-10 0 0 +12 12 1 B-11 0 0 +13 12 1 Zr-90 0 0 +14 12 1 Zr-91 0 0 +15 12 1 Zr-92 0 0 +16 12 1 Zr-94 0 0 +17 12 1 Zr-96 0 0 +0 12 2 H-1 0 0 +1 12 2 O-16 0 0 +2 12 2 B-10 0 0 +3 12 2 B-11 0 0 +4 12 2 Zr-90 0 0 +5 12 2 Zr-91 0 0 +6 12 2 Zr-92 0 0 +7 12 2 Zr-94 0 0 +8 12 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +27 12 1 1 H-1 P0 0.071704 0.167588 P0 +28 12 1 1 O-16 P0 0.013270 0.020403 P0 +29 12 1 1 B-10 P0 0.000000 0.000000 P0 +30 12 1 1 B-11 P0 0.000000 0.000000 P0 +31 12 1 1 Zr-90 P0 0.089997 0.075538 P0 +32 12 1 1 Zr-91 P0 0.000000 0.000000 P0 +33 12 1 1 Zr-92 P0 0.003501 0.017031 P0 +34 12 1 1 Zr-94 P0 0.004850 0.016327 P0 +35 12 1 1 Zr-96 P0 0.002730 0.017476 P0 +18 12 1 2 H-1 P0 0.027240 0.029555 P0 +19 12 1 2 O-16 P0 0.000000 0.000000 P0 +20 12 1 2 B-10 P0 0.000000 0.000000 P0 +21 12 1 2 B-11 P0 0.000000 0.000000 P0 +22 12 1 2 Zr-90 P0 0.000000 0.000000 P0 +23 12 1 2 Zr-91 P0 0.000000 0.000000 P0 +24 12 1 2 Zr-92 P0 0.000000 0.000000 P0 +25 12 1 2 Zr-94 P0 0.000000 0.000000 P0 +26 12 1 2 Zr-96 P0 0.000000 0.000000 P0 +9 12 2 1 H-1 P0 0.000000 0.000000 P0 +10 12 2 1 O-16 P0 0.000000 0.000000 P0 +11 12 2 1 B-10 P0 0.000000 0.000000 P0 +12 12 2 1 B-11 P0 0.000000 0.000000 P0 +13 12 2 1 Zr-90 P0 0.000000 0.000000 P0 +14 12 2 1 Zr-91 P0 0.000000 0.000000 P0 +15 12 2 1 Zr-92 P0 0.000000 0.000000 P0 +16 12 2 1 Zr-94 P0 0.000000 0.000000 P0 +17 12 2 1 Zr-96 P0 0.000000 0.000000 P0 +0 12 2 2 H-1 P0 1.244758 1.956675 P0 +1 12 2 2 O-16 P0 0.079159 0.104796 P0 +2 12 2 2 B-10 P0 0.000000 0.000000 P0 +3 12 2 2 B-11 P0 0.000000 0.000000 P0 +4 12 2 2 Zr-90 P0 0.000000 0.000000 P0 +5 12 2 2 Zr-91 P0 0.033201 0.040665 P0 +6 12 2 2 Zr-92 P0 0.000000 0.000000 P0 +7 12 2 2 Zr-94 P0 0.000000 0.000000 P0 +8 12 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +9 12 1 H-1 0 0 +10 12 1 O-16 0 0 +11 12 1 B-10 0 0 +12 12 1 B-11 0 0 +13 12 1 Zr-90 0 0 +14 12 1 Zr-91 0 0 +15 12 1 Zr-92 0 0 +16 12 1 Zr-94 0 0 +17 12 1 Zr-96 0 0 +0 12 2 H-1 0 0 +1 12 2 O-16 0 0 +2 12 2 B-10 0 0 +3 12 2 B-11 0 0 +4 12 2 Zr-90 0 0 +5 12 2 Zr-91 0 0 +6 12 2 Zr-92 0 0 +7 12 2 Zr-94 0 0 +8 12 2 Zr-96 0 0 \ No newline at end of file From a6fd59a6227cdf2ae29c0e71778d457e335b0bcf Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Tue, 10 May 2016 22:00:39 -0400 Subject: [PATCH 112/147] Updated MGXS tests --- .../results_true.dat | 62 +- .../results_true.dat | 4 +- .../results_true.dat | 140 +- .../results_true.dat | 2520 ++++++++--------- 4 files changed, 1363 insertions(+), 1363 deletions(-) diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 2afa47d6f..5f1d886b0 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -2,48 +2,48 @@ 0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. 0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev. moment 0 1 1 1 total P0 0.345643 0.021487 P0 material group out nuclide mean std. dev. -0 1 1 total 1 0.055333 material group in nuclide mean std. dev. +0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 2 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 2 1 1 total P0 0.241262 0.00841 P0 material group out nuclide mean std. dev. -0 2 1 total 0 0 material group in nuclide mean std. dev. +0 2 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 3 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 3 1 1 total P0 0.393462 0.033646 P0 material group out nuclide mean std. dev. -0 3 1 total 0 0 material group in nuclide mean std. dev. +0 3 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 4 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 4 1 1 total P0 0.371473 0.071226 P0 material group out nuclide mean std. dev. -0 4 1 total 0 0 material group in nuclide mean std. dev. -0 5 1 total 0 0 material group in nuclide mean std. dev. -0 5 1 total 0 0 material group in group out nuclide moment mean std. dev. moment -0 5 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. -0 5 1 total 0 0 material group in nuclide mean std. dev. -0 6 1 total 0 0 material group in nuclide mean std. dev. -0 6 1 total 0 0 material group in group out nuclide moment mean std. dev. moment -0 6 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. -0 6 1 total 0 0 material group in nuclide mean std. dev. -0 7 1 total 0 0 material group in nuclide mean std. dev. -0 7 1 total 0 0 material group in group out nuclide moment mean std. dev. moment -0 7 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. -0 7 1 total 0 0 material group in nuclide mean std. dev. -0 8 1 total 0 0 material group in nuclide mean std. dev. -0 8 1 total 0 0 material group in group out nuclide moment mean std. dev. moment -0 8 1 1 total P0 0 0 P0 material group out nuclide mean std. dev. -0 8 1 total 0 0 material group in nuclide mean std. dev. +0 4 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +0 5 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +0 6 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +0 7 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +0 8 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 9 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 9 1 1 total P0 0.600536 0.748875 P0 material group out nuclide mean std. dev. -0 9 1 total 0 0 material group in nuclide mean std. dev. +0 9 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 10 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 10 1 1 total P0 0.235515 0.613974 P0 material group out nuclide mean std. dev. -0 10 1 total 0 0 material group in nuclide mean std. dev. +0 10 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 11 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 11 1 1 total P0 0.491857 0.715554 P0 material group out nuclide mean std. dev. -0 11 1 total 0 0 material group in nuclide mean std. dev. +0 11 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0 0 material group in group out nuclide moment mean std. dev. moment +0 12 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 0 12 1 1 total P0 0.723265 0.808231 P0 material group out nuclide mean std. dev. -0 12 1 total 0 0 \ No newline at end of file +0 12 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index 4daa6cd97..014eabfa5 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,5 +1,5 @@ avg(distribcell) group in nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean std. dev. moment +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide moment mean std. dev. moment 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 0.695166 0.510606 P0 avg(distribcell) group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 \ No newline at end of file +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index a4b08dd4a..4e6d88208 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -7,115 +7,115 @@ 2 1 1 2 total P0 0.001559 0.000510 P0 1 1 2 1 total P0 0.000000 0.000000 P0 0 1 2 2 total P0 0.422051 0.021617 P0 material group out nuclide mean std. dev. -1 1 1 total 1 0.055333 -0 1 2 total 0 0.000000 material group in nuclide mean std. dev. +1 1 1 total 1.0 0.055333 +0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev. 1 2 1 total 0.237254 0.008184 0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. -1 2 1 total 0 0 -0 2 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 2 1 total 0.0 0.0 +0 2 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 2 1 1 total P0 0.237254 0.008184 P0 2 2 1 2 total P0 0.000000 0.000000 P0 1 2 2 1 total P0 0.000000 0.000000 P0 0 2 2 2 total P0 0.285930 0.048796 P0 material group out nuclide mean std. dev. -1 2 1 total 0 0 -0 2 2 total 0 0 material group in nuclide mean std. dev. +1 2 1 total 0.0 0.0 +0 2 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 3 1 total 0.286906 0.027401 0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. -1 3 1 total 0 0 -0 3 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 3 1 1 total P0 0.259937 0.026115 P0 2 3 1 2 total P0 0.026187 0.001665 P0 1 3 2 1 total P0 0.000000 0.000000 P0 0 3 2 2 total P0 1.359521 0.258505 P0 material group out nuclide mean std. dev. -1 3 1 total 0 0 -0 3 2 total 0 0 material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 4 1 total 0.242447 0.061031 0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. -1 4 1 total 0 0 -0 4 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 4 1 total 0.0 0.0 +0 4 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 4 1 1 total P0 0.217930 0.058565 P0 2 4 1 2 total P0 0.023662 0.003083 P0 1 4 2 1 total P0 0.000000 0.000000 P0 0 4 2 2 total P0 1.215074 0.381025 P0 material group out nuclide mean std. dev. -1 4 1 total 0 0 -0 4 2 total 0 0 material group in nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in group out nuclide moment mean std. dev. moment -3 5 1 1 total P0 0 0 P0 -2 5 1 2 total P0 0 0 P0 -1 5 2 1 total P0 0 0 P0 -0 5 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in group out nuclide moment mean std. dev. moment -3 6 1 1 total P0 0 0 P0 -2 6 1 2 total P0 0 0 P0 -1 6 2 1 total P0 0 0 P0 -0 6 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in group out nuclide moment mean std. dev. moment -3 7 1 1 total P0 0 0 P0 -2 7 1 2 total P0 0 0 P0 -1 7 2 1 total P0 0 0 P0 -0 7 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in group out nuclide moment mean std. dev. moment -3 8 1 1 total P0 0 0 P0 -2 8 1 2 total P0 0 0 P0 -1 8 2 1 total P0 0 0 P0 -0 8 2 2 total P0 0 0 P0 material group out nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in nuclide mean std. dev. +1 4 1 total 0.0 0.0 +0 4 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +3 5 1 1 total P0 0.0 0.0 P0 +2 5 1 2 total P0 0.0 0.0 P0 +1 5 2 1 total P0 0.0 0.0 P0 +0 5 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +3 6 1 1 total P0 0.0 0.0 P0 +2 6 1 2 total P0 0.0 0.0 P0 +1 6 2 1 total P0 0.0 0.0 P0 +0 6 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +3 7 1 1 total P0 0.0 0.0 P0 +2 7 1 2 total P0 0.0 0.0 P0 +1 7 2 1 total P0 0.0 0.0 P0 +0 7 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +3 8 1 1 total P0 0.0 0.0 P0 +2 8 1 2 total P0 0.0 0.0 P0 +1 8 2 1 total P0 0.0 0.0 P0 +0 8 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 9 1 total 0.600536 0.748875 0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 9 1 total 0 0 -0 9 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 9 1 total 0.0 0.0 +0 9 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 9 1 1 total P0 0.600536 0.748875 P0 2 9 1 2 total P0 0.000000 0.000000 P0 1 9 2 1 total P0 0.000000 0.000000 P0 0 9 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -1 9 1 total 0 0 -0 9 2 total 0 0 material group in nuclide mean std. dev. +1 9 1 total 0.0 0.0 +0 9 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 10 1 total 0.235515 0.613974 0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 10 1 total 0 0 -0 10 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 10 1 total 0.0 0.0 +0 10 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 10 1 1 total P0 0.235515 0.613974 P0 2 10 1 2 total P0 0.000000 0.000000 P0 1 10 2 1 total P0 0.000000 0.000000 P0 0 10 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -1 10 1 total 0 0 -0 10 2 total 0 0 material group in nuclide mean std. dev. +1 10 1 total 0.0 0.0 +0 10 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 11 1 total 0.186324 0.632129 0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. -1 11 1 total 0 0 -0 11 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 11 1 total 0.0 0.0 +0 11 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 11 1 1 total P0 0.154449 0.597686 P0 2 11 1 2 total P0 0.031875 0.045078 P0 1 11 2 1 total P0 0.000000 0.000000 P0 0 11 2 2 total P0 0.903085 1.532144 P0 material group out nuclide mean std. dev. -1 11 1 total 0 0 -0 11 2 total 0 0 material group in nuclide mean std. dev. +1 11 1 total 0.0 0.0 +0 11 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 12 1 total 0.213292 0.271444 0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. -1 12 1 total 0 0 -0 12 2 total 0 0 material group in group out nuclide moment mean std. dev. moment +1 12 1 total 0.0 0.0 +0 12 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 3 12 1 1 total P0 0.186052 0.257633 P0 2 12 1 2 total P0 0.027240 0.029555 P0 1 12 2 1 total P0 0.000000 0.000000 P0 0 12 2 2 total P0 1.357118 2.089846 P0 material group out nuclide mean std. dev. -1 12 1 total 0 0 -0 12 2 total 0 0 \ No newline at end of file +1 12 1 total 0.0 0.0 +0 12 2 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index aac5ff1ef..ff34c9fff 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -271,74 +271,74 @@ 31 1 2 2 Eu-153 P0 0.000000 0.000000 P0 32 1 2 2 Gd-155 P0 0.000000 0.000000 P0 33 1 2 2 O-16 P0 0.196946 0.014729 P0 material group out nuclide mean std. dev. -34 1 1 U-234 0 0.000000 -35 1 1 U-235 1 0.066362 -36 1 1 U-236 0 0.000000 -37 1 1 U-238 1 0.093082 -38 1 1 Np-237 0 0.000000 -39 1 1 Pu-238 0 0.000000 -40 1 1 Pu-239 1 0.104567 -41 1 1 Pu-240 0 0.000000 -42 1 1 Pu-241 1 0.263696 -43 1 1 Pu-242 0 0.000000 -44 1 1 Am-241 0 0.000000 -45 1 1 Am-242m 0 0.000000 -46 1 1 Am-243 0 0.000000 -47 1 1 Cm-242 0 0.000000 -48 1 1 Cm-243 0 0.000000 -49 1 1 Cm-244 0 0.000000 -50 1 1 Cm-245 0 0.000000 -51 1 1 Mo-95 0 0.000000 -52 1 1 Tc-99 0 0.000000 -53 1 1 Ru-101 0 0.000000 -54 1 1 Ru-103 0 0.000000 -55 1 1 Ag-109 0 0.000000 -56 1 1 Xe-135 0 0.000000 -57 1 1 Cs-133 0 0.000000 -58 1 1 Nd-143 0 0.000000 -59 1 1 Nd-145 0 0.000000 -60 1 1 Sm-147 0 0.000000 -61 1 1 Sm-149 0 0.000000 -62 1 1 Sm-150 0 0.000000 -63 1 1 Sm-151 0 0.000000 -64 1 1 Sm-152 0 0.000000 -65 1 1 Eu-153 0 0.000000 -66 1 1 Gd-155 0 0.000000 -67 1 1 O-16 0 0.000000 -0 1 2 U-234 0 0.000000 -1 1 2 U-235 0 0.000000 -2 1 2 U-236 0 0.000000 -3 1 2 U-238 0 0.000000 -4 1 2 Np-237 0 0.000000 -5 1 2 Pu-238 0 0.000000 -6 1 2 Pu-239 0 0.000000 -7 1 2 Pu-240 0 0.000000 -8 1 2 Pu-241 0 0.000000 -9 1 2 Pu-242 0 0.000000 -10 1 2 Am-241 0 0.000000 -11 1 2 Am-242m 0 0.000000 -12 1 2 Am-243 0 0.000000 -13 1 2 Cm-242 0 0.000000 -14 1 2 Cm-243 0 0.000000 -15 1 2 Cm-244 0 0.000000 -16 1 2 Cm-245 0 0.000000 -17 1 2 Mo-95 0 0.000000 -18 1 2 Tc-99 0 0.000000 -19 1 2 Ru-101 0 0.000000 -20 1 2 Ru-103 0 0.000000 -21 1 2 Ag-109 0 0.000000 -22 1 2 Xe-135 0 0.000000 -23 1 2 Cs-133 0 0.000000 -24 1 2 Nd-143 0 0.000000 -25 1 2 Nd-145 0 0.000000 -26 1 2 Sm-147 0 0.000000 -27 1 2 Sm-149 0 0.000000 -28 1 2 Sm-150 0 0.000000 -29 1 2 Sm-151 0 0.000000 -30 1 2 Sm-152 0 0.000000 -31 1 2 Eu-153 0 0.000000 -32 1 2 Gd-155 0 0.000000 -33 1 2 O-16 0 0.000000 material group in nuclide mean std. dev. +34 1 1 U-234 0.0 0.000000 +35 1 1 U-235 1.0 0.066362 +36 1 1 U-236 0.0 0.000000 +37 1 1 U-238 1.0 0.093082 +38 1 1 Np-237 0.0 0.000000 +39 1 1 Pu-238 0.0 0.000000 +40 1 1 Pu-239 1.0 0.104567 +41 1 1 Pu-240 0.0 0.000000 +42 1 1 Pu-241 1.0 0.263696 +43 1 1 Pu-242 0.0 0.000000 +44 1 1 Am-241 0.0 0.000000 +45 1 1 Am-242m 0.0 0.000000 +46 1 1 Am-243 0.0 0.000000 +47 1 1 Cm-242 0.0 0.000000 +48 1 1 Cm-243 0.0 0.000000 +49 1 1 Cm-244 0.0 0.000000 +50 1 1 Cm-245 0.0 0.000000 +51 1 1 Mo-95 0.0 0.000000 +52 1 1 Tc-99 0.0 0.000000 +53 1 1 Ru-101 0.0 0.000000 +54 1 1 Ru-103 0.0 0.000000 +55 1 1 Ag-109 0.0 0.000000 +56 1 1 Xe-135 0.0 0.000000 +57 1 1 Cs-133 0.0 0.000000 +58 1 1 Nd-143 0.0 0.000000 +59 1 1 Nd-145 0.0 0.000000 +60 1 1 Sm-147 0.0 0.000000 +61 1 1 Sm-149 0.0 0.000000 +62 1 1 Sm-150 0.0 0.000000 +63 1 1 Sm-151 0.0 0.000000 +64 1 1 Sm-152 0.0 0.000000 +65 1 1 Eu-153 0.0 0.000000 +66 1 1 Gd-155 0.0 0.000000 +67 1 1 O-16 0.0 0.000000 +0 1 2 U-234 0.0 0.000000 +1 1 2 U-235 0.0 0.000000 +2 1 2 U-236 0.0 0.000000 +3 1 2 U-238 0.0 0.000000 +4 1 2 Np-237 0.0 0.000000 +5 1 2 Pu-238 0.0 0.000000 +6 1 2 Pu-239 0.0 0.000000 +7 1 2 Pu-240 0.0 0.000000 +8 1 2 Pu-241 0.0 0.000000 +9 1 2 Pu-242 0.0 0.000000 +10 1 2 Am-241 0.0 0.000000 +11 1 2 Am-242m 0.0 0.000000 +12 1 2 Am-243 0.0 0.000000 +13 1 2 Cm-242 0.0 0.000000 +14 1 2 Cm-243 0.0 0.000000 +15 1 2 Cm-244 0.0 0.000000 +16 1 2 Cm-245 0.0 0.000000 +17 1 2 Mo-95 0.0 0.000000 +18 1 2 Tc-99 0.0 0.000000 +19 1 2 Ru-101 0.0 0.000000 +20 1 2 Ru-103 0.0 0.000000 +21 1 2 Ag-109 0.0 0.000000 +22 1 2 Xe-135 0.0 0.000000 +23 1 2 Cs-133 0.0 0.000000 +24 1 2 Nd-143 0.0 0.000000 +25 1 2 Nd-145 0.0 0.000000 +26 1 2 Sm-147 0.0 0.000000 +27 1 2 Sm-149 0.0 0.000000 +28 1 2 Sm-150 0.0 0.000000 +29 1 2 Sm-151 0.0 0.000000 +30 1 2 Sm-152 0.0 0.000000 +31 1 2 Eu-153 0.0 0.000000 +32 1 2 Gd-155 0.0 0.000000 +33 1 2 O-16 0.0 0.000000 material group in nuclide mean std. dev. 5 2 1 Zr-90 0.104734 0.008915 6 2 1 Zr-91 0.036155 0.003735 7 2 1 Zr-92 0.042422 0.003029 @@ -349,16 +349,16 @@ 2 2 2 Zr-92 0.041633 0.016323 3 2 2 Zr-94 0.060818 0.021483 4 2 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0 0 -6 2 1 Zr-91 0 0 -7 2 1 Zr-92 0 0 -8 2 1 Zr-94 0 0 -9 2 1 Zr-96 0 0 -0 2 2 Zr-90 0 0 -1 2 2 Zr-91 0 0 -2 2 2 Zr-92 0 0 -3 2 2 Zr-94 0 0 -4 2 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +5 2 1 Zr-90 0.0 0.0 +6 2 1 Zr-91 0.0 0.0 +7 2 1 Zr-92 0.0 0.0 +8 2 1 Zr-94 0.0 0.0 +9 2 1 Zr-96 0.0 0.0 +0 2 2 Zr-90 0.0 0.0 +1 2 2 Zr-91 0.0 0.0 +2 2 2 Zr-92 0.0 0.0 +3 2 2 Zr-94 0.0 0.0 +4 2 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 15 2 1 1 Zr-90 P0 0.104734 0.008915 P0 16 2 1 1 Zr-91 P0 0.036155 0.003735 P0 17 2 1 1 Zr-92 P0 0.042422 0.003029 P0 @@ -379,16 +379,16 @@ 2 2 2 2 Zr-92 P0 0.041633 0.016323 P0 3 2 2 2 Zr-94 P0 0.060818 0.021483 P0 4 2 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -5 2 1 Zr-90 0 0 -6 2 1 Zr-91 0 0 -7 2 1 Zr-92 0 0 -8 2 1 Zr-94 0 0 -9 2 1 Zr-96 0 0 -0 2 2 Zr-90 0 0 -1 2 2 Zr-91 0 0 -2 2 2 Zr-92 0 0 -3 2 2 Zr-94 0 0 -4 2 2 Zr-96 0 0 material group in nuclide mean std. dev. +5 2 1 Zr-90 0.0 0.0 +6 2 1 Zr-91 0.0 0.0 +7 2 1 Zr-92 0.0 0.0 +8 2 1 Zr-94 0.0 0.0 +9 2 1 Zr-96 0.0 0.0 +0 2 2 Zr-90 0.0 0.0 +1 2 2 Zr-91 0.0 0.0 +2 2 2 Zr-92 0.0 0.0 +3 2 2 Zr-94 0.0 0.0 +4 2 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. 4 3 1 H-1 0.207103 0.023028 5 3 1 O-16 0.079282 0.005197 6 3 1 B-10 0.000521 0.000244 @@ -397,14 +397,14 @@ 1 3 2 O-16 0.085363 0.014001 2 3 2 B-10 0.049249 0.008232 3 3 2 B-11 0.000195 0.001527 material group in nuclide mean std. dev. -4 3 1 H-1 0 0 -5 3 1 O-16 0 0 -6 3 1 B-10 0 0 -7 3 1 B-11 0 0 -0 3 2 H-1 0 0 -1 3 2 O-16 0 0 -2 3 2 B-10 0 0 -3 3 2 B-11 0 0 material group in group out nuclide moment mean std. dev. moment +4 3 1 H-1 0.0 0.0 +5 3 1 O-16 0.0 0.0 +6 3 1 B-10 0.0 0.0 +7 3 1 B-11 0.0 0.0 +0 3 2 H-1 0.0 0.0 +1 3 2 O-16 0.0 0.0 +2 3 2 B-10 0.0 0.0 +3 3 2 B-11 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 12 3 1 1 H-1 P0 0.181306 0.022102 P0 13 3 1 1 O-16 P0 0.078631 0.005044 P0 14 3 1 1 B-10 P0 0.000000 0.000000 P0 @@ -421,14 +421,14 @@ 1 3 2 2 O-16 P0 0.085363 0.014001 P0 2 3 2 2 B-10 P0 0.000000 0.000000 P0 3 3 2 2 B-11 P0 0.000195 0.001527 P0 material group out nuclide mean std. dev. -4 3 1 H-1 0 0 -5 3 1 O-16 0 0 -6 3 1 B-10 0 0 -7 3 1 B-11 0 0 -0 3 2 H-1 0 0 -1 3 2 O-16 0 0 -2 3 2 B-10 0 0 -3 3 2 B-11 0 0 material group in nuclide mean std. dev. +4 3 1 H-1 0.0 0.0 +5 3 1 O-16 0.0 0.0 +6 3 1 B-10 0.0 0.0 +7 3 1 B-11 0.0 0.0 +0 3 2 H-1 0.0 0.0 +1 3 2 O-16 0.0 0.0 +2 3 2 B-10 0.0 0.0 +3 3 2 B-11 0.0 0.0 material group in nuclide mean std. dev. 4 4 1 H-1 0.175242 0.053715 5 4 1 O-16 0.066545 0.010083 6 4 1 B-10 0.000570 0.000352 @@ -437,14 +437,14 @@ 1 4 2 O-16 0.085141 0.028073 2 4 2 B-10 0.025923 0.007276 3 4 2 B-11 0.000000 0.000000 material group in nuclide mean std. dev. -4 4 1 H-1 0 0 -5 4 1 O-16 0 0 -6 4 1 B-10 0 0 -7 4 1 B-11 0 0 -0 4 2 H-1 0 0 -1 4 2 O-16 0 0 -2 4 2 B-10 0 0 -3 4 2 B-11 0 0 material group in group out nuclide moment mean std. dev. moment +4 4 1 H-1 0.0 0.0 +5 4 1 O-16 0.0 0.0 +6 4 1 B-10 0.0 0.0 +7 4 1 B-11 0.0 0.0 +0 4 2 H-1 0.0 0.0 +1 4 2 O-16 0.0 0.0 +2 4 2 B-10 0.0 0.0 +3 4 2 B-11 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 12 4 1 1 H-1 P0 0.151295 0.051491 P0 13 4 1 1 O-16 P0 0.066545 0.010083 P0 14 4 1 1 B-10 P0 0.000000 0.000000 P0 @@ -461,914 +461,914 @@ 1 4 2 2 O-16 P0 0.085141 0.028073 P0 2 4 2 2 B-10 P0 0.000000 0.000000 P0 3 4 2 2 B-11 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -4 4 1 H-1 0 0 -5 4 1 O-16 0 0 -6 4 1 B-10 0 0 -7 4 1 B-11 0 0 -0 4 2 H-1 0 0 -1 4 2 O-16 0 0 -2 4 2 B-10 0 0 -3 4 2 B-11 0 0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in group out nuclide moment mean std. dev. moment -81 5 1 1 Fe-54 P0 0 0 P0 -82 5 1 1 Fe-56 P0 0 0 P0 -83 5 1 1 Fe-57 P0 0 0 P0 -84 5 1 1 Fe-58 P0 0 0 P0 -85 5 1 1 Ni-58 P0 0 0 P0 -86 5 1 1 Ni-60 P0 0 0 P0 -87 5 1 1 Ni-61 P0 0 0 P0 -88 5 1 1 Ni-62 P0 0 0 P0 -89 5 1 1 Ni-64 P0 0 0 P0 -90 5 1 1 Mn-55 P0 0 0 P0 -91 5 1 1 Mo-92 P0 0 0 P0 -92 5 1 1 Mo-94 P0 0 0 P0 -93 5 1 1 Mo-95 P0 0 0 P0 -94 5 1 1 Mo-96 P0 0 0 P0 -95 5 1 1 Mo-97 P0 0 0 P0 -96 5 1 1 Mo-98 P0 0 0 P0 -97 5 1 1 Mo-100 P0 0 0 P0 -98 5 1 1 Si-28 P0 0 0 P0 -99 5 1 1 Si-29 P0 0 0 P0 -100 5 1 1 Si-30 P0 0 0 P0 -101 5 1 1 Cr-50 P0 0 0 P0 -102 5 1 1 Cr-52 P0 0 0 P0 -103 5 1 1 Cr-53 P0 0 0 P0 -104 5 1 1 Cr-54 P0 0 0 P0 -105 5 1 1 C-Nat P0 0 0 P0 -106 5 1 1 Cu-63 P0 0 0 P0 -107 5 1 1 Cu-65 P0 0 0 P0 -54 5 1 2 Fe-54 P0 0 0 P0 -55 5 1 2 Fe-56 P0 0 0 P0 -56 5 1 2 Fe-57 P0 0 0 P0 -57 5 1 2 Fe-58 P0 0 0 P0 -58 5 1 2 Ni-58 P0 0 0 P0 -59 5 1 2 Ni-60 P0 0 0 P0 -60 5 1 2 Ni-61 P0 0 0 P0 -61 5 1 2 Ni-62 P0 0 0 P0 -62 5 1 2 Ni-64 P0 0 0 P0 -63 5 1 2 Mn-55 P0 0 0 P0 -64 5 1 2 Mo-92 P0 0 0 P0 -65 5 1 2 Mo-94 P0 0 0 P0 -66 5 1 2 Mo-95 P0 0 0 P0 -67 5 1 2 Mo-96 P0 0 0 P0 -68 5 1 2 Mo-97 P0 0 0 P0 -69 5 1 2 Mo-98 P0 0 0 P0 -70 5 1 2 Mo-100 P0 0 0 P0 -71 5 1 2 Si-28 P0 0 0 P0 -72 5 1 2 Si-29 P0 0 0 P0 -73 5 1 2 Si-30 P0 0 0 P0 -74 5 1 2 Cr-50 P0 0 0 P0 -75 5 1 2 Cr-52 P0 0 0 P0 -76 5 1 2 Cr-53 P0 0 0 P0 -77 5 1 2 Cr-54 P0 0 0 P0 -78 5 1 2 C-Nat P0 0 0 P0 -79 5 1 2 Cu-63 P0 0 0 P0 -80 5 1 2 Cu-65 P0 0 0 P0 -27 5 2 1 Fe-54 P0 0 0 P0 -28 5 2 1 Fe-56 P0 0 0 P0 -29 5 2 1 Fe-57 P0 0 0 P0 -30 5 2 1 Fe-58 P0 0 0 P0 -31 5 2 1 Ni-58 P0 0 0 P0 -32 5 2 1 Ni-60 P0 0 0 P0 -33 5 2 1 Ni-61 P0 0 0 P0 -34 5 2 1 Ni-62 P0 0 0 P0 -35 5 2 1 Ni-64 P0 0 0 P0 -36 5 2 1 Mn-55 P0 0 0 P0 -37 5 2 1 Mo-92 P0 0 0 P0 -38 5 2 1 Mo-94 P0 0 0 P0 -39 5 2 1 Mo-95 P0 0 0 P0 -40 5 2 1 Mo-96 P0 0 0 P0 -41 5 2 1 Mo-97 P0 0 0 P0 -42 5 2 1 Mo-98 P0 0 0 P0 -43 5 2 1 Mo-100 P0 0 0 P0 -44 5 2 1 Si-28 P0 0 0 P0 -45 5 2 1 Si-29 P0 0 0 P0 -46 5 2 1 Si-30 P0 0 0 P0 -47 5 2 1 Cr-50 P0 0 0 P0 -48 5 2 1 Cr-52 P0 0 0 P0 -49 5 2 1 Cr-53 P0 0 0 P0 -50 5 2 1 Cr-54 P0 0 0 P0 -51 5 2 1 C-Nat P0 0 0 P0 -52 5 2 1 Cu-63 P0 0 0 P0 -53 5 2 1 Cu-65 P0 0 0 P0 -0 5 2 2 Fe-54 P0 0 0 P0 -1 5 2 2 Fe-56 P0 0 0 P0 -2 5 2 2 Fe-57 P0 0 0 P0 -3 5 2 2 Fe-58 P0 0 0 P0 -4 5 2 2 Ni-58 P0 0 0 P0 -5 5 2 2 Ni-60 P0 0 0 P0 -6 5 2 2 Ni-61 P0 0 0 P0 -7 5 2 2 Ni-62 P0 0 0 P0 -8 5 2 2 Ni-64 P0 0 0 P0 -9 5 2 2 Mn-55 P0 0 0 P0 -10 5 2 2 Mo-92 P0 0 0 P0 -11 5 2 2 Mo-94 P0 0 0 P0 -12 5 2 2 Mo-95 P0 0 0 P0 -13 5 2 2 Mo-96 P0 0 0 P0 -14 5 2 2 Mo-97 P0 0 0 P0 -15 5 2 2 Mo-98 P0 0 0 P0 -16 5 2 2 Mo-100 P0 0 0 P0 -17 5 2 2 Si-28 P0 0 0 P0 -18 5 2 2 Si-29 P0 0 0 P0 -19 5 2 2 Si-30 P0 0 0 P0 -20 5 2 2 Cr-50 P0 0 0 P0 -21 5 2 2 Cr-52 P0 0 0 P0 -22 5 2 2 Cr-53 P0 0 0 P0 -23 5 2 2 Cr-54 P0 0 0 P0 -24 5 2 2 C-Nat P0 0 0 P0 -25 5 2 2 Cu-63 P0 0 0 P0 -26 5 2 2 Cu-65 P0 0 0 P0 material group out nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment -63 6 1 1 H-1 P0 0 0 P0 -64 6 1 1 O-16 P0 0 0 P0 -65 6 1 1 B-10 P0 0 0 P0 -66 6 1 1 B-11 P0 0 0 P0 -67 6 1 1 Fe-54 P0 0 0 P0 -68 6 1 1 Fe-56 P0 0 0 P0 -69 6 1 1 Fe-57 P0 0 0 P0 -70 6 1 1 Fe-58 P0 0 0 P0 -71 6 1 1 Ni-58 P0 0 0 P0 -72 6 1 1 Ni-60 P0 0 0 P0 -73 6 1 1 Ni-61 P0 0 0 P0 -74 6 1 1 Ni-62 P0 0 0 P0 -75 6 1 1 Ni-64 P0 0 0 P0 -76 6 1 1 Mn-55 P0 0 0 P0 -77 6 1 1 Si-28 P0 0 0 P0 -78 6 1 1 Si-29 P0 0 0 P0 -79 6 1 1 Si-30 P0 0 0 P0 -80 6 1 1 Cr-50 P0 0 0 P0 -81 6 1 1 Cr-52 P0 0 0 P0 -82 6 1 1 Cr-53 P0 0 0 P0 -83 6 1 1 Cr-54 P0 0 0 P0 -42 6 1 2 H-1 P0 0 0 P0 -43 6 1 2 O-16 P0 0 0 P0 -44 6 1 2 B-10 P0 0 0 P0 -45 6 1 2 B-11 P0 0 0 P0 -46 6 1 2 Fe-54 P0 0 0 P0 -47 6 1 2 Fe-56 P0 0 0 P0 -48 6 1 2 Fe-57 P0 0 0 P0 -49 6 1 2 Fe-58 P0 0 0 P0 -50 6 1 2 Ni-58 P0 0 0 P0 -51 6 1 2 Ni-60 P0 0 0 P0 -52 6 1 2 Ni-61 P0 0 0 P0 -53 6 1 2 Ni-62 P0 0 0 P0 -54 6 1 2 Ni-64 P0 0 0 P0 -55 6 1 2 Mn-55 P0 0 0 P0 -56 6 1 2 Si-28 P0 0 0 P0 -57 6 1 2 Si-29 P0 0 0 P0 -58 6 1 2 Si-30 P0 0 0 P0 -59 6 1 2 Cr-50 P0 0 0 P0 -60 6 1 2 Cr-52 P0 0 0 P0 -61 6 1 2 Cr-53 P0 0 0 P0 -62 6 1 2 Cr-54 P0 0 0 P0 -21 6 2 1 H-1 P0 0 0 P0 -22 6 2 1 O-16 P0 0 0 P0 -23 6 2 1 B-10 P0 0 0 P0 -24 6 2 1 B-11 P0 0 0 P0 -25 6 2 1 Fe-54 P0 0 0 P0 -26 6 2 1 Fe-56 P0 0 0 P0 -27 6 2 1 Fe-57 P0 0 0 P0 -28 6 2 1 Fe-58 P0 0 0 P0 -29 6 2 1 Ni-58 P0 0 0 P0 -30 6 2 1 Ni-60 P0 0 0 P0 -31 6 2 1 Ni-61 P0 0 0 P0 -32 6 2 1 Ni-62 P0 0 0 P0 -33 6 2 1 Ni-64 P0 0 0 P0 -34 6 2 1 Mn-55 P0 0 0 P0 -35 6 2 1 Si-28 P0 0 0 P0 -36 6 2 1 Si-29 P0 0 0 P0 -37 6 2 1 Si-30 P0 0 0 P0 -38 6 2 1 Cr-50 P0 0 0 P0 -39 6 2 1 Cr-52 P0 0 0 P0 -40 6 2 1 Cr-53 P0 0 0 P0 -41 6 2 1 Cr-54 P0 0 0 P0 -0 6 2 2 H-1 P0 0 0 P0 -1 6 2 2 O-16 P0 0 0 P0 -2 6 2 2 B-10 P0 0 0 P0 -3 6 2 2 B-11 P0 0 0 P0 -4 6 2 2 Fe-54 P0 0 0 P0 -5 6 2 2 Fe-56 P0 0 0 P0 -6 6 2 2 Fe-57 P0 0 0 P0 -7 6 2 2 Fe-58 P0 0 0 P0 -8 6 2 2 Ni-58 P0 0 0 P0 -9 6 2 2 Ni-60 P0 0 0 P0 -10 6 2 2 Ni-61 P0 0 0 P0 -11 6 2 2 Ni-62 P0 0 0 P0 -12 6 2 2 Ni-64 P0 0 0 P0 -13 6 2 2 Mn-55 P0 0 0 P0 -14 6 2 2 Si-28 P0 0 0 P0 -15 6 2 2 Si-29 P0 0 0 P0 -16 6 2 2 Si-30 P0 0 0 P0 -17 6 2 2 Cr-50 P0 0 0 P0 -18 6 2 2 Cr-52 P0 0 0 P0 -19 6 2 2 Cr-53 P0 0 0 P0 -20 6 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment -63 7 1 1 H-1 P0 0 0 P0 -64 7 1 1 O-16 P0 0 0 P0 -65 7 1 1 B-10 P0 0 0 P0 -66 7 1 1 B-11 P0 0 0 P0 -67 7 1 1 Fe-54 P0 0 0 P0 -68 7 1 1 Fe-56 P0 0 0 P0 -69 7 1 1 Fe-57 P0 0 0 P0 -70 7 1 1 Fe-58 P0 0 0 P0 -71 7 1 1 Ni-58 P0 0 0 P0 -72 7 1 1 Ni-60 P0 0 0 P0 -73 7 1 1 Ni-61 P0 0 0 P0 -74 7 1 1 Ni-62 P0 0 0 P0 -75 7 1 1 Ni-64 P0 0 0 P0 -76 7 1 1 Mn-55 P0 0 0 P0 -77 7 1 1 Si-28 P0 0 0 P0 -78 7 1 1 Si-29 P0 0 0 P0 -79 7 1 1 Si-30 P0 0 0 P0 -80 7 1 1 Cr-50 P0 0 0 P0 -81 7 1 1 Cr-52 P0 0 0 P0 -82 7 1 1 Cr-53 P0 0 0 P0 -83 7 1 1 Cr-54 P0 0 0 P0 -42 7 1 2 H-1 P0 0 0 P0 -43 7 1 2 O-16 P0 0 0 P0 -44 7 1 2 B-10 P0 0 0 P0 -45 7 1 2 B-11 P0 0 0 P0 -46 7 1 2 Fe-54 P0 0 0 P0 -47 7 1 2 Fe-56 P0 0 0 P0 -48 7 1 2 Fe-57 P0 0 0 P0 -49 7 1 2 Fe-58 P0 0 0 P0 -50 7 1 2 Ni-58 P0 0 0 P0 -51 7 1 2 Ni-60 P0 0 0 P0 -52 7 1 2 Ni-61 P0 0 0 P0 -53 7 1 2 Ni-62 P0 0 0 P0 -54 7 1 2 Ni-64 P0 0 0 P0 -55 7 1 2 Mn-55 P0 0 0 P0 -56 7 1 2 Si-28 P0 0 0 P0 -57 7 1 2 Si-29 P0 0 0 P0 -58 7 1 2 Si-30 P0 0 0 P0 -59 7 1 2 Cr-50 P0 0 0 P0 -60 7 1 2 Cr-52 P0 0 0 P0 -61 7 1 2 Cr-53 P0 0 0 P0 -62 7 1 2 Cr-54 P0 0 0 P0 -21 7 2 1 H-1 P0 0 0 P0 -22 7 2 1 O-16 P0 0 0 P0 -23 7 2 1 B-10 P0 0 0 P0 -24 7 2 1 B-11 P0 0 0 P0 -25 7 2 1 Fe-54 P0 0 0 P0 -26 7 2 1 Fe-56 P0 0 0 P0 -27 7 2 1 Fe-57 P0 0 0 P0 -28 7 2 1 Fe-58 P0 0 0 P0 -29 7 2 1 Ni-58 P0 0 0 P0 -30 7 2 1 Ni-60 P0 0 0 P0 -31 7 2 1 Ni-61 P0 0 0 P0 -32 7 2 1 Ni-62 P0 0 0 P0 -33 7 2 1 Ni-64 P0 0 0 P0 -34 7 2 1 Mn-55 P0 0 0 P0 -35 7 2 1 Si-28 P0 0 0 P0 -36 7 2 1 Si-29 P0 0 0 P0 -37 7 2 1 Si-30 P0 0 0 P0 -38 7 2 1 Cr-50 P0 0 0 P0 -39 7 2 1 Cr-52 P0 0 0 P0 -40 7 2 1 Cr-53 P0 0 0 P0 -41 7 2 1 Cr-54 P0 0 0 P0 -0 7 2 2 H-1 P0 0 0 P0 -1 7 2 2 O-16 P0 0 0 P0 -2 7 2 2 B-10 P0 0 0 P0 -3 7 2 2 B-11 P0 0 0 P0 -4 7 2 2 Fe-54 P0 0 0 P0 -5 7 2 2 Fe-56 P0 0 0 P0 -6 7 2 2 Fe-57 P0 0 0 P0 -7 7 2 2 Fe-58 P0 0 0 P0 -8 7 2 2 Ni-58 P0 0 0 P0 -9 7 2 2 Ni-60 P0 0 0 P0 -10 7 2 2 Ni-61 P0 0 0 P0 -11 7 2 2 Ni-62 P0 0 0 P0 -12 7 2 2 Ni-64 P0 0 0 P0 -13 7 2 2 Mn-55 P0 0 0 P0 -14 7 2 2 Si-28 P0 0 0 P0 -15 7 2 2 Si-29 P0 0 0 P0 -16 7 2 2 Si-30 P0 0 0 P0 -17 7 2 2 Cr-50 P0 0 0 P0 -18 7 2 2 Cr-52 P0 0 0 P0 -19 7 2 2 Cr-53 P0 0 0 P0 -20 7 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment -63 8 1 1 H-1 P0 0 0 P0 -64 8 1 1 O-16 P0 0 0 P0 -65 8 1 1 B-10 P0 0 0 P0 -66 8 1 1 B-11 P0 0 0 P0 -67 8 1 1 Fe-54 P0 0 0 P0 -68 8 1 1 Fe-56 P0 0 0 P0 -69 8 1 1 Fe-57 P0 0 0 P0 -70 8 1 1 Fe-58 P0 0 0 P0 -71 8 1 1 Ni-58 P0 0 0 P0 -72 8 1 1 Ni-60 P0 0 0 P0 -73 8 1 1 Ni-61 P0 0 0 P0 -74 8 1 1 Ni-62 P0 0 0 P0 -75 8 1 1 Ni-64 P0 0 0 P0 -76 8 1 1 Mn-55 P0 0 0 P0 -77 8 1 1 Si-28 P0 0 0 P0 -78 8 1 1 Si-29 P0 0 0 P0 -79 8 1 1 Si-30 P0 0 0 P0 -80 8 1 1 Cr-50 P0 0 0 P0 -81 8 1 1 Cr-52 P0 0 0 P0 -82 8 1 1 Cr-53 P0 0 0 P0 -83 8 1 1 Cr-54 P0 0 0 P0 -42 8 1 2 H-1 P0 0 0 P0 -43 8 1 2 O-16 P0 0 0 P0 -44 8 1 2 B-10 P0 0 0 P0 -45 8 1 2 B-11 P0 0 0 P0 -46 8 1 2 Fe-54 P0 0 0 P0 -47 8 1 2 Fe-56 P0 0 0 P0 -48 8 1 2 Fe-57 P0 0 0 P0 -49 8 1 2 Fe-58 P0 0 0 P0 -50 8 1 2 Ni-58 P0 0 0 P0 -51 8 1 2 Ni-60 P0 0 0 P0 -52 8 1 2 Ni-61 P0 0 0 P0 -53 8 1 2 Ni-62 P0 0 0 P0 -54 8 1 2 Ni-64 P0 0 0 P0 -55 8 1 2 Mn-55 P0 0 0 P0 -56 8 1 2 Si-28 P0 0 0 P0 -57 8 1 2 Si-29 P0 0 0 P0 -58 8 1 2 Si-30 P0 0 0 P0 -59 8 1 2 Cr-50 P0 0 0 P0 -60 8 1 2 Cr-52 P0 0 0 P0 -61 8 1 2 Cr-53 P0 0 0 P0 -62 8 1 2 Cr-54 P0 0 0 P0 -21 8 2 1 H-1 P0 0 0 P0 -22 8 2 1 O-16 P0 0 0 P0 -23 8 2 1 B-10 P0 0 0 P0 -24 8 2 1 B-11 P0 0 0 P0 -25 8 2 1 Fe-54 P0 0 0 P0 -26 8 2 1 Fe-56 P0 0 0 P0 -27 8 2 1 Fe-57 P0 0 0 P0 -28 8 2 1 Fe-58 P0 0 0 P0 -29 8 2 1 Ni-58 P0 0 0 P0 -30 8 2 1 Ni-60 P0 0 0 P0 -31 8 2 1 Ni-61 P0 0 0 P0 -32 8 2 1 Ni-62 P0 0 0 P0 -33 8 2 1 Ni-64 P0 0 0 P0 -34 8 2 1 Mn-55 P0 0 0 P0 -35 8 2 1 Si-28 P0 0 0 P0 -36 8 2 1 Si-29 P0 0 0 P0 -37 8 2 1 Si-30 P0 0 0 P0 -38 8 2 1 Cr-50 P0 0 0 P0 -39 8 2 1 Cr-52 P0 0 0 P0 -40 8 2 1 Cr-53 P0 0 0 P0 -41 8 2 1 Cr-54 P0 0 0 P0 -0 8 2 2 H-1 P0 0 0 P0 -1 8 2 2 O-16 P0 0 0 P0 -2 8 2 2 B-10 P0 0 0 P0 -3 8 2 2 B-11 P0 0 0 P0 -4 8 2 2 Fe-54 P0 0 0 P0 -5 8 2 2 Fe-56 P0 0 0 P0 -6 8 2 2 Fe-57 P0 0 0 P0 -7 8 2 2 Fe-58 P0 0 0 P0 -8 8 2 2 Ni-58 P0 0 0 P0 -9 8 2 2 Ni-60 P0 0 0 P0 -10 8 2 2 Ni-61 P0 0 0 P0 -11 8 2 2 Ni-62 P0 0 0 P0 -12 8 2 2 Ni-64 P0 0 0 P0 -13 8 2 2 Mn-55 P0 0 0 P0 -14 8 2 2 Si-28 P0 0 0 P0 -15 8 2 2 Si-29 P0 0 0 P0 -16 8 2 2 Si-30 P0 0 0 P0 -17 8 2 2 Cr-50 P0 0 0 P0 -18 8 2 2 Cr-52 P0 0 0 P0 -19 8 2 2 Cr-53 P0 0 0 P0 -20 8 2 2 Cr-54 P0 0 0 P0 material group out nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. +4 4 1 H-1 0.0 0.0 +5 4 1 O-16 0.0 0.0 +6 4 1 B-10 0.0 0.0 +7 4 1 B-11 0.0 0.0 +0 4 2 H-1 0.0 0.0 +1 4 2 O-16 0.0 0.0 +2 4 2 B-10 0.0 0.0 +3 4 2 B-11 0.0 0.0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0.0 0.0 +28 5 1 Fe-56 0.0 0.0 +29 5 1 Fe-57 0.0 0.0 +30 5 1 Fe-58 0.0 0.0 +31 5 1 Ni-58 0.0 0.0 +32 5 1 Ni-60 0.0 0.0 +33 5 1 Ni-61 0.0 0.0 +34 5 1 Ni-62 0.0 0.0 +35 5 1 Ni-64 0.0 0.0 +36 5 1 Mn-55 0.0 0.0 +37 5 1 Mo-92 0.0 0.0 +38 5 1 Mo-94 0.0 0.0 +39 5 1 Mo-95 0.0 0.0 +40 5 1 Mo-96 0.0 0.0 +41 5 1 Mo-97 0.0 0.0 +42 5 1 Mo-98 0.0 0.0 +43 5 1 Mo-100 0.0 0.0 +44 5 1 Si-28 0.0 0.0 +45 5 1 Si-29 0.0 0.0 +46 5 1 Si-30 0.0 0.0 +47 5 1 Cr-50 0.0 0.0 +48 5 1 Cr-52 0.0 0.0 +49 5 1 Cr-53 0.0 0.0 +50 5 1 Cr-54 0.0 0.0 +51 5 1 C-Nat 0.0 0.0 +52 5 1 Cu-63 0.0 0.0 +53 5 1 Cu-65 0.0 0.0 +0 5 2 Fe-54 0.0 0.0 +1 5 2 Fe-56 0.0 0.0 +2 5 2 Fe-57 0.0 0.0 +3 5 2 Fe-58 0.0 0.0 +4 5 2 Ni-58 0.0 0.0 +5 5 2 Ni-60 0.0 0.0 +6 5 2 Ni-61 0.0 0.0 +7 5 2 Ni-62 0.0 0.0 +8 5 2 Ni-64 0.0 0.0 +9 5 2 Mn-55 0.0 0.0 +10 5 2 Mo-92 0.0 0.0 +11 5 2 Mo-94 0.0 0.0 +12 5 2 Mo-95 0.0 0.0 +13 5 2 Mo-96 0.0 0.0 +14 5 2 Mo-97 0.0 0.0 +15 5 2 Mo-98 0.0 0.0 +16 5 2 Mo-100 0.0 0.0 +17 5 2 Si-28 0.0 0.0 +18 5 2 Si-29 0.0 0.0 +19 5 2 Si-30 0.0 0.0 +20 5 2 Cr-50 0.0 0.0 +21 5 2 Cr-52 0.0 0.0 +22 5 2 Cr-53 0.0 0.0 +23 5 2 Cr-54 0.0 0.0 +24 5 2 C-Nat 0.0 0.0 +25 5 2 Cu-63 0.0 0.0 +26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0.0 0.0 +28 5 1 Fe-56 0.0 0.0 +29 5 1 Fe-57 0.0 0.0 +30 5 1 Fe-58 0.0 0.0 +31 5 1 Ni-58 0.0 0.0 +32 5 1 Ni-60 0.0 0.0 +33 5 1 Ni-61 0.0 0.0 +34 5 1 Ni-62 0.0 0.0 +35 5 1 Ni-64 0.0 0.0 +36 5 1 Mn-55 0.0 0.0 +37 5 1 Mo-92 0.0 0.0 +38 5 1 Mo-94 0.0 0.0 +39 5 1 Mo-95 0.0 0.0 +40 5 1 Mo-96 0.0 0.0 +41 5 1 Mo-97 0.0 0.0 +42 5 1 Mo-98 0.0 0.0 +43 5 1 Mo-100 0.0 0.0 +44 5 1 Si-28 0.0 0.0 +45 5 1 Si-29 0.0 0.0 +46 5 1 Si-30 0.0 0.0 +47 5 1 Cr-50 0.0 0.0 +48 5 1 Cr-52 0.0 0.0 +49 5 1 Cr-53 0.0 0.0 +50 5 1 Cr-54 0.0 0.0 +51 5 1 C-Nat 0.0 0.0 +52 5 1 Cu-63 0.0 0.0 +53 5 1 Cu-65 0.0 0.0 +0 5 2 Fe-54 0.0 0.0 +1 5 2 Fe-56 0.0 0.0 +2 5 2 Fe-57 0.0 0.0 +3 5 2 Fe-58 0.0 0.0 +4 5 2 Ni-58 0.0 0.0 +5 5 2 Ni-60 0.0 0.0 +6 5 2 Ni-61 0.0 0.0 +7 5 2 Ni-62 0.0 0.0 +8 5 2 Ni-64 0.0 0.0 +9 5 2 Mn-55 0.0 0.0 +10 5 2 Mo-92 0.0 0.0 +11 5 2 Mo-94 0.0 0.0 +12 5 2 Mo-95 0.0 0.0 +13 5 2 Mo-96 0.0 0.0 +14 5 2 Mo-97 0.0 0.0 +15 5 2 Mo-98 0.0 0.0 +16 5 2 Mo-100 0.0 0.0 +17 5 2 Si-28 0.0 0.0 +18 5 2 Si-29 0.0 0.0 +19 5 2 Si-30 0.0 0.0 +20 5 2 Cr-50 0.0 0.0 +21 5 2 Cr-52 0.0 0.0 +22 5 2 Cr-53 0.0 0.0 +23 5 2 Cr-54 0.0 0.0 +24 5 2 C-Nat 0.0 0.0 +25 5 2 Cu-63 0.0 0.0 +26 5 2 Cu-65 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +81 5 1 1 Fe-54 P0 0.0 0.0 P0 +82 5 1 1 Fe-56 P0 0.0 0.0 P0 +83 5 1 1 Fe-57 P0 0.0 0.0 P0 +84 5 1 1 Fe-58 P0 0.0 0.0 P0 +85 5 1 1 Ni-58 P0 0.0 0.0 P0 +86 5 1 1 Ni-60 P0 0.0 0.0 P0 +87 5 1 1 Ni-61 P0 0.0 0.0 P0 +88 5 1 1 Ni-62 P0 0.0 0.0 P0 +89 5 1 1 Ni-64 P0 0.0 0.0 P0 +90 5 1 1 Mn-55 P0 0.0 0.0 P0 +91 5 1 1 Mo-92 P0 0.0 0.0 P0 +92 5 1 1 Mo-94 P0 0.0 0.0 P0 +93 5 1 1 Mo-95 P0 0.0 0.0 P0 +94 5 1 1 Mo-96 P0 0.0 0.0 P0 +95 5 1 1 Mo-97 P0 0.0 0.0 P0 +96 5 1 1 Mo-98 P0 0.0 0.0 P0 +97 5 1 1 Mo-100 P0 0.0 0.0 P0 +98 5 1 1 Si-28 P0 0.0 0.0 P0 +99 5 1 1 Si-29 P0 0.0 0.0 P0 +100 5 1 1 Si-30 P0 0.0 0.0 P0 +101 5 1 1 Cr-50 P0 0.0 0.0 P0 +102 5 1 1 Cr-52 P0 0.0 0.0 P0 +103 5 1 1 Cr-53 P0 0.0 0.0 P0 +104 5 1 1 Cr-54 P0 0.0 0.0 P0 +105 5 1 1 C-Nat P0 0.0 0.0 P0 +106 5 1 1 Cu-63 P0 0.0 0.0 P0 +107 5 1 1 Cu-65 P0 0.0 0.0 P0 +54 5 1 2 Fe-54 P0 0.0 0.0 P0 +55 5 1 2 Fe-56 P0 0.0 0.0 P0 +56 5 1 2 Fe-57 P0 0.0 0.0 P0 +57 5 1 2 Fe-58 P0 0.0 0.0 P0 +58 5 1 2 Ni-58 P0 0.0 0.0 P0 +59 5 1 2 Ni-60 P0 0.0 0.0 P0 +60 5 1 2 Ni-61 P0 0.0 0.0 P0 +61 5 1 2 Ni-62 P0 0.0 0.0 P0 +62 5 1 2 Ni-64 P0 0.0 0.0 P0 +63 5 1 2 Mn-55 P0 0.0 0.0 P0 +64 5 1 2 Mo-92 P0 0.0 0.0 P0 +65 5 1 2 Mo-94 P0 0.0 0.0 P0 +66 5 1 2 Mo-95 P0 0.0 0.0 P0 +67 5 1 2 Mo-96 P0 0.0 0.0 P0 +68 5 1 2 Mo-97 P0 0.0 0.0 P0 +69 5 1 2 Mo-98 P0 0.0 0.0 P0 +70 5 1 2 Mo-100 P0 0.0 0.0 P0 +71 5 1 2 Si-28 P0 0.0 0.0 P0 +72 5 1 2 Si-29 P0 0.0 0.0 P0 +73 5 1 2 Si-30 P0 0.0 0.0 P0 +74 5 1 2 Cr-50 P0 0.0 0.0 P0 +75 5 1 2 Cr-52 P0 0.0 0.0 P0 +76 5 1 2 Cr-53 P0 0.0 0.0 P0 +77 5 1 2 Cr-54 P0 0.0 0.0 P0 +78 5 1 2 C-Nat P0 0.0 0.0 P0 +79 5 1 2 Cu-63 P0 0.0 0.0 P0 +80 5 1 2 Cu-65 P0 0.0 0.0 P0 +27 5 2 1 Fe-54 P0 0.0 0.0 P0 +28 5 2 1 Fe-56 P0 0.0 0.0 P0 +29 5 2 1 Fe-57 P0 0.0 0.0 P0 +30 5 2 1 Fe-58 P0 0.0 0.0 P0 +31 5 2 1 Ni-58 P0 0.0 0.0 P0 +32 5 2 1 Ni-60 P0 0.0 0.0 P0 +33 5 2 1 Ni-61 P0 0.0 0.0 P0 +34 5 2 1 Ni-62 P0 0.0 0.0 P0 +35 5 2 1 Ni-64 P0 0.0 0.0 P0 +36 5 2 1 Mn-55 P0 0.0 0.0 P0 +37 5 2 1 Mo-92 P0 0.0 0.0 P0 +38 5 2 1 Mo-94 P0 0.0 0.0 P0 +39 5 2 1 Mo-95 P0 0.0 0.0 P0 +40 5 2 1 Mo-96 P0 0.0 0.0 P0 +41 5 2 1 Mo-97 P0 0.0 0.0 P0 +42 5 2 1 Mo-98 P0 0.0 0.0 P0 +43 5 2 1 Mo-100 P0 0.0 0.0 P0 +44 5 2 1 Si-28 P0 0.0 0.0 P0 +45 5 2 1 Si-29 P0 0.0 0.0 P0 +46 5 2 1 Si-30 P0 0.0 0.0 P0 +47 5 2 1 Cr-50 P0 0.0 0.0 P0 +48 5 2 1 Cr-52 P0 0.0 0.0 P0 +49 5 2 1 Cr-53 P0 0.0 0.0 P0 +50 5 2 1 Cr-54 P0 0.0 0.0 P0 +51 5 2 1 C-Nat P0 0.0 0.0 P0 +52 5 2 1 Cu-63 P0 0.0 0.0 P0 +53 5 2 1 Cu-65 P0 0.0 0.0 P0 +0 5 2 2 Fe-54 P0 0.0 0.0 P0 +1 5 2 2 Fe-56 P0 0.0 0.0 P0 +2 5 2 2 Fe-57 P0 0.0 0.0 P0 +3 5 2 2 Fe-58 P0 0.0 0.0 P0 +4 5 2 2 Ni-58 P0 0.0 0.0 P0 +5 5 2 2 Ni-60 P0 0.0 0.0 P0 +6 5 2 2 Ni-61 P0 0.0 0.0 P0 +7 5 2 2 Ni-62 P0 0.0 0.0 P0 +8 5 2 2 Ni-64 P0 0.0 0.0 P0 +9 5 2 2 Mn-55 P0 0.0 0.0 P0 +10 5 2 2 Mo-92 P0 0.0 0.0 P0 +11 5 2 2 Mo-94 P0 0.0 0.0 P0 +12 5 2 2 Mo-95 P0 0.0 0.0 P0 +13 5 2 2 Mo-96 P0 0.0 0.0 P0 +14 5 2 2 Mo-97 P0 0.0 0.0 P0 +15 5 2 2 Mo-98 P0 0.0 0.0 P0 +16 5 2 2 Mo-100 P0 0.0 0.0 P0 +17 5 2 2 Si-28 P0 0.0 0.0 P0 +18 5 2 2 Si-29 P0 0.0 0.0 P0 +19 5 2 2 Si-30 P0 0.0 0.0 P0 +20 5 2 2 Cr-50 P0 0.0 0.0 P0 +21 5 2 2 Cr-52 P0 0.0 0.0 P0 +22 5 2 2 Cr-53 P0 0.0 0.0 P0 +23 5 2 2 Cr-54 P0 0.0 0.0 P0 +24 5 2 2 C-Nat P0 0.0 0.0 P0 +25 5 2 2 Cu-63 P0 0.0 0.0 P0 +26 5 2 2 Cu-65 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +27 5 1 Fe-54 0.0 0.0 +28 5 1 Fe-56 0.0 0.0 +29 5 1 Fe-57 0.0 0.0 +30 5 1 Fe-58 0.0 0.0 +31 5 1 Ni-58 0.0 0.0 +32 5 1 Ni-60 0.0 0.0 +33 5 1 Ni-61 0.0 0.0 +34 5 1 Ni-62 0.0 0.0 +35 5 1 Ni-64 0.0 0.0 +36 5 1 Mn-55 0.0 0.0 +37 5 1 Mo-92 0.0 0.0 +38 5 1 Mo-94 0.0 0.0 +39 5 1 Mo-95 0.0 0.0 +40 5 1 Mo-96 0.0 0.0 +41 5 1 Mo-97 0.0 0.0 +42 5 1 Mo-98 0.0 0.0 +43 5 1 Mo-100 0.0 0.0 +44 5 1 Si-28 0.0 0.0 +45 5 1 Si-29 0.0 0.0 +46 5 1 Si-30 0.0 0.0 +47 5 1 Cr-50 0.0 0.0 +48 5 1 Cr-52 0.0 0.0 +49 5 1 Cr-53 0.0 0.0 +50 5 1 Cr-54 0.0 0.0 +51 5 1 C-Nat 0.0 0.0 +52 5 1 Cu-63 0.0 0.0 +53 5 1 Cu-65 0.0 0.0 +0 5 2 Fe-54 0.0 0.0 +1 5 2 Fe-56 0.0 0.0 +2 5 2 Fe-57 0.0 0.0 +3 5 2 Fe-58 0.0 0.0 +4 5 2 Ni-58 0.0 0.0 +5 5 2 Ni-60 0.0 0.0 +6 5 2 Ni-61 0.0 0.0 +7 5 2 Ni-62 0.0 0.0 +8 5 2 Ni-64 0.0 0.0 +9 5 2 Mn-55 0.0 0.0 +10 5 2 Mo-92 0.0 0.0 +11 5 2 Mo-94 0.0 0.0 +12 5 2 Mo-95 0.0 0.0 +13 5 2 Mo-96 0.0 0.0 +14 5 2 Mo-97 0.0 0.0 +15 5 2 Mo-98 0.0 0.0 +16 5 2 Mo-100 0.0 0.0 +17 5 2 Si-28 0.0 0.0 +18 5 2 Si-29 0.0 0.0 +19 5 2 Si-30 0.0 0.0 +20 5 2 Cr-50 0.0 0.0 +21 5 2 Cr-52 0.0 0.0 +22 5 2 Cr-53 0.0 0.0 +23 5 2 Cr-54 0.0 0.0 +24 5 2 C-Nat 0.0 0.0 +25 5 2 Cu-63 0.0 0.0 +26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. +21 6 1 H-1 0.0 0.0 +22 6 1 O-16 0.0 0.0 +23 6 1 B-10 0.0 0.0 +24 6 1 B-11 0.0 0.0 +25 6 1 Fe-54 0.0 0.0 +26 6 1 Fe-56 0.0 0.0 +27 6 1 Fe-57 0.0 0.0 +28 6 1 Fe-58 0.0 0.0 +29 6 1 Ni-58 0.0 0.0 +30 6 1 Ni-60 0.0 0.0 +31 6 1 Ni-61 0.0 0.0 +32 6 1 Ni-62 0.0 0.0 +33 6 1 Ni-64 0.0 0.0 +34 6 1 Mn-55 0.0 0.0 +35 6 1 Si-28 0.0 0.0 +36 6 1 Si-29 0.0 0.0 +37 6 1 Si-30 0.0 0.0 +38 6 1 Cr-50 0.0 0.0 +39 6 1 Cr-52 0.0 0.0 +40 6 1 Cr-53 0.0 0.0 +41 6 1 Cr-54 0.0 0.0 +0 6 2 H-1 0.0 0.0 +1 6 2 O-16 0.0 0.0 +2 6 2 B-10 0.0 0.0 +3 6 2 B-11 0.0 0.0 +4 6 2 Fe-54 0.0 0.0 +5 6 2 Fe-56 0.0 0.0 +6 6 2 Fe-57 0.0 0.0 +7 6 2 Fe-58 0.0 0.0 +8 6 2 Ni-58 0.0 0.0 +9 6 2 Ni-60 0.0 0.0 +10 6 2 Ni-61 0.0 0.0 +11 6 2 Ni-62 0.0 0.0 +12 6 2 Ni-64 0.0 0.0 +13 6 2 Mn-55 0.0 0.0 +14 6 2 Si-28 0.0 0.0 +15 6 2 Si-29 0.0 0.0 +16 6 2 Si-30 0.0 0.0 +17 6 2 Cr-50 0.0 0.0 +18 6 2 Cr-52 0.0 0.0 +19 6 2 Cr-53 0.0 0.0 +20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 6 1 H-1 0.0 0.0 +22 6 1 O-16 0.0 0.0 +23 6 1 B-10 0.0 0.0 +24 6 1 B-11 0.0 0.0 +25 6 1 Fe-54 0.0 0.0 +26 6 1 Fe-56 0.0 0.0 +27 6 1 Fe-57 0.0 0.0 +28 6 1 Fe-58 0.0 0.0 +29 6 1 Ni-58 0.0 0.0 +30 6 1 Ni-60 0.0 0.0 +31 6 1 Ni-61 0.0 0.0 +32 6 1 Ni-62 0.0 0.0 +33 6 1 Ni-64 0.0 0.0 +34 6 1 Mn-55 0.0 0.0 +35 6 1 Si-28 0.0 0.0 +36 6 1 Si-29 0.0 0.0 +37 6 1 Si-30 0.0 0.0 +38 6 1 Cr-50 0.0 0.0 +39 6 1 Cr-52 0.0 0.0 +40 6 1 Cr-53 0.0 0.0 +41 6 1 Cr-54 0.0 0.0 +0 6 2 H-1 0.0 0.0 +1 6 2 O-16 0.0 0.0 +2 6 2 B-10 0.0 0.0 +3 6 2 B-11 0.0 0.0 +4 6 2 Fe-54 0.0 0.0 +5 6 2 Fe-56 0.0 0.0 +6 6 2 Fe-57 0.0 0.0 +7 6 2 Fe-58 0.0 0.0 +8 6 2 Ni-58 0.0 0.0 +9 6 2 Ni-60 0.0 0.0 +10 6 2 Ni-61 0.0 0.0 +11 6 2 Ni-62 0.0 0.0 +12 6 2 Ni-64 0.0 0.0 +13 6 2 Mn-55 0.0 0.0 +14 6 2 Si-28 0.0 0.0 +15 6 2 Si-29 0.0 0.0 +16 6 2 Si-30 0.0 0.0 +17 6 2 Cr-50 0.0 0.0 +18 6 2 Cr-52 0.0 0.0 +19 6 2 Cr-53 0.0 0.0 +20 6 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +63 6 1 1 H-1 P0 0.0 0.0 P0 +64 6 1 1 O-16 P0 0.0 0.0 P0 +65 6 1 1 B-10 P0 0.0 0.0 P0 +66 6 1 1 B-11 P0 0.0 0.0 P0 +67 6 1 1 Fe-54 P0 0.0 0.0 P0 +68 6 1 1 Fe-56 P0 0.0 0.0 P0 +69 6 1 1 Fe-57 P0 0.0 0.0 P0 +70 6 1 1 Fe-58 P0 0.0 0.0 P0 +71 6 1 1 Ni-58 P0 0.0 0.0 P0 +72 6 1 1 Ni-60 P0 0.0 0.0 P0 +73 6 1 1 Ni-61 P0 0.0 0.0 P0 +74 6 1 1 Ni-62 P0 0.0 0.0 P0 +75 6 1 1 Ni-64 P0 0.0 0.0 P0 +76 6 1 1 Mn-55 P0 0.0 0.0 P0 +77 6 1 1 Si-28 P0 0.0 0.0 P0 +78 6 1 1 Si-29 P0 0.0 0.0 P0 +79 6 1 1 Si-30 P0 0.0 0.0 P0 +80 6 1 1 Cr-50 P0 0.0 0.0 P0 +81 6 1 1 Cr-52 P0 0.0 0.0 P0 +82 6 1 1 Cr-53 P0 0.0 0.0 P0 +83 6 1 1 Cr-54 P0 0.0 0.0 P0 +42 6 1 2 H-1 P0 0.0 0.0 P0 +43 6 1 2 O-16 P0 0.0 0.0 P0 +44 6 1 2 B-10 P0 0.0 0.0 P0 +45 6 1 2 B-11 P0 0.0 0.0 P0 +46 6 1 2 Fe-54 P0 0.0 0.0 P0 +47 6 1 2 Fe-56 P0 0.0 0.0 P0 +48 6 1 2 Fe-57 P0 0.0 0.0 P0 +49 6 1 2 Fe-58 P0 0.0 0.0 P0 +50 6 1 2 Ni-58 P0 0.0 0.0 P0 +51 6 1 2 Ni-60 P0 0.0 0.0 P0 +52 6 1 2 Ni-61 P0 0.0 0.0 P0 +53 6 1 2 Ni-62 P0 0.0 0.0 P0 +54 6 1 2 Ni-64 P0 0.0 0.0 P0 +55 6 1 2 Mn-55 P0 0.0 0.0 P0 +56 6 1 2 Si-28 P0 0.0 0.0 P0 +57 6 1 2 Si-29 P0 0.0 0.0 P0 +58 6 1 2 Si-30 P0 0.0 0.0 P0 +59 6 1 2 Cr-50 P0 0.0 0.0 P0 +60 6 1 2 Cr-52 P0 0.0 0.0 P0 +61 6 1 2 Cr-53 P0 0.0 0.0 P0 +62 6 1 2 Cr-54 P0 0.0 0.0 P0 +21 6 2 1 H-1 P0 0.0 0.0 P0 +22 6 2 1 O-16 P0 0.0 0.0 P0 +23 6 2 1 B-10 P0 0.0 0.0 P0 +24 6 2 1 B-11 P0 0.0 0.0 P0 +25 6 2 1 Fe-54 P0 0.0 0.0 P0 +26 6 2 1 Fe-56 P0 0.0 0.0 P0 +27 6 2 1 Fe-57 P0 0.0 0.0 P0 +28 6 2 1 Fe-58 P0 0.0 0.0 P0 +29 6 2 1 Ni-58 P0 0.0 0.0 P0 +30 6 2 1 Ni-60 P0 0.0 0.0 P0 +31 6 2 1 Ni-61 P0 0.0 0.0 P0 +32 6 2 1 Ni-62 P0 0.0 0.0 P0 +33 6 2 1 Ni-64 P0 0.0 0.0 P0 +34 6 2 1 Mn-55 P0 0.0 0.0 P0 +35 6 2 1 Si-28 P0 0.0 0.0 P0 +36 6 2 1 Si-29 P0 0.0 0.0 P0 +37 6 2 1 Si-30 P0 0.0 0.0 P0 +38 6 2 1 Cr-50 P0 0.0 0.0 P0 +39 6 2 1 Cr-52 P0 0.0 0.0 P0 +40 6 2 1 Cr-53 P0 0.0 0.0 P0 +41 6 2 1 Cr-54 P0 0.0 0.0 P0 +0 6 2 2 H-1 P0 0.0 0.0 P0 +1 6 2 2 O-16 P0 0.0 0.0 P0 +2 6 2 2 B-10 P0 0.0 0.0 P0 +3 6 2 2 B-11 P0 0.0 0.0 P0 +4 6 2 2 Fe-54 P0 0.0 0.0 P0 +5 6 2 2 Fe-56 P0 0.0 0.0 P0 +6 6 2 2 Fe-57 P0 0.0 0.0 P0 +7 6 2 2 Fe-58 P0 0.0 0.0 P0 +8 6 2 2 Ni-58 P0 0.0 0.0 P0 +9 6 2 2 Ni-60 P0 0.0 0.0 P0 +10 6 2 2 Ni-61 P0 0.0 0.0 P0 +11 6 2 2 Ni-62 P0 0.0 0.0 P0 +12 6 2 2 Ni-64 P0 0.0 0.0 P0 +13 6 2 2 Mn-55 P0 0.0 0.0 P0 +14 6 2 2 Si-28 P0 0.0 0.0 P0 +15 6 2 2 Si-29 P0 0.0 0.0 P0 +16 6 2 2 Si-30 P0 0.0 0.0 P0 +17 6 2 2 Cr-50 P0 0.0 0.0 P0 +18 6 2 2 Cr-52 P0 0.0 0.0 P0 +19 6 2 2 Cr-53 P0 0.0 0.0 P0 +20 6 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +21 6 1 H-1 0.0 0.0 +22 6 1 O-16 0.0 0.0 +23 6 1 B-10 0.0 0.0 +24 6 1 B-11 0.0 0.0 +25 6 1 Fe-54 0.0 0.0 +26 6 1 Fe-56 0.0 0.0 +27 6 1 Fe-57 0.0 0.0 +28 6 1 Fe-58 0.0 0.0 +29 6 1 Ni-58 0.0 0.0 +30 6 1 Ni-60 0.0 0.0 +31 6 1 Ni-61 0.0 0.0 +32 6 1 Ni-62 0.0 0.0 +33 6 1 Ni-64 0.0 0.0 +34 6 1 Mn-55 0.0 0.0 +35 6 1 Si-28 0.0 0.0 +36 6 1 Si-29 0.0 0.0 +37 6 1 Si-30 0.0 0.0 +38 6 1 Cr-50 0.0 0.0 +39 6 1 Cr-52 0.0 0.0 +40 6 1 Cr-53 0.0 0.0 +41 6 1 Cr-54 0.0 0.0 +0 6 2 H-1 0.0 0.0 +1 6 2 O-16 0.0 0.0 +2 6 2 B-10 0.0 0.0 +3 6 2 B-11 0.0 0.0 +4 6 2 Fe-54 0.0 0.0 +5 6 2 Fe-56 0.0 0.0 +6 6 2 Fe-57 0.0 0.0 +7 6 2 Fe-58 0.0 0.0 +8 6 2 Ni-58 0.0 0.0 +9 6 2 Ni-60 0.0 0.0 +10 6 2 Ni-61 0.0 0.0 +11 6 2 Ni-62 0.0 0.0 +12 6 2 Ni-64 0.0 0.0 +13 6 2 Mn-55 0.0 0.0 +14 6 2 Si-28 0.0 0.0 +15 6 2 Si-29 0.0 0.0 +16 6 2 Si-30 0.0 0.0 +17 6 2 Cr-50 0.0 0.0 +18 6 2 Cr-52 0.0 0.0 +19 6 2 Cr-53 0.0 0.0 +20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 7 1 H-1 0.0 0.0 +22 7 1 O-16 0.0 0.0 +23 7 1 B-10 0.0 0.0 +24 7 1 B-11 0.0 0.0 +25 7 1 Fe-54 0.0 0.0 +26 7 1 Fe-56 0.0 0.0 +27 7 1 Fe-57 0.0 0.0 +28 7 1 Fe-58 0.0 0.0 +29 7 1 Ni-58 0.0 0.0 +30 7 1 Ni-60 0.0 0.0 +31 7 1 Ni-61 0.0 0.0 +32 7 1 Ni-62 0.0 0.0 +33 7 1 Ni-64 0.0 0.0 +34 7 1 Mn-55 0.0 0.0 +35 7 1 Si-28 0.0 0.0 +36 7 1 Si-29 0.0 0.0 +37 7 1 Si-30 0.0 0.0 +38 7 1 Cr-50 0.0 0.0 +39 7 1 Cr-52 0.0 0.0 +40 7 1 Cr-53 0.0 0.0 +41 7 1 Cr-54 0.0 0.0 +0 7 2 H-1 0.0 0.0 +1 7 2 O-16 0.0 0.0 +2 7 2 B-10 0.0 0.0 +3 7 2 B-11 0.0 0.0 +4 7 2 Fe-54 0.0 0.0 +5 7 2 Fe-56 0.0 0.0 +6 7 2 Fe-57 0.0 0.0 +7 7 2 Fe-58 0.0 0.0 +8 7 2 Ni-58 0.0 0.0 +9 7 2 Ni-60 0.0 0.0 +10 7 2 Ni-61 0.0 0.0 +11 7 2 Ni-62 0.0 0.0 +12 7 2 Ni-64 0.0 0.0 +13 7 2 Mn-55 0.0 0.0 +14 7 2 Si-28 0.0 0.0 +15 7 2 Si-29 0.0 0.0 +16 7 2 Si-30 0.0 0.0 +17 7 2 Cr-50 0.0 0.0 +18 7 2 Cr-52 0.0 0.0 +19 7 2 Cr-53 0.0 0.0 +20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 7 1 H-1 0.0 0.0 +22 7 1 O-16 0.0 0.0 +23 7 1 B-10 0.0 0.0 +24 7 1 B-11 0.0 0.0 +25 7 1 Fe-54 0.0 0.0 +26 7 1 Fe-56 0.0 0.0 +27 7 1 Fe-57 0.0 0.0 +28 7 1 Fe-58 0.0 0.0 +29 7 1 Ni-58 0.0 0.0 +30 7 1 Ni-60 0.0 0.0 +31 7 1 Ni-61 0.0 0.0 +32 7 1 Ni-62 0.0 0.0 +33 7 1 Ni-64 0.0 0.0 +34 7 1 Mn-55 0.0 0.0 +35 7 1 Si-28 0.0 0.0 +36 7 1 Si-29 0.0 0.0 +37 7 1 Si-30 0.0 0.0 +38 7 1 Cr-50 0.0 0.0 +39 7 1 Cr-52 0.0 0.0 +40 7 1 Cr-53 0.0 0.0 +41 7 1 Cr-54 0.0 0.0 +0 7 2 H-1 0.0 0.0 +1 7 2 O-16 0.0 0.0 +2 7 2 B-10 0.0 0.0 +3 7 2 B-11 0.0 0.0 +4 7 2 Fe-54 0.0 0.0 +5 7 2 Fe-56 0.0 0.0 +6 7 2 Fe-57 0.0 0.0 +7 7 2 Fe-58 0.0 0.0 +8 7 2 Ni-58 0.0 0.0 +9 7 2 Ni-60 0.0 0.0 +10 7 2 Ni-61 0.0 0.0 +11 7 2 Ni-62 0.0 0.0 +12 7 2 Ni-64 0.0 0.0 +13 7 2 Mn-55 0.0 0.0 +14 7 2 Si-28 0.0 0.0 +15 7 2 Si-29 0.0 0.0 +16 7 2 Si-30 0.0 0.0 +17 7 2 Cr-50 0.0 0.0 +18 7 2 Cr-52 0.0 0.0 +19 7 2 Cr-53 0.0 0.0 +20 7 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +63 7 1 1 H-1 P0 0.0 0.0 P0 +64 7 1 1 O-16 P0 0.0 0.0 P0 +65 7 1 1 B-10 P0 0.0 0.0 P0 +66 7 1 1 B-11 P0 0.0 0.0 P0 +67 7 1 1 Fe-54 P0 0.0 0.0 P0 +68 7 1 1 Fe-56 P0 0.0 0.0 P0 +69 7 1 1 Fe-57 P0 0.0 0.0 P0 +70 7 1 1 Fe-58 P0 0.0 0.0 P0 +71 7 1 1 Ni-58 P0 0.0 0.0 P0 +72 7 1 1 Ni-60 P0 0.0 0.0 P0 +73 7 1 1 Ni-61 P0 0.0 0.0 P0 +74 7 1 1 Ni-62 P0 0.0 0.0 P0 +75 7 1 1 Ni-64 P0 0.0 0.0 P0 +76 7 1 1 Mn-55 P0 0.0 0.0 P0 +77 7 1 1 Si-28 P0 0.0 0.0 P0 +78 7 1 1 Si-29 P0 0.0 0.0 P0 +79 7 1 1 Si-30 P0 0.0 0.0 P0 +80 7 1 1 Cr-50 P0 0.0 0.0 P0 +81 7 1 1 Cr-52 P0 0.0 0.0 P0 +82 7 1 1 Cr-53 P0 0.0 0.0 P0 +83 7 1 1 Cr-54 P0 0.0 0.0 P0 +42 7 1 2 H-1 P0 0.0 0.0 P0 +43 7 1 2 O-16 P0 0.0 0.0 P0 +44 7 1 2 B-10 P0 0.0 0.0 P0 +45 7 1 2 B-11 P0 0.0 0.0 P0 +46 7 1 2 Fe-54 P0 0.0 0.0 P0 +47 7 1 2 Fe-56 P0 0.0 0.0 P0 +48 7 1 2 Fe-57 P0 0.0 0.0 P0 +49 7 1 2 Fe-58 P0 0.0 0.0 P0 +50 7 1 2 Ni-58 P0 0.0 0.0 P0 +51 7 1 2 Ni-60 P0 0.0 0.0 P0 +52 7 1 2 Ni-61 P0 0.0 0.0 P0 +53 7 1 2 Ni-62 P0 0.0 0.0 P0 +54 7 1 2 Ni-64 P0 0.0 0.0 P0 +55 7 1 2 Mn-55 P0 0.0 0.0 P0 +56 7 1 2 Si-28 P0 0.0 0.0 P0 +57 7 1 2 Si-29 P0 0.0 0.0 P0 +58 7 1 2 Si-30 P0 0.0 0.0 P0 +59 7 1 2 Cr-50 P0 0.0 0.0 P0 +60 7 1 2 Cr-52 P0 0.0 0.0 P0 +61 7 1 2 Cr-53 P0 0.0 0.0 P0 +62 7 1 2 Cr-54 P0 0.0 0.0 P0 +21 7 2 1 H-1 P0 0.0 0.0 P0 +22 7 2 1 O-16 P0 0.0 0.0 P0 +23 7 2 1 B-10 P0 0.0 0.0 P0 +24 7 2 1 B-11 P0 0.0 0.0 P0 +25 7 2 1 Fe-54 P0 0.0 0.0 P0 +26 7 2 1 Fe-56 P0 0.0 0.0 P0 +27 7 2 1 Fe-57 P0 0.0 0.0 P0 +28 7 2 1 Fe-58 P0 0.0 0.0 P0 +29 7 2 1 Ni-58 P0 0.0 0.0 P0 +30 7 2 1 Ni-60 P0 0.0 0.0 P0 +31 7 2 1 Ni-61 P0 0.0 0.0 P0 +32 7 2 1 Ni-62 P0 0.0 0.0 P0 +33 7 2 1 Ni-64 P0 0.0 0.0 P0 +34 7 2 1 Mn-55 P0 0.0 0.0 P0 +35 7 2 1 Si-28 P0 0.0 0.0 P0 +36 7 2 1 Si-29 P0 0.0 0.0 P0 +37 7 2 1 Si-30 P0 0.0 0.0 P0 +38 7 2 1 Cr-50 P0 0.0 0.0 P0 +39 7 2 1 Cr-52 P0 0.0 0.0 P0 +40 7 2 1 Cr-53 P0 0.0 0.0 P0 +41 7 2 1 Cr-54 P0 0.0 0.0 P0 +0 7 2 2 H-1 P0 0.0 0.0 P0 +1 7 2 2 O-16 P0 0.0 0.0 P0 +2 7 2 2 B-10 P0 0.0 0.0 P0 +3 7 2 2 B-11 P0 0.0 0.0 P0 +4 7 2 2 Fe-54 P0 0.0 0.0 P0 +5 7 2 2 Fe-56 P0 0.0 0.0 P0 +6 7 2 2 Fe-57 P0 0.0 0.0 P0 +7 7 2 2 Fe-58 P0 0.0 0.0 P0 +8 7 2 2 Ni-58 P0 0.0 0.0 P0 +9 7 2 2 Ni-60 P0 0.0 0.0 P0 +10 7 2 2 Ni-61 P0 0.0 0.0 P0 +11 7 2 2 Ni-62 P0 0.0 0.0 P0 +12 7 2 2 Ni-64 P0 0.0 0.0 P0 +13 7 2 2 Mn-55 P0 0.0 0.0 P0 +14 7 2 2 Si-28 P0 0.0 0.0 P0 +15 7 2 2 Si-29 P0 0.0 0.0 P0 +16 7 2 2 Si-30 P0 0.0 0.0 P0 +17 7 2 2 Cr-50 P0 0.0 0.0 P0 +18 7 2 2 Cr-52 P0 0.0 0.0 P0 +19 7 2 2 Cr-53 P0 0.0 0.0 P0 +20 7 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +21 7 1 H-1 0.0 0.0 +22 7 1 O-16 0.0 0.0 +23 7 1 B-10 0.0 0.0 +24 7 1 B-11 0.0 0.0 +25 7 1 Fe-54 0.0 0.0 +26 7 1 Fe-56 0.0 0.0 +27 7 1 Fe-57 0.0 0.0 +28 7 1 Fe-58 0.0 0.0 +29 7 1 Ni-58 0.0 0.0 +30 7 1 Ni-60 0.0 0.0 +31 7 1 Ni-61 0.0 0.0 +32 7 1 Ni-62 0.0 0.0 +33 7 1 Ni-64 0.0 0.0 +34 7 1 Mn-55 0.0 0.0 +35 7 1 Si-28 0.0 0.0 +36 7 1 Si-29 0.0 0.0 +37 7 1 Si-30 0.0 0.0 +38 7 1 Cr-50 0.0 0.0 +39 7 1 Cr-52 0.0 0.0 +40 7 1 Cr-53 0.0 0.0 +41 7 1 Cr-54 0.0 0.0 +0 7 2 H-1 0.0 0.0 +1 7 2 O-16 0.0 0.0 +2 7 2 B-10 0.0 0.0 +3 7 2 B-11 0.0 0.0 +4 7 2 Fe-54 0.0 0.0 +5 7 2 Fe-56 0.0 0.0 +6 7 2 Fe-57 0.0 0.0 +7 7 2 Fe-58 0.0 0.0 +8 7 2 Ni-58 0.0 0.0 +9 7 2 Ni-60 0.0 0.0 +10 7 2 Ni-61 0.0 0.0 +11 7 2 Ni-62 0.0 0.0 +12 7 2 Ni-64 0.0 0.0 +13 7 2 Mn-55 0.0 0.0 +14 7 2 Si-28 0.0 0.0 +15 7 2 Si-29 0.0 0.0 +16 7 2 Si-30 0.0 0.0 +17 7 2 Cr-50 0.0 0.0 +18 7 2 Cr-52 0.0 0.0 +19 7 2 Cr-53 0.0 0.0 +20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 8 1 H-1 0.0 0.0 +22 8 1 O-16 0.0 0.0 +23 8 1 B-10 0.0 0.0 +24 8 1 B-11 0.0 0.0 +25 8 1 Fe-54 0.0 0.0 +26 8 1 Fe-56 0.0 0.0 +27 8 1 Fe-57 0.0 0.0 +28 8 1 Fe-58 0.0 0.0 +29 8 1 Ni-58 0.0 0.0 +30 8 1 Ni-60 0.0 0.0 +31 8 1 Ni-61 0.0 0.0 +32 8 1 Ni-62 0.0 0.0 +33 8 1 Ni-64 0.0 0.0 +34 8 1 Mn-55 0.0 0.0 +35 8 1 Si-28 0.0 0.0 +36 8 1 Si-29 0.0 0.0 +37 8 1 Si-30 0.0 0.0 +38 8 1 Cr-50 0.0 0.0 +39 8 1 Cr-52 0.0 0.0 +40 8 1 Cr-53 0.0 0.0 +41 8 1 Cr-54 0.0 0.0 +0 8 2 H-1 0.0 0.0 +1 8 2 O-16 0.0 0.0 +2 8 2 B-10 0.0 0.0 +3 8 2 B-11 0.0 0.0 +4 8 2 Fe-54 0.0 0.0 +5 8 2 Fe-56 0.0 0.0 +6 8 2 Fe-57 0.0 0.0 +7 8 2 Fe-58 0.0 0.0 +8 8 2 Ni-58 0.0 0.0 +9 8 2 Ni-60 0.0 0.0 +10 8 2 Ni-61 0.0 0.0 +11 8 2 Ni-62 0.0 0.0 +12 8 2 Ni-64 0.0 0.0 +13 8 2 Mn-55 0.0 0.0 +14 8 2 Si-28 0.0 0.0 +15 8 2 Si-29 0.0 0.0 +16 8 2 Si-30 0.0 0.0 +17 8 2 Cr-50 0.0 0.0 +18 8 2 Cr-52 0.0 0.0 +19 8 2 Cr-53 0.0 0.0 +20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 8 1 H-1 0.0 0.0 +22 8 1 O-16 0.0 0.0 +23 8 1 B-10 0.0 0.0 +24 8 1 B-11 0.0 0.0 +25 8 1 Fe-54 0.0 0.0 +26 8 1 Fe-56 0.0 0.0 +27 8 1 Fe-57 0.0 0.0 +28 8 1 Fe-58 0.0 0.0 +29 8 1 Ni-58 0.0 0.0 +30 8 1 Ni-60 0.0 0.0 +31 8 1 Ni-61 0.0 0.0 +32 8 1 Ni-62 0.0 0.0 +33 8 1 Ni-64 0.0 0.0 +34 8 1 Mn-55 0.0 0.0 +35 8 1 Si-28 0.0 0.0 +36 8 1 Si-29 0.0 0.0 +37 8 1 Si-30 0.0 0.0 +38 8 1 Cr-50 0.0 0.0 +39 8 1 Cr-52 0.0 0.0 +40 8 1 Cr-53 0.0 0.0 +41 8 1 Cr-54 0.0 0.0 +0 8 2 H-1 0.0 0.0 +1 8 2 O-16 0.0 0.0 +2 8 2 B-10 0.0 0.0 +3 8 2 B-11 0.0 0.0 +4 8 2 Fe-54 0.0 0.0 +5 8 2 Fe-56 0.0 0.0 +6 8 2 Fe-57 0.0 0.0 +7 8 2 Fe-58 0.0 0.0 +8 8 2 Ni-58 0.0 0.0 +9 8 2 Ni-60 0.0 0.0 +10 8 2 Ni-61 0.0 0.0 +11 8 2 Ni-62 0.0 0.0 +12 8 2 Ni-64 0.0 0.0 +13 8 2 Mn-55 0.0 0.0 +14 8 2 Si-28 0.0 0.0 +15 8 2 Si-29 0.0 0.0 +16 8 2 Si-30 0.0 0.0 +17 8 2 Cr-50 0.0 0.0 +18 8 2 Cr-52 0.0 0.0 +19 8 2 Cr-53 0.0 0.0 +20 8 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment +63 8 1 1 H-1 P0 0.0 0.0 P0 +64 8 1 1 O-16 P0 0.0 0.0 P0 +65 8 1 1 B-10 P0 0.0 0.0 P0 +66 8 1 1 B-11 P0 0.0 0.0 P0 +67 8 1 1 Fe-54 P0 0.0 0.0 P0 +68 8 1 1 Fe-56 P0 0.0 0.0 P0 +69 8 1 1 Fe-57 P0 0.0 0.0 P0 +70 8 1 1 Fe-58 P0 0.0 0.0 P0 +71 8 1 1 Ni-58 P0 0.0 0.0 P0 +72 8 1 1 Ni-60 P0 0.0 0.0 P0 +73 8 1 1 Ni-61 P0 0.0 0.0 P0 +74 8 1 1 Ni-62 P0 0.0 0.0 P0 +75 8 1 1 Ni-64 P0 0.0 0.0 P0 +76 8 1 1 Mn-55 P0 0.0 0.0 P0 +77 8 1 1 Si-28 P0 0.0 0.0 P0 +78 8 1 1 Si-29 P0 0.0 0.0 P0 +79 8 1 1 Si-30 P0 0.0 0.0 P0 +80 8 1 1 Cr-50 P0 0.0 0.0 P0 +81 8 1 1 Cr-52 P0 0.0 0.0 P0 +82 8 1 1 Cr-53 P0 0.0 0.0 P0 +83 8 1 1 Cr-54 P0 0.0 0.0 P0 +42 8 1 2 H-1 P0 0.0 0.0 P0 +43 8 1 2 O-16 P0 0.0 0.0 P0 +44 8 1 2 B-10 P0 0.0 0.0 P0 +45 8 1 2 B-11 P0 0.0 0.0 P0 +46 8 1 2 Fe-54 P0 0.0 0.0 P0 +47 8 1 2 Fe-56 P0 0.0 0.0 P0 +48 8 1 2 Fe-57 P0 0.0 0.0 P0 +49 8 1 2 Fe-58 P0 0.0 0.0 P0 +50 8 1 2 Ni-58 P0 0.0 0.0 P0 +51 8 1 2 Ni-60 P0 0.0 0.0 P0 +52 8 1 2 Ni-61 P0 0.0 0.0 P0 +53 8 1 2 Ni-62 P0 0.0 0.0 P0 +54 8 1 2 Ni-64 P0 0.0 0.0 P0 +55 8 1 2 Mn-55 P0 0.0 0.0 P0 +56 8 1 2 Si-28 P0 0.0 0.0 P0 +57 8 1 2 Si-29 P0 0.0 0.0 P0 +58 8 1 2 Si-30 P0 0.0 0.0 P0 +59 8 1 2 Cr-50 P0 0.0 0.0 P0 +60 8 1 2 Cr-52 P0 0.0 0.0 P0 +61 8 1 2 Cr-53 P0 0.0 0.0 P0 +62 8 1 2 Cr-54 P0 0.0 0.0 P0 +21 8 2 1 H-1 P0 0.0 0.0 P0 +22 8 2 1 O-16 P0 0.0 0.0 P0 +23 8 2 1 B-10 P0 0.0 0.0 P0 +24 8 2 1 B-11 P0 0.0 0.0 P0 +25 8 2 1 Fe-54 P0 0.0 0.0 P0 +26 8 2 1 Fe-56 P0 0.0 0.0 P0 +27 8 2 1 Fe-57 P0 0.0 0.0 P0 +28 8 2 1 Fe-58 P0 0.0 0.0 P0 +29 8 2 1 Ni-58 P0 0.0 0.0 P0 +30 8 2 1 Ni-60 P0 0.0 0.0 P0 +31 8 2 1 Ni-61 P0 0.0 0.0 P0 +32 8 2 1 Ni-62 P0 0.0 0.0 P0 +33 8 2 1 Ni-64 P0 0.0 0.0 P0 +34 8 2 1 Mn-55 P0 0.0 0.0 P0 +35 8 2 1 Si-28 P0 0.0 0.0 P0 +36 8 2 1 Si-29 P0 0.0 0.0 P0 +37 8 2 1 Si-30 P0 0.0 0.0 P0 +38 8 2 1 Cr-50 P0 0.0 0.0 P0 +39 8 2 1 Cr-52 P0 0.0 0.0 P0 +40 8 2 1 Cr-53 P0 0.0 0.0 P0 +41 8 2 1 Cr-54 P0 0.0 0.0 P0 +0 8 2 2 H-1 P0 0.0 0.0 P0 +1 8 2 2 O-16 P0 0.0 0.0 P0 +2 8 2 2 B-10 P0 0.0 0.0 P0 +3 8 2 2 B-11 P0 0.0 0.0 P0 +4 8 2 2 Fe-54 P0 0.0 0.0 P0 +5 8 2 2 Fe-56 P0 0.0 0.0 P0 +6 8 2 2 Fe-57 P0 0.0 0.0 P0 +7 8 2 2 Fe-58 P0 0.0 0.0 P0 +8 8 2 2 Ni-58 P0 0.0 0.0 P0 +9 8 2 2 Ni-60 P0 0.0 0.0 P0 +10 8 2 2 Ni-61 P0 0.0 0.0 P0 +11 8 2 2 Ni-62 P0 0.0 0.0 P0 +12 8 2 2 Ni-64 P0 0.0 0.0 P0 +13 8 2 2 Mn-55 P0 0.0 0.0 P0 +14 8 2 2 Si-28 P0 0.0 0.0 P0 +15 8 2 2 Si-29 P0 0.0 0.0 P0 +16 8 2 2 Si-30 P0 0.0 0.0 P0 +17 8 2 2 Cr-50 P0 0.0 0.0 P0 +18 8 2 2 Cr-52 P0 0.0 0.0 P0 +19 8 2 2 Cr-53 P0 0.0 0.0 P0 +20 8 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +21 8 1 H-1 0.0 0.0 +22 8 1 O-16 0.0 0.0 +23 8 1 B-10 0.0 0.0 +24 8 1 B-11 0.0 0.0 +25 8 1 Fe-54 0.0 0.0 +26 8 1 Fe-56 0.0 0.0 +27 8 1 Fe-57 0.0 0.0 +28 8 1 Fe-58 0.0 0.0 +29 8 1 Ni-58 0.0 0.0 +30 8 1 Ni-60 0.0 0.0 +31 8 1 Ni-61 0.0 0.0 +32 8 1 Ni-62 0.0 0.0 +33 8 1 Ni-64 0.0 0.0 +34 8 1 Mn-55 0.0 0.0 +35 8 1 Si-28 0.0 0.0 +36 8 1 Si-29 0.0 0.0 +37 8 1 Si-30 0.0 0.0 +38 8 1 Cr-50 0.0 0.0 +39 8 1 Cr-52 0.0 0.0 +40 8 1 Cr-53 0.0 0.0 +41 8 1 Cr-54 0.0 0.0 +0 8 2 H-1 0.0 0.0 +1 8 2 O-16 0.0 0.0 +2 8 2 B-10 0.0 0.0 +3 8 2 B-11 0.0 0.0 +4 8 2 Fe-54 0.0 0.0 +5 8 2 Fe-56 0.0 0.0 +6 8 2 Fe-57 0.0 0.0 +7 8 2 Fe-58 0.0 0.0 +8 8 2 Ni-58 0.0 0.0 +9 8 2 Ni-60 0.0 0.0 +10 8 2 Ni-61 0.0 0.0 +11 8 2 Ni-62 0.0 0.0 +12 8 2 Ni-64 0.0 0.0 +13 8 2 Mn-55 0.0 0.0 +14 8 2 Si-28 0.0 0.0 +15 8 2 Si-29 0.0 0.0 +16 8 2 Si-30 0.0 0.0 +17 8 2 Cr-50 0.0 0.0 +18 8 2 Cr-52 0.0 0.0 +19 8 2 Cr-53 0.0 0.0 +20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. 21 9 1 H-1 0.150655 0.480993 22 9 1 O-16 0.116221 0.114089 23 9 1 B-10 0.000000 0.000000 @@ -1411,48 +1411,48 @@ 18 9 2 Cr-52 0.000000 0.000000 19 9 2 Cr-53 0.000000 0.000000 20 9 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 9 1 H-1 0 0 -22 9 1 O-16 0 0 -23 9 1 B-10 0 0 -24 9 1 B-11 0 0 -25 9 1 Fe-54 0 0 -26 9 1 Fe-56 0 0 -27 9 1 Fe-57 0 0 -28 9 1 Fe-58 0 0 -29 9 1 Ni-58 0 0 -30 9 1 Ni-60 0 0 -31 9 1 Ni-61 0 0 -32 9 1 Ni-62 0 0 -33 9 1 Ni-64 0 0 -34 9 1 Mn-55 0 0 -35 9 1 Si-28 0 0 -36 9 1 Si-29 0 0 -37 9 1 Si-30 0 0 -38 9 1 Cr-50 0 0 -39 9 1 Cr-52 0 0 -40 9 1 Cr-53 0 0 -41 9 1 Cr-54 0 0 -0 9 2 H-1 0 0 -1 9 2 O-16 0 0 -2 9 2 B-10 0 0 -3 9 2 B-11 0 0 -4 9 2 Fe-54 0 0 -5 9 2 Fe-56 0 0 -6 9 2 Fe-57 0 0 -7 9 2 Fe-58 0 0 -8 9 2 Ni-58 0 0 -9 9 2 Ni-60 0 0 -10 9 2 Ni-61 0 0 -11 9 2 Ni-62 0 0 -12 9 2 Ni-64 0 0 -13 9 2 Mn-55 0 0 -14 9 2 Si-28 0 0 -15 9 2 Si-29 0 0 -16 9 2 Si-30 0 0 -17 9 2 Cr-50 0 0 -18 9 2 Cr-52 0 0 -19 9 2 Cr-53 0 0 -20 9 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +21 9 1 H-1 0.0 0.0 +22 9 1 O-16 0.0 0.0 +23 9 1 B-10 0.0 0.0 +24 9 1 B-11 0.0 0.0 +25 9 1 Fe-54 0.0 0.0 +26 9 1 Fe-56 0.0 0.0 +27 9 1 Fe-57 0.0 0.0 +28 9 1 Fe-58 0.0 0.0 +29 9 1 Ni-58 0.0 0.0 +30 9 1 Ni-60 0.0 0.0 +31 9 1 Ni-61 0.0 0.0 +32 9 1 Ni-62 0.0 0.0 +33 9 1 Ni-64 0.0 0.0 +34 9 1 Mn-55 0.0 0.0 +35 9 1 Si-28 0.0 0.0 +36 9 1 Si-29 0.0 0.0 +37 9 1 Si-30 0.0 0.0 +38 9 1 Cr-50 0.0 0.0 +39 9 1 Cr-52 0.0 0.0 +40 9 1 Cr-53 0.0 0.0 +41 9 1 Cr-54 0.0 0.0 +0 9 2 H-1 0.0 0.0 +1 9 2 O-16 0.0 0.0 +2 9 2 B-10 0.0 0.0 +3 9 2 B-11 0.0 0.0 +4 9 2 Fe-54 0.0 0.0 +5 9 2 Fe-56 0.0 0.0 +6 9 2 Fe-57 0.0 0.0 +7 9 2 Fe-58 0.0 0.0 +8 9 2 Ni-58 0.0 0.0 +9 9 2 Ni-60 0.0 0.0 +10 9 2 Ni-61 0.0 0.0 +11 9 2 Ni-62 0.0 0.0 +12 9 2 Ni-64 0.0 0.0 +13 9 2 Mn-55 0.0 0.0 +14 9 2 Si-28 0.0 0.0 +15 9 2 Si-29 0.0 0.0 +16 9 2 Si-30 0.0 0.0 +17 9 2 Cr-50 0.0 0.0 +18 9 2 Cr-52 0.0 0.0 +19 9 2 Cr-53 0.0 0.0 +20 9 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 63 9 1 1 H-1 P0 0.150655 0.480993 P0 64 9 1 1 O-16 P0 0.116221 0.114089 P0 65 9 1 1 B-10 P0 0.000000 0.000000 P0 @@ -1537,48 +1537,48 @@ 18 9 2 2 Cr-52 P0 0.000000 0.000000 P0 19 9 2 2 Cr-53 P0 0.000000 0.000000 P0 20 9 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -21 9 1 H-1 0 0 -22 9 1 O-16 0 0 -23 9 1 B-10 0 0 -24 9 1 B-11 0 0 -25 9 1 Fe-54 0 0 -26 9 1 Fe-56 0 0 -27 9 1 Fe-57 0 0 -28 9 1 Fe-58 0 0 -29 9 1 Ni-58 0 0 -30 9 1 Ni-60 0 0 -31 9 1 Ni-61 0 0 -32 9 1 Ni-62 0 0 -33 9 1 Ni-64 0 0 -34 9 1 Mn-55 0 0 -35 9 1 Si-28 0 0 -36 9 1 Si-29 0 0 -37 9 1 Si-30 0 0 -38 9 1 Cr-50 0 0 -39 9 1 Cr-52 0 0 -40 9 1 Cr-53 0 0 -41 9 1 Cr-54 0 0 -0 9 2 H-1 0 0 -1 9 2 O-16 0 0 -2 9 2 B-10 0 0 -3 9 2 B-11 0 0 -4 9 2 Fe-54 0 0 -5 9 2 Fe-56 0 0 -6 9 2 Fe-57 0 0 -7 9 2 Fe-58 0 0 -8 9 2 Ni-58 0 0 -9 9 2 Ni-60 0 0 -10 9 2 Ni-61 0 0 -11 9 2 Ni-62 0 0 -12 9 2 Ni-64 0 0 -13 9 2 Mn-55 0 0 -14 9 2 Si-28 0 0 -15 9 2 Si-29 0 0 -16 9 2 Si-30 0 0 -17 9 2 Cr-50 0 0 -18 9 2 Cr-52 0 0 -19 9 2 Cr-53 0 0 -20 9 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 9 1 H-1 0.0 0.0 +22 9 1 O-16 0.0 0.0 +23 9 1 B-10 0.0 0.0 +24 9 1 B-11 0.0 0.0 +25 9 1 Fe-54 0.0 0.0 +26 9 1 Fe-56 0.0 0.0 +27 9 1 Fe-57 0.0 0.0 +28 9 1 Fe-58 0.0 0.0 +29 9 1 Ni-58 0.0 0.0 +30 9 1 Ni-60 0.0 0.0 +31 9 1 Ni-61 0.0 0.0 +32 9 1 Ni-62 0.0 0.0 +33 9 1 Ni-64 0.0 0.0 +34 9 1 Mn-55 0.0 0.0 +35 9 1 Si-28 0.0 0.0 +36 9 1 Si-29 0.0 0.0 +37 9 1 Si-30 0.0 0.0 +38 9 1 Cr-50 0.0 0.0 +39 9 1 Cr-52 0.0 0.0 +40 9 1 Cr-53 0.0 0.0 +41 9 1 Cr-54 0.0 0.0 +0 9 2 H-1 0.0 0.0 +1 9 2 O-16 0.0 0.0 +2 9 2 B-10 0.0 0.0 +3 9 2 B-11 0.0 0.0 +4 9 2 Fe-54 0.0 0.0 +5 9 2 Fe-56 0.0 0.0 +6 9 2 Fe-57 0.0 0.0 +7 9 2 Fe-58 0.0 0.0 +8 9 2 Ni-58 0.0 0.0 +9 9 2 Ni-60 0.0 0.0 +10 9 2 Ni-61 0.0 0.0 +11 9 2 Ni-62 0.0 0.0 +12 9 2 Ni-64 0.0 0.0 +13 9 2 Mn-55 0.0 0.0 +14 9 2 Si-28 0.0 0.0 +15 9 2 Si-29 0.0 0.0 +16 9 2 Si-30 0.0 0.0 +17 9 2 Cr-50 0.0 0.0 +18 9 2 Cr-52 0.0 0.0 +19 9 2 Cr-53 0.0 0.0 +20 9 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. 21 10 1 H-1 0.123944 0.541390 22 10 1 O-16 0.000000 0.000000 23 10 1 B-10 0.000000 0.000000 @@ -1621,48 +1621,48 @@ 18 10 2 Cr-52 0.000000 0.000000 19 10 2 Cr-53 0.000000 0.000000 20 10 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 10 1 H-1 0 0 -22 10 1 O-16 0 0 -23 10 1 B-10 0 0 -24 10 1 B-11 0 0 -25 10 1 Fe-54 0 0 -26 10 1 Fe-56 0 0 -27 10 1 Fe-57 0 0 -28 10 1 Fe-58 0 0 -29 10 1 Ni-58 0 0 -30 10 1 Ni-60 0 0 -31 10 1 Ni-61 0 0 -32 10 1 Ni-62 0 0 -33 10 1 Ni-64 0 0 -34 10 1 Mn-55 0 0 -35 10 1 Si-28 0 0 -36 10 1 Si-29 0 0 -37 10 1 Si-30 0 0 -38 10 1 Cr-50 0 0 -39 10 1 Cr-52 0 0 -40 10 1 Cr-53 0 0 -41 10 1 Cr-54 0 0 -0 10 2 H-1 0 0 -1 10 2 O-16 0 0 -2 10 2 B-10 0 0 -3 10 2 B-11 0 0 -4 10 2 Fe-54 0 0 -5 10 2 Fe-56 0 0 -6 10 2 Fe-57 0 0 -7 10 2 Fe-58 0 0 -8 10 2 Ni-58 0 0 -9 10 2 Ni-60 0 0 -10 10 2 Ni-61 0 0 -11 10 2 Ni-62 0 0 -12 10 2 Ni-64 0 0 -13 10 2 Mn-55 0 0 -14 10 2 Si-28 0 0 -15 10 2 Si-29 0 0 -16 10 2 Si-30 0 0 -17 10 2 Cr-50 0 0 -18 10 2 Cr-52 0 0 -19 10 2 Cr-53 0 0 -20 10 2 Cr-54 0 0 material group in group out nuclide moment mean std. dev. moment +21 10 1 H-1 0.0 0.0 +22 10 1 O-16 0.0 0.0 +23 10 1 B-10 0.0 0.0 +24 10 1 B-11 0.0 0.0 +25 10 1 Fe-54 0.0 0.0 +26 10 1 Fe-56 0.0 0.0 +27 10 1 Fe-57 0.0 0.0 +28 10 1 Fe-58 0.0 0.0 +29 10 1 Ni-58 0.0 0.0 +30 10 1 Ni-60 0.0 0.0 +31 10 1 Ni-61 0.0 0.0 +32 10 1 Ni-62 0.0 0.0 +33 10 1 Ni-64 0.0 0.0 +34 10 1 Mn-55 0.0 0.0 +35 10 1 Si-28 0.0 0.0 +36 10 1 Si-29 0.0 0.0 +37 10 1 Si-30 0.0 0.0 +38 10 1 Cr-50 0.0 0.0 +39 10 1 Cr-52 0.0 0.0 +40 10 1 Cr-53 0.0 0.0 +41 10 1 Cr-54 0.0 0.0 +0 10 2 H-1 0.0 0.0 +1 10 2 O-16 0.0 0.0 +2 10 2 B-10 0.0 0.0 +3 10 2 B-11 0.0 0.0 +4 10 2 Fe-54 0.0 0.0 +5 10 2 Fe-56 0.0 0.0 +6 10 2 Fe-57 0.0 0.0 +7 10 2 Fe-58 0.0 0.0 +8 10 2 Ni-58 0.0 0.0 +9 10 2 Ni-60 0.0 0.0 +10 10 2 Ni-61 0.0 0.0 +11 10 2 Ni-62 0.0 0.0 +12 10 2 Ni-64 0.0 0.0 +13 10 2 Mn-55 0.0 0.0 +14 10 2 Si-28 0.0 0.0 +15 10 2 Si-29 0.0 0.0 +16 10 2 Si-30 0.0 0.0 +17 10 2 Cr-50 0.0 0.0 +18 10 2 Cr-52 0.0 0.0 +19 10 2 Cr-53 0.0 0.0 +20 10 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 63 10 1 1 H-1 P0 0.123944 0.541390 P0 64 10 1 1 O-16 P0 0.000000 0.000000 P0 65 10 1 1 B-10 P0 0.000000 0.000000 P0 @@ -1747,48 +1747,48 @@ 18 10 2 2 Cr-52 P0 0.000000 0.000000 P0 19 10 2 2 Cr-53 P0 0.000000 0.000000 P0 20 10 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -21 10 1 H-1 0 0 -22 10 1 O-16 0 0 -23 10 1 B-10 0 0 -24 10 1 B-11 0 0 -25 10 1 Fe-54 0 0 -26 10 1 Fe-56 0 0 -27 10 1 Fe-57 0 0 -28 10 1 Fe-58 0 0 -29 10 1 Ni-58 0 0 -30 10 1 Ni-60 0 0 -31 10 1 Ni-61 0 0 -32 10 1 Ni-62 0 0 -33 10 1 Ni-64 0 0 -34 10 1 Mn-55 0 0 -35 10 1 Si-28 0 0 -36 10 1 Si-29 0 0 -37 10 1 Si-30 0 0 -38 10 1 Cr-50 0 0 -39 10 1 Cr-52 0 0 -40 10 1 Cr-53 0 0 -41 10 1 Cr-54 0 0 -0 10 2 H-1 0 0 -1 10 2 O-16 0 0 -2 10 2 B-10 0 0 -3 10 2 B-11 0 0 -4 10 2 Fe-54 0 0 -5 10 2 Fe-56 0 0 -6 10 2 Fe-57 0 0 -7 10 2 Fe-58 0 0 -8 10 2 Ni-58 0 0 -9 10 2 Ni-60 0 0 -10 10 2 Ni-61 0 0 -11 10 2 Ni-62 0 0 -12 10 2 Ni-64 0 0 -13 10 2 Mn-55 0 0 -14 10 2 Si-28 0 0 -15 10 2 Si-29 0 0 -16 10 2 Si-30 0 0 -17 10 2 Cr-50 0 0 -18 10 2 Cr-52 0 0 -19 10 2 Cr-53 0 0 -20 10 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 10 1 H-1 0.0 0.0 +22 10 1 O-16 0.0 0.0 +23 10 1 B-10 0.0 0.0 +24 10 1 B-11 0.0 0.0 +25 10 1 Fe-54 0.0 0.0 +26 10 1 Fe-56 0.0 0.0 +27 10 1 Fe-57 0.0 0.0 +28 10 1 Fe-58 0.0 0.0 +29 10 1 Ni-58 0.0 0.0 +30 10 1 Ni-60 0.0 0.0 +31 10 1 Ni-61 0.0 0.0 +32 10 1 Ni-62 0.0 0.0 +33 10 1 Ni-64 0.0 0.0 +34 10 1 Mn-55 0.0 0.0 +35 10 1 Si-28 0.0 0.0 +36 10 1 Si-29 0.0 0.0 +37 10 1 Si-30 0.0 0.0 +38 10 1 Cr-50 0.0 0.0 +39 10 1 Cr-52 0.0 0.0 +40 10 1 Cr-53 0.0 0.0 +41 10 1 Cr-54 0.0 0.0 +0 10 2 H-1 0.0 0.0 +1 10 2 O-16 0.0 0.0 +2 10 2 B-10 0.0 0.0 +3 10 2 B-11 0.0 0.0 +4 10 2 Fe-54 0.0 0.0 +5 10 2 Fe-56 0.0 0.0 +6 10 2 Fe-57 0.0 0.0 +7 10 2 Fe-58 0.0 0.0 +8 10 2 Ni-58 0.0 0.0 +9 10 2 Ni-60 0.0 0.0 +10 10 2 Ni-61 0.0 0.0 +11 10 2 Ni-62 0.0 0.0 +12 10 2 Ni-64 0.0 0.0 +13 10 2 Mn-55 0.0 0.0 +14 10 2 Si-28 0.0 0.0 +15 10 2 Si-29 0.0 0.0 +16 10 2 Si-30 0.0 0.0 +17 10 2 Cr-50 0.0 0.0 +18 10 2 Cr-52 0.0 0.0 +19 10 2 Cr-53 0.0 0.0 +20 10 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. 9 11 1 H-1 0.131470 0.476035 10 11 1 O-16 0.028684 0.043000 11 11 1 B-10 0.000000 0.000000 @@ -1807,24 +1807,24 @@ 6 11 2 Zr-92 0.084226 0.103161 7 11 2 Zr-94 0.092039 0.125985 8 11 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 11 1 H-1 0 0 -10 11 1 O-16 0 0 -11 11 1 B-10 0 0 -12 11 1 B-11 0 0 -13 11 1 Zr-90 0 0 -14 11 1 Zr-91 0 0 -15 11 1 Zr-92 0 0 -16 11 1 Zr-94 0 0 -17 11 1 Zr-96 0 0 -0 11 2 H-1 0 0 -1 11 2 O-16 0 0 -2 11 2 B-10 0 0 -3 11 2 B-11 0 0 -4 11 2 Zr-90 0 0 -5 11 2 Zr-91 0 0 -6 11 2 Zr-92 0 0 -7 11 2 Zr-94 0 0 -8 11 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +9 11 1 H-1 0.0 0.0 +10 11 1 O-16 0.0 0.0 +11 11 1 B-10 0.0 0.0 +12 11 1 B-11 0.0 0.0 +13 11 1 Zr-90 0.0 0.0 +14 11 1 Zr-91 0.0 0.0 +15 11 1 Zr-92 0.0 0.0 +16 11 1 Zr-94 0.0 0.0 +17 11 1 Zr-96 0.0 0.0 +0 11 2 H-1 0.0 0.0 +1 11 2 O-16 0.0 0.0 +2 11 2 B-10 0.0 0.0 +3 11 2 B-11 0.0 0.0 +4 11 2 Zr-90 0.0 0.0 +5 11 2 Zr-91 0.0 0.0 +6 11 2 Zr-92 0.0 0.0 +7 11 2 Zr-94 0.0 0.0 +8 11 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 27 11 1 1 H-1 P0 0.099594 0.442578 P0 28 11 1 1 O-16 P0 0.028684 0.043000 P0 29 11 1 1 B-10 P0 0.000000 0.000000 P0 @@ -1861,24 +1861,24 @@ 6 11 2 2 Zr-92 P0 0.084226 0.103161 P0 7 11 2 2 Zr-94 P0 0.092039 0.125985 P0 8 11 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -9 11 1 H-1 0 0 -10 11 1 O-16 0 0 -11 11 1 B-10 0 0 -12 11 1 B-11 0 0 -13 11 1 Zr-90 0 0 -14 11 1 Zr-91 0 0 -15 11 1 Zr-92 0 0 -16 11 1 Zr-94 0 0 -17 11 1 Zr-96 0 0 -0 11 2 H-1 0 0 -1 11 2 O-16 0 0 -2 11 2 B-10 0 0 -3 11 2 B-11 0 0 -4 11 2 Zr-90 0 0 -5 11 2 Zr-91 0 0 -6 11 2 Zr-92 0 0 -7 11 2 Zr-94 0 0 -8 11 2 Zr-96 0 0 material group in nuclide mean std. dev. +9 11 1 H-1 0.0 0.0 +10 11 1 O-16 0.0 0.0 +11 11 1 B-10 0.0 0.0 +12 11 1 B-11 0.0 0.0 +13 11 1 Zr-90 0.0 0.0 +14 11 1 Zr-91 0.0 0.0 +15 11 1 Zr-92 0.0 0.0 +16 11 1 Zr-94 0.0 0.0 +17 11 1 Zr-96 0.0 0.0 +0 11 2 H-1 0.0 0.0 +1 11 2 O-16 0.0 0.0 +2 11 2 B-10 0.0 0.0 +3 11 2 B-11 0.0 0.0 +4 11 2 Zr-90 0.0 0.0 +5 11 2 Zr-91 0.0 0.0 +6 11 2 Zr-92 0.0 0.0 +7 11 2 Zr-94 0.0 0.0 +8 11 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. 9 12 1 H-1 0.098944 0.178543 10 12 1 O-16 0.013270 0.020403 11 12 1 B-10 0.000000 0.000000 @@ -1897,24 +1897,24 @@ 6 12 2 Zr-92 0.000000 0.000000 7 12 2 Zr-94 0.000000 0.000000 8 12 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 12 1 H-1 0 0 -10 12 1 O-16 0 0 -11 12 1 B-10 0 0 -12 12 1 B-11 0 0 -13 12 1 Zr-90 0 0 -14 12 1 Zr-91 0 0 -15 12 1 Zr-92 0 0 -16 12 1 Zr-94 0 0 -17 12 1 Zr-96 0 0 -0 12 2 H-1 0 0 -1 12 2 O-16 0 0 -2 12 2 B-10 0 0 -3 12 2 B-11 0 0 -4 12 2 Zr-90 0 0 -5 12 2 Zr-91 0 0 -6 12 2 Zr-92 0 0 -7 12 2 Zr-94 0 0 -8 12 2 Zr-96 0 0 material group in group out nuclide moment mean std. dev. moment +9 12 1 H-1 0.0 0.0 +10 12 1 O-16 0.0 0.0 +11 12 1 B-10 0.0 0.0 +12 12 1 B-11 0.0 0.0 +13 12 1 Zr-90 0.0 0.0 +14 12 1 Zr-91 0.0 0.0 +15 12 1 Zr-92 0.0 0.0 +16 12 1 Zr-94 0.0 0.0 +17 12 1 Zr-96 0.0 0.0 +0 12 2 H-1 0.0 0.0 +1 12 2 O-16 0.0 0.0 +2 12 2 B-10 0.0 0.0 +3 12 2 B-11 0.0 0.0 +4 12 2 Zr-90 0.0 0.0 +5 12 2 Zr-91 0.0 0.0 +6 12 2 Zr-92 0.0 0.0 +7 12 2 Zr-94 0.0 0.0 +8 12 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment 27 12 1 1 H-1 P0 0.071704 0.167588 P0 28 12 1 1 O-16 P0 0.013270 0.020403 P0 29 12 1 1 B-10 P0 0.000000 0.000000 P0 @@ -1951,21 +1951,21 @@ 6 12 2 2 Zr-92 P0 0.000000 0.000000 P0 7 12 2 2 Zr-94 P0 0.000000 0.000000 P0 8 12 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. -9 12 1 H-1 0 0 -10 12 1 O-16 0 0 -11 12 1 B-10 0 0 -12 12 1 B-11 0 0 -13 12 1 Zr-90 0 0 -14 12 1 Zr-91 0 0 -15 12 1 Zr-92 0 0 -16 12 1 Zr-94 0 0 -17 12 1 Zr-96 0 0 -0 12 2 H-1 0 0 -1 12 2 O-16 0 0 -2 12 2 B-10 0 0 -3 12 2 B-11 0 0 -4 12 2 Zr-90 0 0 -5 12 2 Zr-91 0 0 -6 12 2 Zr-92 0 0 -7 12 2 Zr-94 0 0 -8 12 2 Zr-96 0 0 \ No newline at end of file +9 12 1 H-1 0.0 0.0 +10 12 1 O-16 0.0 0.0 +11 12 1 B-10 0.0 0.0 +12 12 1 B-11 0.0 0.0 +13 12 1 Zr-90 0.0 0.0 +14 12 1 Zr-91 0.0 0.0 +15 12 1 Zr-92 0.0 0.0 +16 12 1 Zr-94 0.0 0.0 +17 12 1 Zr-96 0.0 0.0 +0 12 2 H-1 0.0 0.0 +1 12 2 O-16 0.0 0.0 +2 12 2 B-10 0.0 0.0 +3 12 2 B-11 0.0 0.0 +4 12 2 Zr-90 0.0 0.0 +5 12 2 Zr-91 0.0 0.0 +6 12 2 Zr-92 0.0 0.0 +7 12 2 Zr-94 0.0 0.0 +8 12 2 Zr-96 0.0 0.0 \ No newline at end of file From 32eb58774df061c2198814ab99be6db7058288f6 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Tue, 10 May 2016 22:08:10 -0500 Subject: [PATCH 113/147] Add make_hexagon_region() function --- docs/source/pythonapi/index.rst | 10 ++++++++ openmc/surface.py | 45 ++++++++++++++++++++++++++++++++- 2 files changed, 54 insertions(+), 1 deletion(-) diff --git a/docs/source/pythonapi/index.rst b/docs/source/pythonapi/index.rst index 1631976e6..89d1b0508 100644 --- a/docs/source/pythonapi/index.rst +++ b/docs/source/pythonapi/index.rst @@ -122,6 +122,16 @@ Many of the above classes are derived from several abstract classes: openmc.Region openmc.Lattice +One function is also available to create a hexagonal region defined by the +intersection of six surface half-spaces. + +.. autosummary:: + :toctree: generated + :nosignatures: + :template: myfunction.rst + + openmc.make_hexagon_region + Constructing Tallies -------------------- diff --git a/openmc/surface.py b/openmc/surface.py index 37e7c2ffd..84028c1af 100644 --- a/openmc/surface.py +++ b/openmc/surface.py @@ -2,11 +2,12 @@ from abc import ABCMeta from numbers import Real, Integral from xml.etree import ElementTree as ET import sys +from math import sqrt import numpy as np from openmc.checkvalue import check_type, check_value, check_greater_than -from openmc.region import Region +from openmc.region import Region, Intersection if sys.version_info[0] >= 3: basestring = str @@ -1503,3 +1504,45 @@ class Halfspace(Region): def __str__(self): return '-' + str(self.surface.id) if self.side == '-' \ else str(self.surface.id) + + +def make_hexagon_region(edge_length=1., orientation='y'): + """Create a hexagon region from six surface planes. + + Parameters + ---------- + edge_length : float + Length of a side of the hexagon in cm + orientation : {'x', 'y'} + An 'x' orientation means that two sides of the hexagon are parallel to + the x-axis and a 'y' orientation means that two sides of the hexagon are + parallel to the y-axis. + + Returns + ------- + openmc.Region + The inside of a hexagonal prism + + """ + + l = edge_length + + if orientation == 'x': + right = XPlane(x0=sqrt(3.)/2.*l) + left = XPlane(x0=-sqrt(3.)/2.*l) + c = sqrt(3.)/3. + ur = Plane(A=c, B=1., D=l) # y = -x/sqrt(3) + a + ul = Plane(A=-c, B=1., D=l) # y = x/sqrt(3) + a + lr = Plane(A=-c, B=1., D=-l) # y = x/sqrt(3) - a + ll = Plane(A=c, B=1., D=-l) # y = -x/sqrt(3) - a + return Intersection(-right, +left, -ur, -ul, +lr, +ll) + + elif orientation == 'y': + top = YPlane(y0=sqrt(3.)/2.*l) + bottom = YPlane(y0=-sqrt(3.)/2.*l) + c = sqrt(3.) + ur = Plane(A=c, B=1., D=c*l) # y = -sqrt(3)*(x - a) + lr = Plane(A=-c, B=1., D=-c*l) # y = sqrt(3)*(x + a) + ll = Plane(A=c, B=1., D=-c*l) # y = -sqrt(3)*(x + a) + ul = Plane(A=-c, B=1., D=c*l) # y = sqrt(3)*(x + a) + return Intersection(-top, +bottom, -ur, +lr, +ll, -ul) From 0cabfec5e7279d6a449b1a71da063d710ce200ef Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 11 May 2016 09:46:58 -0500 Subject: [PATCH 114/147] A little error checking on Element.name --- openmc/element.py | 5 +++-- 1 file changed, 3 insertions(+), 2 deletions(-) diff --git a/openmc/element.py b/openmc/element.py index 39564add4..66371aba9 100644 --- a/openmc/element.py +++ b/openmc/element.py @@ -1,7 +1,7 @@ import sys import openmc -from openmc.checkvalue import check_type +from openmc.checkvalue import check_type, check_length from openmc.data import natural_abundance if sys.version_info[0] >= 3: @@ -99,7 +99,8 @@ class Element(object): @name.setter def name(self, name): - check_type('name', name, basestring) + check_type('element name', name, basestring) + check_length('element name', name, 1, 2) self._name = name @scattering.setter From f184f2a9e9b34d043d05de26748e82f6f57b9255 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Wed, 11 May 2016 14:27:33 -0400 Subject: [PATCH 115/147] Added warning messages to Library for the correction and legendre_order properties --- openmc/mgxs/library.py | 14 ++++++++++++++ openmc/mgxs/mgxs.py | 6 +++++- 2 files changed, 19 insertions(+), 1 deletion(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index f2a5c7569..ea856d735 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -297,12 +297,26 @@ class Library(object): @correction.setter def correction(self, correction): cv.check_value('correction', correction, ('P0', None)) + + if correction == 'P0' and self.legendre_order > 0: + msg = 'The P0 correction will be ignored since the scattering ' \ + 'order {} is greater than zero'.format(self.legendre_order) + warnings.warn(msg) + self._correction = correction @legendre_order.setter def legendre_order(self, legendre_order): cv.check_type('legendre_order', legendre_order, Integral) cv.check_greater_than('legendre_order', legendre_order, 0, equality=True) + cv.check_less_than('legendre_order', legendre_order, 10, equality=True) + + if self.correction == 'P0' and legendre_order > 0: + msg = 'The P0 correction will be ignored since the scattering ' \ + 'order {} is greater than zero'.format(self.legendre_order) + warnings.warn(msg, RuntimeWarning) + self.correction = None + self._legendre_order = legendre_order @tally_trigger.setter diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index dc3d0d127..830b6d766 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2034,11 +2034,15 @@ class ScatterMatrixXS(MGXS): subdomains='all', nuclides='all', moment='all', xs_type='macro', order_groups='increasing', row_column='inout', value='mean', **kwargs): - """Returns an array of multi-group cross sections. + r"""Returns an array of multi-group cross sections. This method constructs a 2D NumPy array for the requested scattering matrix data data for one or more energy groups and subdomains. + NOTE: The scattering moments are not multiplied by the :math:`(2l+1)/2` + prefactor in the expansion of the scattering source into Legendre + moments in the neutron transport equation. + Parameters ---------- in_groups : Iterable of Integral or 'all' From 44ba08f70a2478dc3c933a6a1d0a93cef9c88f06 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Wed, 11 May 2016 14:29:11 -0400 Subject: [PATCH 116/147] Removed reference to OpenCG in Pandas DF getter for ScatterMatrixXS --- openmc/mgxs/mgxs.py | 15 +++++++-------- 1 file changed, 7 insertions(+), 8 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index eed0627bf..cc192855b 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2190,7 +2190,7 @@ class ScatterMatrixXS(MGXS): return xs def get_pandas_dataframe(self, groups='all', nuclides='all', moment='all', - xs_type='macro', summary=None): + xs_type='macro', distribcell_paths=True): """Build a Pandas DataFrame for the MGXS data. This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but @@ -2214,12 +2214,11 @@ class ScatterMatrixXS(MGXS): xs_type: {'macro', 'micro'} Return macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - summary : None or openmc.Summary - An optional Summary object to be used to construct columns for - distribcell tally filters (default is None). The geometric - information in the Summary object is embedded into a multi-index - column with a geometric "path" to each distribcell intance. - NOTE: This option requires the OpenCG Python package. + distribcell_paths : bool, optional + Construct columns for distribcell tally filters (default is True). + The geometric information in the Summary object is embedded into a + Multi-index column with a geometric "path" to each distribcell + instance. Returns ------- @@ -2235,7 +2234,7 @@ class ScatterMatrixXS(MGXS): """ df = super(ScatterMatrixXS, self).get_pandas_dataframe( - groups, nuclides, xs_type, summary) + groups, nuclides, xs_type, distribcell_paths) # Add a moment column to dataframe moments = np.array(['P{}'.format(i) for i in range(self.legendre_order+1)]) From 98a02d5d5048308eb608c1513d2f4bd6ee40ede8 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Wed, 11 May 2016 21:19:30 -0400 Subject: [PATCH 117/147] Simplifications as per comments from @wbinventor and @paulromano. Next is updating notebook --- openmc/mgxs/library.py | 372 ++++++++++------------- openmc/mgxs_library.py | 671 ++++++++++++++++++++++++++++------------- 2 files changed, 620 insertions(+), 423 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index dfa55b3a5..991a98f62 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -15,14 +15,9 @@ import openmc.checkvalue as cv if sys.version_info[0] >= 3: basestring = str -# The following represent the most accurate MGXS generation strategy -# for use in the MG mode of OpenMC. -OPENMC_MG_MGXS_TYPES = ['transport', 'absorption', 'nu-fission', 'chi', - 'scatter matrix', 'nu-scatter matrix'] - class Library(object): - """A multi-group cross section library for some energy group structure. + '''A multi-group cross section library for some energy group structure. This class can be used for both OpenMC input generation and tally data post-processing to compute spatially-homogenized and energy-integrated @@ -84,7 +79,7 @@ class Library(object): Whether or not the Library's tallies use SciPy's LIL sparse matrix format for compressed data storage - """ + ''' def __init__(self, openmc_geometry, by_nuclide=False, mgxs_types=None, name=''): @@ -252,7 +247,8 @@ class Library(object): @domain_type.setter def domain_type(self, domain_type): - cv.check_value('domain type', domain_type, tuple(openmc.mgxs.DOMAIN_TYPES)) + cv.check_value('domain type', domain_type, + tuple(openmc.mgxs.DOMAIN_TYPES)) self._domain_type = domain_type @domains.setter @@ -304,7 +300,7 @@ class Library(object): @sparse.setter def sparse(self, sparse): - """Convert tally data from NumPy arrays to SciPy list of lists (LIL) + '''Convert tally data from NumPy arrays to SciPy list of lists (LIL) sparse matrices, and vice versa. This property may be used to reduce the amount of data in memory during @@ -312,7 +308,7 @@ class Library(object): matrices internally within the Tally object. All tally data access properties and methods will return data as a dense NumPy array. - """ + ''' cv.check_type('sparse', sparse, bool) @@ -325,14 +321,14 @@ class Library(object): self._sparse = sparse def build_library(self): - """Initialize MGXS objects in each domain and for each reaction type + '''Initialize MGXS objects in each domain and for each reaction type in the library. This routine will populate the all_mgxs instance attribute dictionary with MGXS subclass objects keyed by each domain ID (e.g., Material IDs) and cross section type (e.g., 'nu-fission', 'total', etc.). - """ + ''' # Initialize MGXS for each domain and mgxs type and store in dictionary for domain in self.domains: @@ -355,7 +351,7 @@ class Library(object): self.all_mgxs[domain.id][mgxs_type] = mgxs def add_to_tallies_file(self, tallies_file, merge=True): - """Add all tallies from all MGXS objects to a tallies file. + '''Add all tallies from all MGXS objects to a tallies file. NOTE: This assumes that :meth:`Library.build_library` has been called @@ -363,12 +359,12 @@ class Library(object): ---------- tallies_file : openmc.Tallies A Tallies collection to add each MGXS' tallies to generate a - "tallies.xml" input file for OpenMC + 'tallies.xml' input file for OpenMC merge : bool Indicate whether tallies should be merged when possible. Defaults to True. - """ + ''' cv.check_type('tallies_file', tallies_file, openmc.Tallies) @@ -380,7 +376,7 @@ class Library(object): tallies_file.append(tally, merge=merge) def load_from_statepoint(self, statepoint): - """Extracts tallies in an OpenMC StatePoint with the data needed to + '''Extracts tallies in an OpenMC StatePoint with the data needed to compute multi-group cross sections. This method is needed to compute cross section data from tallies @@ -399,7 +395,7 @@ class Library(object): When this method is called with a statepoint that has not been linked with a summary object. - """ + ''' cv.check_type('statepoint', statepoint, openmc.StatePoint) @@ -423,7 +419,7 @@ class Library(object): mgxs.sparse = self.sparse def get_mgxs(self, domain, mgxs_type): - """Return the MGXS object for some domain and reaction rate type. + '''Return the MGXS object for some domain and reaction rate type. This routine searches the library for an MGXS object for the spatial domain and reaction rate type requested by the user. @@ -448,7 +444,7 @@ class Library(object): If no MGXS object can be found for the requested domain or multi-group cross section type - """ + ''' if self.domain_type == 'material': cv.check_type('domain', domain, (openmc.Material, Integral)) @@ -464,7 +460,7 @@ class Library(object): if domain_id == domain.id: break else: - msg = 'Unable to find MGXS for {0} "{1}" in ' \ + msg = 'Unable to find MGXS for "{0}" "{1}" in ' \ 'library'.format(self.domain_type, domain_id) raise ValueError(msg) else: @@ -478,7 +474,7 @@ class Library(object): return self.all_mgxs[domain_id][mgxs_type] def get_condensed_library(self, coarse_groups): - """Construct an energy-condensed version of this library. + '''Construct an energy-condensed version of this library. This routine condenses each of the multi-group cross sections in the library to a coarse energy group structure. NOTE: This routine must @@ -505,7 +501,7 @@ class Library(object): -------- MGXS.get_condensed_xs(coarse_groups) - """ + ''' if self.sp_filename is None: msg = 'Unable to get a condensed coarse group cross section ' \ @@ -534,7 +530,7 @@ class Library(object): return condensed_library def get_subdomain_avg_library(self): - """Construct a subdomain-averaged version of this library. + '''Construct a subdomain-averaged version of this library. This routine averages each multi-group cross section across distribcell instances. The method performs spatial homogenization to compute the @@ -557,7 +553,7 @@ class Library(object): -------- MGXS.get_subdomain_avg_xs(subdomains) - """ + ''' if self.sp_filename is None: msg = 'Unable to get a subdomain-averaged cross section ' \ @@ -585,7 +581,7 @@ class Library(object): def build_hdf5_store(self, filename='mgxs.h5', directory='mgxs', subdomains='all', nuclides='all', xs_type='macro', row_column='inout'): - """Export the multi-group cross section library to an HDF5 binary file. + '''Export the multi-group cross section library to an HDF5 binary file. This method constructs an HDF5 file which stores the library's multi-group cross section data. The data is stored in a hierarchy of @@ -628,7 +624,7 @@ class Library(object): -------- MGXS.build_hdf5_store(filename, directory, xs_type) - """ + ''' if self.sp_filename is None: msg = 'Unable to export multi-group cross section library ' \ @@ -648,7 +644,7 @@ class Library(object): full_filename = os.path.join(directory, filename) full_filename = full_filename.replace(' ', '-') f = h5py.File(full_filename, 'w') - f.attrs["# groups"] = self.num_groups + f.attrs['# groups'] = self.num_groups f.close() # Export MGXS for each domain and mgxs type to an HDF5 file @@ -663,7 +659,7 @@ class Library(object): nuclides=nuclides, row_column=row_column) def dump_to_file(self, filename='mgxs', directory='mgxs'): - """Store this Library object in a pickle binary file. + '''Store this Library object in a pickle binary file. Parameters ---------- @@ -676,7 +672,7 @@ class Library(object): -------- Library.load_from_file(filename, directory) - """ + ''' cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) @@ -693,7 +689,7 @@ class Library(object): @staticmethod def load_from_file(filename='mgxs', directory='mgxs'): - """Load a Library object from a pickle binary file. + '''Load a Library object from a pickle binary file. Parameters ---------- @@ -711,7 +707,7 @@ class Library(object): -------- Library.dump_to_file(mgxs_lib, filename, directory) - """ + ''' cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) @@ -729,7 +725,7 @@ class Library(object): def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, filename='mg_cross_sections', directory='./', return_names=True): - """Creates a cross-section data library file for the Multi-Group + '''Creates a cross-section data library file for the Multi-Group mode of OpenMC. Parameters @@ -740,11 +736,11 @@ class Library(object): nuclide this will be set to 'macro' regardless. domain_names : Iterable of str List of names to apply to the xsdata entries in the - resultant mgxs data file. Defaults to "set1", "set2", ... + resultant mgxs data file. Defaults to 'set1', 'set2', ... xs_ids : str or Iterable of str - Cross section set identifier (i.e., "71c") for all + Cross section set identifier (i.e., '71c') for all data sets (if only str) or for each individual one - (if iterable of str). Defaults to '1g' + (if iterable of str). Defaults to '1m'. filename : str Filename for the pickle file. Defaults to 'mg_cross_sections'. directory : str @@ -772,7 +768,11 @@ class Library(object): -------- Library.dump_to_file(mgxs_lib, filename, directory) - """ + ''' + + # Check to ensure the Library contains the correct + # multi-group cross section types + self.check_library_for_openmc_mgxs() # Check the provided parameters cv.check_value('xs_type', xs_type, ['macro', 'micro']) @@ -786,14 +786,18 @@ class Library(object): else: cv.check_iterable_type('xs_ids', xs_ids, basestring) else: - xs_ids = ['1g' for i in range(len(self.domains))] + xs_ids = ['1m' for i in range(len(self.domains))] cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) + # Make sure statepoint has been loaded + if self._sp_filename is None: + msg = 'A StatePoint must be loaded before calling ' \ + 'the write_mg_library() function' + raise ValueError(msg) + # Construct the collection of the nuclides to report - if self.by_nuclide: - nuclides = self.all_mgxs[1][self.mgxs_types[-1]].get_all_nuclides() - else: + if not self.by_nuclide: xs_type = 'macro' # Make directory if it does not exist and build our filename @@ -813,213 +817,98 @@ class Library(object): xsdatas = [] mat_names = {} - for i in range(len(self.domains)): + for i, domain in enumerate(self.domains): - id = self.domains[i].id - if not self.by_nuclide: + mat_names[domain.id] = {} + if self.by_nuclide: + nuclides = list(domain.get_all_nuclides().keys()) + else: + nuclides = ['total'] + for nuclide in nuclides: # Build & add metadata to XSdata object - # (Use i here because k in nuclides will add chars to this) if domain_names is None: name = 'set' + str(i + 1) else: name = domain_names[i] + if nuclide is not 'total': + name += '_' + nuclide name += '.' + xs_ids[i] + + # Store the name + mat_names[domain.id][nuclide] = name + xsdata = openmc.XSdata(name, self.energy_groups) xsdata.order = order + if nuclide is not 'total': + xsdata.zaid = self._nuclides[nuclide][0] + xsdata.awr = self._nuclides[nuclide][1] - mat_names[id] = name - + nuclide = [nuclide] # Now get xs data itself if 'transport' in self.mgxs_types: - if self.correction == 'P0': - xsdata.set_total(self.all_mgxs[id]['transport'], - xs_type=xs_type, subdomains=(id,)) - else: - msg = "The use of a transport cross section " + \ - "requires the correction attribute to be" + \ - "set to 'P0' to produce valid cross " + \ - "section libraries" - raise ValueError(msg) + mymgxs = self.get_mgxs(domain, 'transport') + xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) elif 'total' in self.mgxs_types: - xsdata.set_total(self.all_mgxs[id]['total'], - xs_type=xs_type, subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'total') + xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) if 'absorption' in self.mgxs_types: - xsdata.set_absorption(self.all_mgxs[id]['absorption'], - xs_type=xs_type, - subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'absorption') + xsdata.set_absorption_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) if 'fission' in self.mgxs_types: - xsdata.set_fission(self.all_mgxs[id]['fission'], - xs_type=xs_type, subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'fission') + xsdata.set_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) if 'kappa-fission' in self.mgxs_types: - xsdata.set_k_fission(self.all_mgxs[id]['kappa-fission'], - xs_type=xs_type, subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'kappa-fission') + xsdata.set_kappa_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) if 'chi' in self.mgxs_types: - xsdata.set_chi(self.all_mgxs[id]['chi'], - xs_type=xs_type, subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'chi') + xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) if 'nu-fission' in self.mgxs_types: - xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], - xs_type=xs_type, - subdomains=(id,)) + mymgxs = self.get_mgxs(domain, 'nu-fission') + xsdata.set_nu_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=nuclide) # multiplicity requires scatter and nu-scatter if ((('scatter matrix' in self.mgxs_types) and ('nu-scatter matrix' in self.mgxs_types))): - xsdata.set_multiplicity( - self.all_mgxs[id]['nu-scatter matrix'], - self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, subdomains=(id,)) - xsdata.multiplicity = np.nan_to_num(xsdata.multiplicity) + scatt_mgxs = self.get_mgxs(domain, + 'scatter matrix') + nuscatt_mgxs = self.get_mgxs(domain, + 'nu-scatter matrix') + xsdata.set_multiplicity_mgxs(nuscatt_mgxs, scatt_mgxs, + xs_type=xs_type, + nuclide=nuclide) using_multiplicity = True else: using_multiplicity = False if using_multiplicity: - xsdata.set_scatter(self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, - subdomains=(id,)) + nuscatt_mgxs = self.get_mgxs(domain, + 'nu-scatter matrix') + xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, + nuclide=nuclide) else: if 'nu-scatter matrix' in self.mgxs_types: - xsdata.set_scatter( - self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(id,)) + nuscatt_mgxs = self.get_mgxs(domain, + 'nu-scatter matrix') + xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, + nuclide=nuclide) + # Since we are not using multiplicity, then # scattering multiplication (nu-scatter) must be # accounted for approximately by using an adjusted # absorption cross section. - # We can not do this with a transport x/s so check - # for that. if 'total' in self.mgxs_types: xsdata.absorption = \ np.subtract(xsdata.total, np.sum(xsdata.scatter[0, :, :], axis=1)) - else: - msg = "Absorption cross section must be " + \ - "provided if using a transport cross" + \ - " section and while not providing a " + \ - "scattering matrix" - raise ValueError(msg) - else: - msg = "No nu-scatter matrix data was provided. " + \ - "This means neutron balance cannot be " + \ - "achieved since (n,xn) multiplication is " + \ - "ignored." - warn(msg) - xsdata.set_scatter(self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, - subdomains=(id,)) - xsdatas.append(xsdata) - else: - mat_names[id] = {} - for nuclide in nuclides: - # Build & add metadata to XSdata object - if domain_names is None: - name = 'set' + str(i + 1) - else: - name = domain_names[i] - name += '_' + nuclide - name += '.' + xs_ids[i] - - mat_names[id][nuclide] = name - - xsdata = openmc.XSdata(name, self.energy_groups) - xsdata.order = order - xsdata.zaid = self._nuclides[nuclide][0] - xsdata.awr = self._nuclides[nuclide][1] - - # Now get xs data itself - if 'transport' in self.mgxs_types: - if self.correction == 'P0': - xsdata.set_total(self.all_mgxs[id]['transport'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - else: - msg = "The use of a transport cross section " + \ - "requires the correction attribute to be" + \ - "set to 'P0' to produce valid cross " + \ - "section libraries" - raise ValueError(msg) - elif 'total' in self.mgxs_types: - xsdata.set_total(self.all_mgxs[id]['total'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - if 'absorption' in self.mgxs_types: - xsdata.set_absorption(self.all_mgxs[id]['absorption'], - xs_type=xs_type, - subdomains=(id,), - nuclides=[nuclide]) - if 'fission' in self.mgxs_types: - xsdata.set_fission(self.all_mgxs[id]['fission'], - xs_type=xs_type, - subdomains=(id,), - nuclides=[nuclide]) - if 'kappa-fission' in self.mgxs_types: - xsdata.set_k_fission( - self.all_mgxs[id]['kappa-fission'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - if 'chi' in self.mgxs_types: - xsdata.set_chi(self.all_mgxs[id]['chi'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - if 'nu-fission' in self.mgxs_types: - xsdata.set_nu_fission(self.all_mgxs[id]['nu-fission'], - xs_type=xs_type, - subdomains=(id,), - nuclides=[nuclide]) - # multiplicity requires scatter and nu-scatter - if ((('scatter matrix' in self.mgxs_types) and - ('nu-scatter matrix' in self.mgxs_types))): - xsdata.set_multiplicity( - self.all_mgxs[id]['nu-scatter matrix'], - self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - xsdata.multiplicity = \ - np.nan_to_num(xsdata.multiplicity) - using_multiplicity = True - else: - using_multiplicity = False - - if using_multiplicity: - xsdata.set_scatter( - self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - else: - if 'nu-scatter matrix' in self.mgxs_types: - xsdata.set_scatter( - self.all_mgxs[id]['nu-scatter matrix'], - xs_type=xs_type, subdomains=(id,), - nuclides=[nuclide]) - # Since we are not using multiplicity, then - # scattering multiplication (nu-scatter) must be - # accounted for approximately by using an adjusted - # absorption cross section. - if 'total' in self.mgxs_types: - xsdata.absorption = \ - np.subtract(xsdata.total, - np.sum(xsdata.scatter[0, :, :], - axis=1)) - else: - msg = "Absorption cross section must be " + \ - "provided if using a transport cross" + \ - " section and while not providing a " + \ - "scattering matrix" - raise ValueError(msg) - else: - msg = "No nu-scatter matrix data was provided. " +\ - "This means neutron balance cannot be " + \ - "achieved since (n,xn) multiplication is " +\ - "ignored." - warn(msg) - xsdata.set_scatter( - self.all_mgxs[id]['scatter matrix'], - xs_type=xs_type, - subdomains=(id,), - nuclides=[nuclide]) - - xsdatas.append(xsdata) # Add XSdatas to file mgxs_file.add_xsdatas(xsdatas) @@ -1029,3 +918,68 @@ class Library(object): if return_names: return mat_names + + def check_library_for_openmc_mgxs(self): + """This routine will check the MGXS Types within the provided + Library to ensure the data types provided can be used to create + a MGXS Library for OpenMC's Multi-Group mode via the + `Library.write_mg_library` method. + The rules to check include: + - Fission is not required as a fixed source problem could be + the target. + - Absorption is required. + - A nu-scatter matrix is required. + - Having both nu-scatter (of any order) and scatter + (at least isotropic) matrices is preferred + - If only nu-scatter, need total (not transport), to + be used in adjusting absorption + (i.e., reduced_abs = tot - nuscatt) + - Either total or transport should be present. + - Both can be available if one wants, but we should + use whatever corresponds to Library.correction (if P0: transport) + + Raises + ------ + ValueError + When the Library object is initialized with insufficient types of + cross sections for the Library. + + See also + -------- + Library.write_mg_library(...) + + """ + + error_flag = False + # Ensure absorption is present + if 'absorption' not in self.mgxs_types: + error_flag = True + msg = 'Absorption MGXS type is required but not provided.' + warn(msg) + # Ensure nu-scattering matrix is required + if 'nu-scatter matrix' not in self.mgxs_types: + error_flag = True + msg = 'Nu-Scatter Matrix MGXS type is required but not provided.' + warn(msg) + else: + # Ok, now see the status of scatter + if 'scatter matrix' not in self.mgxs_types: + # We dont have both nu-scatter and scatter, therefore + # we need total, and not transport. + if 'total' not in self.mgxs_types: + error_flag = True + msg = 'Total MGXS type is required if a ' \ + 'scattering matrix is not provided.' + warn(msg) + # Total or transport can be present, but if using + # self.correction=="P0", then we should use transport. + if (((self.correction is "P0") and + ('transport' not in self.mgxs_types))): + error_flag = True + msg = 'Transport MGXS type is required since a "P0" correction ' \ + 'is applied, but a Transport MGXS is not provided.' + warn(msg) + + if error_flag: + msg = "Invalid MGXS configuration encountered." + raise ValueError(msg) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index ba9ba75b0..f9353f9cc 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -122,12 +122,23 @@ class XSdata(object): Legendre polynomial form). Dict contains two keys: 'enable' and 'num_points'. 'enable' is a boolean and 'num_points' is the number of points to use, if 'enable' is True. + representation : {'isotropic', 'angle'} + Method used in generating the MGXS (isotropic or angle-dependent flux + weighting). num_azimuthal : int Number of equal width angular bins that the azimuthal angular domain is subdivided into. This only applies when ``representation`` is "angle". num_polar : int Number of equal width angular bins that the polar angular domain is subdivided into. This only applies when ``representation`` is "angle". + vector_shape : iterable of int + Dimensionality of vector multi-group cross sections (e.g., the total + cross section). The return result depends on the value of + ``representation``. + matrix_shape : iterable of int + Dimensionality of matrix multi-group cross sections (e.g., the + scattering matrix cross section). The return result depends on the + value of ``representation``. total : numpy.ndarray Group-wise total cross section ordered by increasing group index (i.e., fast to thermal). If ``representation`` is "isotropic", then the length @@ -173,7 +184,7 @@ class XSdata(object): azimuthal angles times the number of polar angles, with the inner-dimension being groups, intermediate-dimension being azimuthal angles and outer-dimension being the polar angles. - k_fission : numpy.ndarray + kappa_fission : numpy.ndarray Group-wise kappa-fission cross section ordered by increasing group index (i.e., fast to thermal). If ``representation`` is "isotropic", then the length of this list should equal the number of groups in the @@ -225,7 +236,7 @@ class XSdata(object): self._multiplicity = None self._fission = None self._nu_fission = None - self._k_fission = None + self._kappa_fission = None self._chi = None self._use_chi = None @@ -302,8 +313,8 @@ class XSdata(object): return self._nu_fission @property - def k_fission(self): - return self._k_fission + def kappa_fission(self): + return self._kappa_fission @property def chi(self): @@ -317,6 +328,24 @@ class XSdata(object): else: return self._order + @property + def vector_shape(self): + if self.representation is 'isotropic': + return (self.energy_groups.num_groups,) + elif self.representation is 'angle': + return (self.num_polar, self.num_azimuthal, + self.energy_groups.num_groups) + + @property + def matrix_shape(self): + if self.representation is 'isotropic': + return (self.energy_groups.num_groups, + self.energy_groups.num_groups) + elif self.representation is 'angle': + return (self.num_polar, self.num_azimuthal, + self.energy_groups.num_groups, + self.energy_groups.num_groups) + @name.setter def name(self, name): check_type('name for XSdata', name, basestring) @@ -326,6 +355,11 @@ class XSdata(object): def energy_groups(self, energy_groups): # Check validity of energy_groups check_type('energy_groups', energy_groups, openmc.mgxs.EnergyGroups) + + if energy_group.group_edges is None: + msg = 'Unable to assign an EnergyGroups object ' + \ + 'with uninitialized group edges' + raise ValueError(msg) self._energy_groups = energy_groups @representation.setter @@ -414,141 +448,196 @@ class XSdata(object): @total.setter def total(self, total): - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) + """This method sets the total cross section by performing a + deep-copy of the provided ndarray. + + Parameters + ---------- + total: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ + # check we have a numpy list check_type('total', total, np.ndarray, expected_iter_type=Real) - if total.shape == shape: - self._total = np.copy(total) - else: - msg = 'Shape of provided total "{0}" does not match shape ' \ - 'required, "{1}"'.format(total.shape, shape) - raise ValueError(msg) + # Check the dimensions of the data + check_value('total shape', total.shape, self.vector_shape) + + self._total = np.copy(total) @absorption.setter def absorption(self, absorption): - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) + """This method sets the absorption cross section by performing a + deep-copy of the provided ndarray. + + Parameters + ---------- + absorption: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # check we have a numpy list check_type('absorption', absorption, np.ndarray, expected_iter_type=Real) - if absorption.shape == shape: - self._absorption = np.copy(absorption) - else: - msg = 'Shape of provided absorption "{0}" does not match shape ' \ - 'required, "{1}"'.format(absorption.shape, shape) - raise ValueError(msg) + # Check the dimensions of the data + check_value('absorption shape', absorption.shape, self.vector_shape) + + self._absorption = np.copy(absorption) @fission.setter def fission(self, fission): - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - # check we have a numpy list - check_type('fission', fission, np.ndarray, expected_iter_type=Real) - if fission.shape == shape: - self._fission = np.copy(fission) - if np.sum(self._fission) > 0.0: - self._fissionable = True - else: - msg = 'Shape of provided fission "{0}" does not match shape ' \ - 'required, "{1}"'.format(fission.shape, shape) - raise ValueError(msg) + """This method sets the fission cross section by performing a + deep-copy of the provided ndarray. - @k_fission.setter - def k_fission(self, k_fission): - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) + Parameters + ---------- + fission: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # check we have a numpy list - check_type('k_fission', k_fission, np.ndarray, + check_type('fission', fission, np.ndarray, expected_iter_type=Real) - if k_fission.shape == shape: - self._k_fission = np.copy(k_fission) - if np.sum(self._k_fission) > 0.0: - self._fissionable = True - else: - msg = 'Shape of provided k_fission "{0}" does not match ' \ - 'shape required, "{1}"'.format(k_fission.shape, shape) - raise ValueError(msg) + # Check the dimensions of the data + check_value('fission shape', fission.shape, self.vector_shape) + + self._fission = np.copy(fission) + + if np.sum(self._fission) > 0.0: + self._fissionable = True + + @kappa_fission.setter + def kappa_fission(self, kappa_fission): + """This method sets the kappa_fission cross section by performing a + deep-copy of the provided ndarray. + + Parameters + ---------- + kappa_fission: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ + # check we have a numpy list + check_type('kappa_fission', fission, np.ndarray, + expected_iter_type=Real) + # Check the dimensions of the data + check_value('kappa fission shape', kappa_fission.shape, + self.vector_shape) + + self._kappa_fission = np.copy(fission) + + if np.sum(self._kappa_fission) > 0.0: + self._fissionable = True @chi.setter def chi(self, chi): + """This method sets the chi cross section by performing a + deep-copy of the provided ndarray. + + Parameters + ---------- + chi: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if self._use_chi is not None: if not self._use_chi: - msg = 'Providing chi when nu_fission already provided as matrix!' + msg = 'Providing chi when nu_fission already provided as a' \ + 'matrix' raise ValueError(msg) - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups,) - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) # check we have a numpy list check_type('chi', chi, np.ndarray, expected_iter_type=Real) - if chi.shape == shape: - self._chi = np.copy(chi) - else: - msg = 'Shape of provided chi "{0}" does not match shape ' \ - 'required, "{1}"'.format(chi.shape, shape) - raise ValueError(msg) + # Check the dimensions of the data + check_value('chi shape', chi.shape, self.vector_shape) + + self._chi = np.copy(chi) + if self._use_chi is not None: self._use_chi = True @scatter.setter def scatter(self, scatter): - if self._representation is 'isotropic': - shape = (self.num_orders, self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 3 - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, self.num_orders, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 5 + """This method sets the scattering matrix cross sections + by performing a deep-copy of the provided ndarray. + + Parameters + ---------- + scatter : ndarrays + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # check we have a numpy list - check_iterable_type('scatter', scatter, expected_type=Real, - max_depth=max_depth) - if scatter.shape == shape: - self._scatter = np.copy(scatter) - else: - msg = 'Shape of provided scatter "{0}" does not match shape ' \ - 'required, "{1}"'.format(scatter.shape, shape) - raise ValueError(msg) + check_type('scatter', scatter, np.ndarray, expected_iter_type=Real, + max_depth=len(scatter.shape)) + # Check the dimensions of the data + check_value('scatter shape', scatter.shape, self.matrix_shape) + + self._scatter = np.copy(scatter) @multiplicity.setter def multiplicity(self, multiplicity): - if self._representation is 'isotropic': - shape = (self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 2 - elif self._representation is 'angle': - shape = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - max_depth = 4 + """This method sets the scattering multiplicity matrix cross sections + by performing a deep-copy of the provided ndarray. + + Parameters + ---------- + multiplicity : ndarrays + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # check we have a numpy list - check_iterable_type('multiplicity', multiplicity, expected_type=Real, - max_depth=max_depth) - if multiplicity.shape == shape: - self._multiplicity = np.copy(multiplicity) - else: - msg = 'Shape of provided multiplicity "{0}" does not match shape' \ - ' required, "{1}"'.format(multiplicity.shape, shape) - raise ValueError(msg) + check_type('multiplicity', multiplicity, np.ndarray, + expected_iter_type=Real, max_depth=len(multiplicity.shape)) + # Check the dimensions of the data + check_value('multiplicity shape', multiplicity.shape, + self.matrix_shape) + + self._multiplicity = np.copy(multiplicity) @nu_fission.setter def nu_fission(self, nu_fission): + """This method sets the nu_fission cross section by performing a + deep-copy of the provided ndarray. + + Parameters + ---------- + nu_fission: ndarray + Array of group-wise cross sections to apply + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. @@ -559,47 +648,54 @@ class XSdata(object): # chi already has been set. If not, we just check that this is OK # and set the use_chi flag accordingly - # First lets set our dimensions here since they get used repeatedly - # throughout this code. - if self._representation is 'isotropic': - shape_vec = (self._energy_groups.num_groups,) - shape_mat = (self._energy_groups.num_groups, - self._energy_groups.num_groups) - elif self._representation is 'angle': - shape_vec = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups) - shape_mat = (self._num_polar, self._num_azimuthal, - self._energy_groups.num_groups, - self._energy_groups.num_groups) - - # Begin by checking the case when chi has already been given and - # thus the rules for filling in nu_fission are set. - if self._use_chi is not None: - if self._use_chi: - shape = shape_vec - else: - shape = shape_mat - if nu_fission.shape != shape: - msg = 'Invalid Shape of Nu_fission!' - raise ValueError(msg) - else: - # Get shape of nu_fission to determine if we need chi or not - if nu_fission.shape == shape_vec: - self._use_chi = True - elif nu_fission.shape == shape_mat: - self._use_chi = False - else: - msg = 'Invalid Shape of Nu_fission!' - raise ValueError(msg) - - # check we have a numpy list + # First, check we have a numpy list check_type('nu_fission', nu_fission, np.ndarray, - expected_iter_type=Real) + expected_iter_type=Real, max_depth=len(nu_fission.shape)) + + if self._use_chi is not None: + # Check the dimensions of the data + if self._use_chi: + check_value('nu_fission shape', nu_fission.shape, + self.vector_shape) + else: + check_value('nu_fission shape', nu_fission.shape, + self.matrix_shape) + else: + # Make sure the dimensions are at least right + check_value('nu_fission shape', nu_fission.shape, + (self.vector_shape, self.matrix_shape)) + # Then find out which one we have so we can set use_chi + if nu_fission.shape == self.vector_shape: + self._use_chi = True + else: + self._use_chi = False + self._nu_fission = np.copy(nu_fission) if np.sum(self._nu_fission) > 0.0: self._fissionable = True - def set_total(self, total, subdomain, nuclide='sum', xs_type='macro'): + def set_total_mgxs(self, total, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.TotalXS or + openmc.mgxs.TransportXS to be used to set the total cross section + for this XSdata object. + + Parameters + ---------- + total: {openmc.mgxs.TotalXS, openmc.mgxs.TransportXS} + MGXS Object containing the total or transport cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if not isinstance(total, (openmc.mgxs.TotalXS, openmc.mgxs.TransportXS)): msg = 'Method must be passed an openmc.mgxs.TotalXS or ' \ @@ -607,59 +703,119 @@ class XSdata(object): raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != total.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', total.energy_groups, [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', total.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._total = total.get_xs(subdomain=subdomains, nuclides=nuclide, - xs_type=xs_type) + self._total = total.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_absorption(self, absorption, subdomain, nuclide='sum', - xs_type='macro'): + def set_absorption_mgxs(self, absorption, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.AbsorptionXS + to be used to set the absorption cross section for this XSdata object. + + Parameters + ---------- + absorption: openmc.mgxs.AbsorptionXS + MGXS Object containing the absorption cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if not isinstance(absorption, openmc.mgxs.AbsorptionXS): msg = 'Method must be passed an openmc.mgxs.AbsorptionXS' raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != absorption.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', absorption.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', absorption.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._absorption = absorption.get_xs(subdomains=subdomain, - nuclides=nuclide, + self._absorption = absorption.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_fission(self, fission, subdomain, nuclide='sum', xs_type='macro'): + def set_fission_mgxs(self, fission, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.FissionXS + to be used to set the fission cross section for this XSdata object. + + Parameters + ---------- + fission: openmc.mgxs.FissionXS + MGXS Object containing the fission cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if not isinstance(fission, openmc.mgxs.FissionXS): msg = 'Method must be passed an openmc.mgxs.FissionXS' raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != fission.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', fission.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', fission.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._fission = fission.get_xs(subdomains=subdomain, - nuclides=nuclide, + self._fission = fission.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_nu_fission(self, nu_fission, subdomain, nuclide='sum', - xs_type='macro'): + def set_nu_fission_mgxs(self, nu_fission, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.NuFissionXS + to be used to set the nu-fission cross section for this XSdata object. + + Parameters + ---------- + nu_fission: openmc.mgxs.NuFissionXS + MGXS Object containing the nu-fission cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. @@ -668,14 +824,15 @@ class XSdata(object): raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != nu_fission.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', nu_fission.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', nu_fission.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._nu_fission = nu_fission.get_xs(subdomains=subdomain, - nuclides=nuclide, + self._nu_fission = nu_fission.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' @@ -686,27 +843,68 @@ class XSdata(object): if np.sum(self._nu_fission) > 0.0: self._fissionable = True - def set_k_fission(self, k_fission, subdomain, nuclide='sum', - xs_type='macro'): + def set_kappa_fission_mgxs(self, k_fission, nuclide='total', + xs_type='macro'): + """This method allows for an openmc.mgxs.KappaFissionXS + to be used to set the kappa-fission cross section for this XSdata + object. + + Parameters + ---------- + kappa_fission: openmc.mgxs.KappaFissionXS + MGXS Object containing the kappa-fission cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if not isinstance(k_fission, openmc.mgxs.KappaFissionXS): msg = 'Method must be passed an openmc.mgxs.KappaFissionXS' raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != k_fission.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', k_fission.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', k_fission.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._k_fission = k_fission.get_xs(subdomains=subdomain, - nuclides=nuclide, - xs_type=xs_type) + self._kappa_fission = k_fission.get_xs(nuclides=nuclide, + xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_chi(self, chi, subdomain, nuclide='sum', xs_type='macro'): + def set_chi_mgxs(self, chi, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.Chi + to be used to set chi for this XSdata object. + + Parameters + ---------- + chi: openmc.mgxs.Chi + MGXS Object containing chi for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if self._use_chi is not None: if not self._use_chi: msg = 'Providing chi when nu_fission already provided as a ' \ @@ -718,14 +916,14 @@ class XSdata(object): raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != chi.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', chi.energy_groups, [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', chi.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._chi = chi.get_xs(subdomains=subdomain, - nuclides=nuclide, + self._chi = chi.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' @@ -734,55 +932,102 @@ class XSdata(object): if self._use_chi is not None: self._use_chi = True - def set_scatter(self, scatter, subdomain, nuclide='sum', xs_type='macro'): + def set_scatter_mgxs(self, scatter, nuclide='total', xs_type='macro'): + """This method allows for an openmc.mgxs.ScatterMatrixXS + to be used to set the scatter matrix cross section for this XSdata + object. + + Parameters + ---------- + scatter: openmc.mgxs.ScatterMatrixXS + MGXS Object containing the scatter matrix cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' raise TypeError(msg) # Make sure passed MGXS object contains correct group structure - if self.energy_groups != scatter.energy_groups: - msg = 'Group structure of provided data does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + check_value('energy_groups', scatter.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', scatter.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._scatter = scatter.get_xs(subdomains=subdomain, - nuclides=nuclide, + self._scatter = scatter.get_xs(nuclides=nuclide, xs_type=xs_type) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_multiplicity(self, multiplicity, scatter, subdomain, - nuclide='sum', xs_type='macro'): - if not isinstance(multiplicity, openmc.mgxs.ScatterMatrixXS): + def set_multiplicity_mgxs(self, nuscatter, scatter, nuclide='total', + xs_type='macro'): + """This method allows for an openmc.mgxs.NuScatterMatrixXS and + openmc.mgxs.ScatterMatrixXS to be used to set the scattering + multiplicity for this XSdata object. + + Parameters + ---------- + nuscatter: openmc.mgxs.NuScatterMatrixXS + MGXS Object containing the nu-scattering matrix cross section + for the domain of interest. + scatter: openmc.mgxs.ScatterMatrixXS + MGXS Object containing the scattering matrix cross section + for the domain of interest. + nuclide : str + Individual nuclide (or 'total' if obtaining material-wise data) + to gather data for. Defaults to 'total'. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. + + Raises + ------ + ValueError + When invalid parameters are passed. + """ + if not isinstance(nuscatter, openmc.mgxs.NuScatterMatrixXS): msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' raise TypeError(msg) if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' raise TypeError(msg) - # Make sure passed MGXS objects contain correct group structure - if self.energy_groups != multiplicity.energy_groups: - msg = 'Group structure of "multiplicity" does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) - if self.energy_groups != scatter.energy_groups: - msg = 'Group structure of "scatter" does not match' \ - ' group structure of XSdata object' - raise ValueError(msg) + # Make sure passed MGXS object contains correct group structure + check_value('energy_groups', nuscatter.energy_groups, + [self.energy_groups]) + check_value('energy_groups', scatter.energy_groups, + [self.energy_groups]) + + # Make sure passed MGXS object has correct domain type + check_value('domain_type', nuscatter.domain_type, + ['universe', 'cell', 'material']) + check_value('domain_type', scatter.domain_type, + ['universe', 'cell', 'material']) if self._representation is 'isotropic': - nuscatt = multiplicity.get_xs(subdomains=subdomain, - nuclides=nuclide, - xs_type=xs_type) - scatt = scatter.get_xs(subdomains=subdomain, - nuclides=nuclide, + nuscatt = nuscatter.get_xs(nuclides=nuclide, + xs_type=xs_type) + scatt = scatter.get_xs(nuclides=nuclide, xs_type=xs_type) self._multiplicity = np.divide(nuscatt, scatt) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) + self._multiplicity = np.nan_to_num(self._multiplicity) def _get_xsdata_xml(self): element = ET.Element('xsdata') @@ -858,9 +1103,9 @@ class XSdata(object): subelement = ET.SubElement(element, 'fission') subelement.text = ndarray_to_string(self._fission) - if self._k_fission is not None: + if self._kappa_fission is not None: subelement = ET.SubElement(element, 'k_fission') - subelement.text = ndarray_to_string(self._k_fission) + subelement.text = ndarray_to_string(self._kappa_fission) if self._nu_fission is not None: subelement = ET.SubElement(element, 'nu_fission') @@ -947,10 +1192,8 @@ class MGXSLibrary(object): """ - if not isinstance(xsdatas, Iterable): - msg = 'Unable to create OpenMC xsdatas.xml file from "{0}" which' \ - ' is not iterable'.format(xsdatas) - raise ValueError(msg) + # Check we have an iterable of XSdatas + check_iterable_type('xsdatas', xsdatas, XSdata) for xsdata in xsdatas: self.add_xsdata(xsdata) From 6bbf83a9b6010bcabc8467d16d1c9013164b431e Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 12 May 2016 05:16:21 -0400 Subject: [PATCH 118/147] Revised docstrings and added some check_type commands instead of isinstance --- openmc/mgxs/library.py | 78 ++++++++-------- openmc/mgxs_library.py | 203 +++++++++++++++++++---------------------- 2 files changed, 134 insertions(+), 147 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 991a98f62..82b761673 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -17,7 +17,7 @@ if sys.version_info[0] >= 3: class Library(object): - '''A multi-group cross section library for some energy group structure. + """A multi-group cross section library for some energy group structure. This class can be used for both OpenMC input generation and tally data post-processing to compute spatially-homogenized and energy-integrated @@ -79,7 +79,7 @@ class Library(object): Whether or not the Library's tallies use SciPy's LIL sparse matrix format for compressed data storage - ''' + """ def __init__(self, openmc_geometry, by_nuclide=False, mgxs_types=None, name=''): @@ -300,7 +300,7 @@ class Library(object): @sparse.setter def sparse(self, sparse): - '''Convert tally data from NumPy arrays to SciPy list of lists (LIL) + """Convert tally data from NumPy arrays to SciPy list of lists (LIL) sparse matrices, and vice versa. This property may be used to reduce the amount of data in memory during @@ -308,7 +308,7 @@ class Library(object): matrices internally within the Tally object. All tally data access properties and methods will return data as a dense NumPy array. - ''' + """ cv.check_type('sparse', sparse, bool) @@ -321,14 +321,14 @@ class Library(object): self._sparse = sparse def build_library(self): - '''Initialize MGXS objects in each domain and for each reaction type + """Initialize MGXS objects in each domain and for each reaction type in the library. This routine will populate the all_mgxs instance attribute dictionary with MGXS subclass objects keyed by each domain ID (e.g., Material IDs) and cross section type (e.g., 'nu-fission', 'total', etc.). - ''' + """ # Initialize MGXS for each domain and mgxs type and store in dictionary for domain in self.domains: @@ -351,7 +351,7 @@ class Library(object): self.all_mgxs[domain.id][mgxs_type] = mgxs def add_to_tallies_file(self, tallies_file, merge=True): - '''Add all tallies from all MGXS objects to a tallies file. + """Add all tallies from all MGXS objects to a tallies file. NOTE: This assumes that :meth:`Library.build_library` has been called @@ -364,7 +364,7 @@ class Library(object): Indicate whether tallies should be merged when possible. Defaults to True. - ''' + """ cv.check_type('tallies_file', tallies_file, openmc.Tallies) @@ -376,7 +376,7 @@ class Library(object): tallies_file.append(tally, merge=merge) def load_from_statepoint(self, statepoint): - '''Extracts tallies in an OpenMC StatePoint with the data needed to + """Extracts tallies in an OpenMC StatePoint with the data needed to compute multi-group cross sections. This method is needed to compute cross section data from tallies @@ -395,7 +395,7 @@ class Library(object): When this method is called with a statepoint that has not been linked with a summary object. - ''' + """ cv.check_type('statepoint', statepoint, openmc.StatePoint) @@ -419,7 +419,7 @@ class Library(object): mgxs.sparse = self.sparse def get_mgxs(self, domain, mgxs_type): - '''Return the MGXS object for some domain and reaction rate type. + """Return the MGXS object for some domain and reaction rate type. This routine searches the library for an MGXS object for the spatial domain and reaction rate type requested by the user. @@ -444,7 +444,7 @@ class Library(object): If no MGXS object can be found for the requested domain or multi-group cross section type - ''' + """ if self.domain_type == 'material': cv.check_type('domain', domain, (openmc.Material, Integral)) @@ -474,7 +474,7 @@ class Library(object): return self.all_mgxs[domain_id][mgxs_type] def get_condensed_library(self, coarse_groups): - '''Construct an energy-condensed version of this library. + """Construct an energy-condensed version of this library. This routine condenses each of the multi-group cross sections in the library to a coarse energy group structure. NOTE: This routine must @@ -501,7 +501,7 @@ class Library(object): -------- MGXS.get_condensed_xs(coarse_groups) - ''' + """ if self.sp_filename is None: msg = 'Unable to get a condensed coarse group cross section ' \ @@ -530,7 +530,7 @@ class Library(object): return condensed_library def get_subdomain_avg_library(self): - '''Construct a subdomain-averaged version of this library. + """Construct a subdomain-averaged version of this library. This routine averages each multi-group cross section across distribcell instances. The method performs spatial homogenization to compute the @@ -553,7 +553,7 @@ class Library(object): -------- MGXS.get_subdomain_avg_xs(subdomains) - ''' + """ if self.sp_filename is None: msg = 'Unable to get a subdomain-averaged cross section ' \ @@ -581,7 +581,7 @@ class Library(object): def build_hdf5_store(self, filename='mgxs.h5', directory='mgxs', subdomains='all', nuclides='all', xs_type='macro', row_column='inout'): - '''Export the multi-group cross section library to an HDF5 binary file. + """Export the multi-group cross section library to an HDF5 binary file. This method constructs an HDF5 file which stores the library's multi-group cross section data. The data is stored in a hierarchy of @@ -624,7 +624,7 @@ class Library(object): -------- MGXS.build_hdf5_store(filename, directory, xs_type) - ''' + """ if self.sp_filename is None: msg = 'Unable to export multi-group cross section library ' \ @@ -659,7 +659,7 @@ class Library(object): nuclides=nuclides, row_column=row_column) def dump_to_file(self, filename='mgxs', directory='mgxs'): - '''Store this Library object in a pickle binary file. + """Store this Library object in a pickle binary file. Parameters ---------- @@ -672,7 +672,7 @@ class Library(object): -------- Library.load_from_file(filename, directory) - ''' + """ cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) @@ -689,7 +689,7 @@ class Library(object): @staticmethod def load_from_file(filename='mgxs', directory='mgxs'): - '''Load a Library object from a pickle binary file. + """Load a Library object from a pickle binary file. Parameters ---------- @@ -707,7 +707,7 @@ class Library(object): -------- Library.dump_to_file(mgxs_lib, filename, directory) - ''' + """ cv.check_type('filename', filename, basestring) cv.check_type('directory', directory, basestring) @@ -725,7 +725,7 @@ class Library(object): def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, filename='mg_cross_sections', directory='./', return_names=True): - '''Creates a cross-section data library file for the Multi-Group + """Creates a cross-section data library file for the Multi-Group mode of OpenMC. Parameters @@ -768,7 +768,7 @@ class Library(object): -------- Library.dump_to_file(mgxs_lib, filename, directory) - ''' + """ # Check to ensure the Library contains the correct # multi-group cross section types @@ -904,10 +904,11 @@ class Library(object): # accounted for approximately by using an adjusted # absorption cross section. if 'total' in self.mgxs_types: - xsdata.absorption = \ + xsdata._absorption = \ np.subtract(xsdata.total, np.sum(xsdata.scatter[0, :, :], axis=1)) + xsdatas.append(xsdata) # Add XSdatas to file @@ -925,24 +926,20 @@ class Library(object): a MGXS Library for OpenMC's Multi-Group mode via the `Library.write_mg_library` method. The rules to check include: - - Fission is not required as a fixed source problem could be - the target. - - Absorption is required. + - Either total or transport should be present. + - Both can be available if one wants, but we should + use whatever corresponds to Library.correction (if P0: transport) + - Absorption and total (or transport) are required. + - A nu-fission cross section and chi values are not required as a + fixed source problem could be the target. + - Fission and kappa-fission are not required as they are only + needed to support tallies the user may wish to request. - A nu-scatter matrix is required. - Having both nu-scatter (of any order) and scatter (at least isotropic) matrices is preferred - If only nu-scatter, need total (not transport), to be used in adjusting absorption (i.e., reduced_abs = tot - nuscatt) - - Either total or transport should be present. - - Both can be available if one wants, but we should - use whatever corresponds to Library.correction (if P0: transport) - - Raises - ------ - ValueError - When the Library object is initialized with insufficient types of - cross sections for the Library. See also -------- @@ -979,7 +976,12 @@ class Library(object): msg = 'Transport MGXS type is required since a "P0" correction ' \ 'is applied, but a Transport MGXS is not provided.' warn(msg) + elif (((self.correction is None) and + ('total' not in self.mgxs_types))): + error_flag = True + msg = 'Total MGXS type is required, but not provided.' + warn(msg) if error_flag: - msg = "Invalid MGXS configuration encountered." + msg = 'Invalid MGXS configuration encountered.' raise ValueError(msg) diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index f9353f9cc..29d0bfdd7 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -449,17 +449,18 @@ class XSdata(object): @total.setter def total(self, total): """This method sets the total cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- total: ndarray Array of group-wise cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ # check we have a numpy list @@ -472,18 +473,20 @@ class XSdata(object): @absorption.setter def absorption(self, absorption): """This method sets the absorption cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- absorption: ndarray Array of group-wise cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # check we have a numpy list check_type('absorption', absorption, np.ndarray, expected_iter_type=Real) @@ -495,18 +498,20 @@ class XSdata(object): @fission.setter def fission(self, fission): """This method sets the fission cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- fission: ndarray Array of group-wise cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # check we have a numpy list check_type('fission', fission, np.ndarray, expected_iter_type=Real) @@ -521,18 +526,20 @@ class XSdata(object): @kappa_fission.setter def kappa_fission(self, kappa_fission): """This method sets the kappa_fission cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- kappa_fission: ndarray Array of group-wise cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # check we have a numpy list check_type('kappa_fission', fission, np.ndarray, expected_iter_type=Real) @@ -548,18 +555,20 @@ class XSdata(object): @chi.setter def chi(self, chi): """This method sets the chi cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- chi: ndarray - Array of group-wise cross sections to apply + Array of group-wise chi values to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + if self._use_chi is not None: if not self._use_chi: msg = 'Providing chi when nu_fission already provided as a' \ @@ -580,40 +589,50 @@ class XSdata(object): def scatter(self, scatter): """This method sets the scattering matrix cross sections by performing a deep-copy of the provided ndarray. + If the angular representation is "isotropic" the shape of + the input array must be the number of scattering orders, the + number of energy groups, and the number of energy groups. If + the angular representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles, number of scattering orders, energy groups, and energy groups. Parameters ---------- scatter : ndarrays - Array of group-wise cross sections to apply + Array of cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # check we have a numpy list check_type('scatter', scatter, np.ndarray, expected_iter_type=Real, max_depth=len(scatter.shape)) # Check the dimensions of the data - check_value('scatter shape', scatter.shape, self.matrix_shape) + check_value('scatter shape', scatter.shape, self.pn_matrix_shape) self._scatter = np.copy(scatter) @multiplicity.setter def multiplicity(self, multiplicity): """This method sets the scattering multiplicity matrix cross sections - by performing a deep-copy of the provided ndarray. + by performing a deep-copy of the provided ndarray. Multiplicity, + in OpenMC parlance, is a factor used to account for the production + of neutrons introduced by scattering multiplication reactions, i.e., + (n,xn) events. In this sense, the multiplication matrix is simply + defined as the ratio of the nu-scatter and scatter matrices. + If the angular representation is "isotropic" the shape of + the input array must be the number of energy groups and the number + of energy groups. If the angular representation is "angle" then the + shape of the input array must be the number of polar angles, + number azimuthal angles, number of scattering orders, energy groups, + and energy groups. Parameters ---------- multiplicity : ndarrays - Array of group-wise cross sections to apply + Array of scattering multiplications to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # check we have a numpy list check_type('multiplicity', multiplicity, np.ndarray, expected_iter_type=Real, max_depth=len(multiplicity.shape)) @@ -626,18 +645,20 @@ class XSdata(object): @nu_fission.setter def nu_fission(self, nu_fission): """This method sets the nu_fission cross section by performing a - deep-copy of the provided ndarray. + deep-copy of the provided ndarray. If the angular + representation is "isotropic" the shape of the input array + must be the number of energy groups. If the angular + representation is "angle" then the shape of the input + array must be the number of polar angles, number azimuthal + angles and energy groups. Parameters ---------- nu_fission: ndarray Array of group-wise cross sections to apply - Raises - ------ - ValueError - When invalid parameters are passed. """ + # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. @@ -691,16 +712,10 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(total, (openmc.mgxs.TotalXS, - openmc.mgxs.TransportXS)): - msg = 'Method must be passed an openmc.mgxs.TotalXS or ' \ - 'openmc.mgxs.TransportXS object' - raise TypeError(msg) + + check_type('total', total, (openmc.mgxs.TotalXS, + openmc.mgxs.TransportXS)) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', total.energy_groups, [self.energy_groups]) @@ -715,7 +730,8 @@ class XSdata(object): msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_absorption_mgxs(self, absorption, nuclide='total', xs_type='macro'): + def set_absorption_mgxs(self, absorption, nuclide='total', + xs_type='macro'): """This method allows for an openmc.mgxs.AbsorptionXS to be used to set the absorption cross section for this XSdata object. @@ -731,14 +747,9 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(absorption, openmc.mgxs.AbsorptionXS): - msg = 'Method must be passed an openmc.mgxs.AbsorptionXS' - raise TypeError(msg) + + check_type('absorption', absorption, openmc.mgxs.AbsorptionXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', absorption.energy_groups, @@ -771,14 +782,9 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(fission, openmc.mgxs.FissionXS): - msg = 'Method must be passed an openmc.mgxs.FissionXS' - raise TypeError(msg) + + check_type('fission', fission, openmc.mgxs.FissionXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', fission.energy_groups, @@ -795,7 +801,8 @@ class XSdata(object): msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) - def set_nu_fission_mgxs(self, nu_fission, nuclide='total', xs_type='macro'): + def set_nu_fission_mgxs(self, nu_fission, nuclide='total', + xs_type='macro'): """This method allows for an openmc.mgxs.NuFissionXS to be used to set the nu-fission cross section for this XSdata object. @@ -811,17 +818,12 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ + # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. - if not isinstance(nu_fission, openmc.mgxs.NuFissionXS): - msg = 'Method must be passed an openmc.mgxs.NuFissionXS' - raise TypeError(msg) + check_type('nu_fission', nu_fission, openmc.mgxs.NuFissionXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', nu_fission.energy_groups, @@ -861,14 +863,9 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(k_fission, openmc.mgxs.KappaFissionXS): - msg = 'Method must be passed an openmc.mgxs.KappaFissionXS' - raise TypeError(msg) + + check_type('k_fission', k_fission, openmc.mgxs.KappaFissionXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', k_fission.energy_groups, @@ -900,20 +897,15 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ + if self._use_chi is not None: if not self._use_chi: msg = 'Providing chi when nu_fission already provided as a ' \ 'matrix!' raise ValueError(msg) - if not isinstance(chi, openmc.mgxs.Chi): - msg = 'Method must be passed an openmc.mgxs.Chi' - raise TypeError(msg) + check_type('chi', chi, openmc.mgxs.Chi) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', chi.energy_groups, [self.energy_groups]) @@ -949,14 +941,9 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): - msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' - raise TypeError(msg) + + check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', scatter.energy_groups, @@ -967,8 +954,9 @@ class XSdata(object): ['universe', 'cell', 'material']) if self._representation is 'isotropic': - self._scatter = scatter.get_xs(nuclides=nuclide, - xs_type=xs_type) + self._scatter = np.array([scatter.get_xs(nuclides=nuclide, + xs_type=xs_type)]) + elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -977,7 +965,11 @@ class XSdata(object): xs_type='macro'): """This method allows for an openmc.mgxs.NuScatterMatrixXS and openmc.mgxs.ScatterMatrixXS to be used to set the scattering - multiplicity for this XSdata object. + multiplicity for this XSdata object. Multiplicity, + in OpenMC parlance, is a factor used to account for the production + of neutrons introduced by scattering multiplication reactions, i.e., + (n,xn) events. In this sense, the multiplication matrix is simply + defined as the ratio of the nu-scatter and scatter matrices. Parameters ---------- @@ -994,17 +986,10 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. - Raises - ------ - ValueError - When invalid parameters are passed. """ - if not isinstance(nuscatter, openmc.mgxs.NuScatterMatrixXS): - msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' - raise TypeError(msg) - if not isinstance(scatter, openmc.mgxs.ScatterMatrixXS): - msg = 'Method must be passed an openmc.mgxs.ScatterMatrixXS' - raise TypeError(msg) + + check_type('nuscatter', nuscatter, openmc.mgxs.NuScatterMatrixXS) + check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS) # Make sure passed MGXS object contains correct group structure check_value('energy_groups', nuscatter.energy_groups, From 17f4927e8b010a8b59606d0050767de0306ad640 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Thu, 12 May 2016 16:32:40 -0400 Subject: [PATCH 119/147] Added new NuTransportXS class --- openmc/mgxs/mgxs.py | 72 ++++++++++++++++++++++++++++++++++++++++++--- 1 file changed, 68 insertions(+), 4 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index cc192855b..3194df2bc 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -22,6 +22,7 @@ if sys.version_info[0] >= 3: # Supported cross section types MGXS_TYPES = ['total', 'transport', + 'nu-transport', 'absorption', 'capture', 'fission', @@ -333,7 +334,7 @@ class MGXS(object): Parameters ---------- - mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'} + mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'} The type of multi-group cross section object to return domain : openmc.Material or openmc.Cell or openmc.Universe The domain for spatial homogenization @@ -362,6 +363,8 @@ class MGXS(object): mgxs = TotalXS(domain, domain_type, energy_groups) elif mgxs_type == 'transport': mgxs = TransportXS(domain, domain_type, energy_groups) + elif mgxs_type == 'nu-transport': + mgxs = NuTransportXS(domain, domain_type, energy_groups) elif mgxs_type == 'absorption': mgxs = AbsorptionXS(domain, domain_type, energy_groups) elif mgxs_type == 'capture': @@ -1526,13 +1529,29 @@ class TotalXS(MGXS): class TransportXS(MGXS): - """A transport-corrected total multi-group cross section.""" + """A transport-corrected total multi-group cross section. + + Attributes + ---------- + use_nu : bool + Whether or not to account for scattering multiplicity in the + correction. If False, a "scatter-1" score is used (default); + if True, a "nu-scatter-1" score is used. This should be + set to False if using a ScatterMatrixXS and True if using + a NuScatterMatrixXS to preserve neutron balance. + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): super(TransportXS, self).__init__(domain, domain_type, groups, by_nuclide, name) self._rxn_type = 'transport' + self._use_nu = False + + @property + def use_nu(self): + return self._use_nu @property def tallies(self): @@ -1548,9 +1567,14 @@ class TransportXS(MGXS): if self._tallies is None: # Create a list of scores for each Tally to be created - scores = ['flux', 'total', 'scatter-1'] + scores = ['flux', 'total'] + if self.use_nu: + scores.append('nu-scatter-1') + else: + scores.append('scatter-1') + estimator = 'analog' - keys = scores + keys = ['flux', 'total', 'scatter-1'] # Create the non-domain specific Filters for the Tallies group_edges = self.energy_groups.group_edges @@ -1574,6 +1598,46 @@ class TransportXS(MGXS): return self._rxn_rate_tally +class NuTransportXS(TransportXS): + """A transport-corrected total multi-group cross section which + accounts for neutron multiplicity in scattering reactions.""" + + def __init__(self, domain=None, domain_type=None, + groups=None, by_nuclide=False, name=''): + super(NuTransportXS, self).__init__(domain, domain_type, + groups, by_nuclide, name) + self._rxn_type = 'nu-transport' + + @property + def tallies(self): + """Construct the OpenMC tallies needed to compute this cross section. + + This method constructs three analog tallies to compute the 'flux', + 'total' and 'nu-scatter-1' reaction rates in the spatial domain and + energy groups of interest. + + """ + + # Instantiate tallies if they do not exist + if self._tallies is None: + + # Create a list of scores for each Tally to be created + scores = ['flux', 'total', 'nu-scatter-1'] + keys = ['flux', 'total', 'scatter-1'] + estimator = 'analog' + + # Create the non-domain specific Filters for the Tallies + group_edges = self.energy_groups.group_edges + energy_filter = openmc.Filter('energy', group_edges) + energyout_filter = openmc.Filter('energyout', group_edges) + filters = [[energy_filter], [energy_filter], [energyout_filter]] + + # Initialize the Tallies + self._create_tallies(scores, filters, keys, estimator) + + return self._tallies + + class AbsorptionXS(MGXS): """An absorption multi-group cross section.""" From 9e843de1bd7bc00ce3c5edd11bc5523761c8e385 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Thu, 12 May 2016 20:13:27 -0400 Subject: [PATCH 120/147] Partial refactor of MGXS subclasses --- openmc/mgxs/mgxs.py | 445 ++++++++++---------------------------------- 1 file changed, 95 insertions(+), 350 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 3194df2bc..89f12d5ed 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -215,10 +215,50 @@ class MGXS(object): @property def tallies(self): + """Construct the OpenMC tallies needed to compute the cross section.""" + + # Instantiate tallies if they do not exist + if self._tallies is None: + + # Initialize a collection of Tallies + self._tallies = OrderedDict() + + # Create a domain Filter object + domain_filter = openmc.Filter(self.domain_type, self.domain.id) + + # Create each Tally needed to compute the multi group cross section + for score, key, filters in zip(self.scores, self.keys, self.filters): + self.tallies[key] = openmc.Tally(name=self.name) + self.tallies[key].scores = [score] + self.tallies[key].estimator = self.estimator + self.tallies[key].filters = [domain_filter] + + # If a tally trigger was specified, add it to each tally + if self.tally_trigger: + trigger_clone = copy.deepcopy(self.tally_trigger) + trigger_clone.scores = [score] + self.tallies[key].triggers.append(trigger_clone) + + # Add non-domain specific Filters (e.g., 'energy') to the Tally + for add_filter in filters: + self.tallies[key].filters.append(add_filter) + + # If this is a by-nuclide cross-section, add nuclides to Tally + if self.by_nuclide and score != 'flux': + all_nuclides = self.get_all_nuclides() + for nuclide in all_nuclides: + self.tallies[key].nuclides.append(nuclide) + else: + self.tallies[key].nuclides.append('total') + return self._tallies @property def rxn_rate_tally(self): + if self._rxn_rate_tally is None: + self._rxn_rate_tally = self.tallies[self.rxn_type] + self._rxn_rate_tally.sparse = self.sparse + return self._rxn_rate_tally @property @@ -263,6 +303,24 @@ class MGXS(object): def derived(self): return self._derived + @property + def scores(self): + return ['flux', self.rxn_type] + + @property + def filters(self): + group_edges = self.energy_groups.group_edges + energy_filter = openmc.Filter('energy', group_edges) + return [[energy_filter] * len(self.scores)] + + @property + def tally_keys(self): + return self.scores + + @property + def estimator(self): + return 'tracklength' + @name.setter def name(self, name): cv.check_type('name', name, basestring) @@ -504,63 +562,6 @@ class MGXS(object): return densities - def _create_tallies(self, scores, all_filters, keys, estimator): - """Instantiates tallies needed to compute the multi-group cross section. - - This is a helper method for MGXS subclasses to create tallies - for input file generation. The tallies are stored in the tallies dict. - This method is called by each subclass' tallies property getter - which define the parameters given to this parent class method. - - Parameters - ---------- - scores : Iterable of str - Scores for each tally - all_filters : Iterable of tuple of openmc.Filter - Tuples of non-spatial domain filters for each tally - keys : Iterable of str - Key string used to store each tally in the tallies dictionary - estimator : {'analog', 'tracklength'} - Type of estimator to use for each tally - - """ - - cv.check_iterable_type('scores', scores, basestring) - cv.check_length('scores', scores, len(keys)) - cv.check_iterable_type('filters', all_filters, openmc.Filter, 1, 2) - cv.check_type('keys', keys, Iterable, basestring) - cv.check_value('estimator', estimator, ['analog', 'tracklength']) - - self._tallies = OrderedDict() - - # Create a domain Filter object - domain_filter = openmc.Filter(self.domain_type, self.domain.id) - - # Create each Tally needed to compute the multi group cross section - for score, key, filters in zip(scores, keys, all_filters): - self.tallies[key] = openmc.Tally(name=self.name) - self.tallies[key].scores = [score] - self.tallies[key].estimator = estimator - self.tallies[key].filters = [domain_filter] - - # If a tally trigger was specified, add it to each tally - if self.tally_trigger: - trigger_clone = copy.deepcopy(self.tally_trigger) - trigger_clone.scores = [score] - self.tallies[key].triggers.append(trigger_clone) - - # Add all non-domain specific Filters (e.g., 'energy') to the Tally - for add_filter in filters: - self.tallies[key].filters.append(add_filter) - - # If this is a by-nuclide cross-section, add all nuclides to Tally - if self.by_nuclide and score != 'flux': - all_nuclides = self.get_all_nuclides() - for nuclide in all_nuclides: - self.tallies[key].nuclides.append(nuclide) - else: - self.tallies[key].nuclides.append('total') - def _compute_xs(self): """Performs generic cleanup after a subclass' uses tally arithmetic to compute a multi-group cross section as a derived tally. @@ -1492,100 +1493,30 @@ class TotalXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'total' - @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two tracklength tallies to compute the 'flux' - and 'total' reaction rates in the spatial domain and energy groups - of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'total'] - estimator = 'tracklength' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies - - @property - def rxn_rate_tally(self): - if self._rxn_rate_tally is None : - self._rxn_rate_tally = self.tallies['total'] - self._rxn_rate_tally.sparse = self.sparse - return self._rxn_rate_tally - class TransportXS(MGXS): - """A transport-corrected total multi-group cross section. - - Attributes - ---------- - use_nu : bool - Whether or not to account for scattering multiplicity in the - correction. If False, a "scatter-1" score is used (default); - if True, a "nu-scatter-1" score is used. This should be - set to False if using a ScatterMatrixXS and True if using - a NuScatterMatrixXS to preserve neutron balance. - - """ + """A transport-corrected total multi-group cross section.""" def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): super(TransportXS, self).__init__(domain, domain_type, groups, by_nuclide, name) self._rxn_type = 'transport' - self._use_nu = False @property - def use_nu(self): - return self._use_nu + def scores(self): + return ['flux', 'total', 'scatter-1'] @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. + def filters(self): + group_edges = self.energy_groups.group_edges + energy_filter = openmc.Filter('energy', group_edges) + energyout_filter = openmc.Filter('energyout', group_edges) + return [[energy_filter], [energy_filter], [energyout_filter]] - This method constructs three analog tallies to compute the 'flux', - 'total' and 'scatter-1' reaction rates in the spatial domain and - energy groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'total'] - if self.use_nu: - scores.append('nu-scatter-1') - else: - scores.append('scatter-1') - - estimator = 'analog' - keys = ['flux', 'total', 'scatter-1'] - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - energyout_filter = openmc.Filter('energyout', group_edges) - filters = [[energy_filter], [energy_filter], [energyout_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + @property + def estimator(self): + return 'analog' @property def rxn_rate_tally(self): @@ -1609,33 +1540,12 @@ class NuTransportXS(TransportXS): self._rxn_type = 'nu-transport' @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. + def scores(self): + return ['flux', 'total', 'nu-scatter-1'] - This method constructs three analog tallies to compute the 'flux', - 'total' and 'nu-scatter-1' reaction rates in the spatial domain and - energy groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'total', 'nu-scatter-1'] - keys = ['flux', 'total', 'scatter-1'] - estimator = 'analog' - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - energyout_filter = openmc.Filter('energyout', group_edges) - filters = [[energy_filter], [energy_filter], [energyout_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + @property + def keys(self): + return ['flux', 'total', 'scatter-1'] class AbsorptionXS(MGXS): @@ -1647,41 +1557,6 @@ class AbsorptionXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'absorption' - @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two tracklength tallies to compute the 'flux' - and 'absorption' reaction rates in the spatial domain and energy - groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'absorption'] - estimator = 'tracklength' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies - - @property - def rxn_rate_tally(self): - if self._rxn_rate_tally is None: - self._rxn_rate_tally = self.tallies['absorption'] - self._rxn_rate_tally.sparse = self.sparse - return self._rxn_rate_tally - class CaptureXS(MGXS): """A capture multi-group cross section. @@ -1700,32 +1575,8 @@ class CaptureXS(MGXS): self._rxn_type = 'capture' @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two tracklength tallies to compute the 'flux' - and 'capture' reaction rates in the spatial domain and energy - groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'absorption', 'fission'] - estimator = 'tracklength' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter], [energy_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + def scores(self): + return ['flux', 'absorption', 'fission'] @property def rxn_rate_tally(self): @@ -1735,80 +1586,36 @@ class CaptureXS(MGXS): self._rxn_rate_tally.sparse = self.sparse return self._rxn_rate_tally -class FissionXSBase(MGXS): - """A fission production multi-group cross section base class - for NuFission and KappaFission - """ - # This is an abstract class which cannot be instantiated - __metaclass__ = abc.ABCMeta - - def __init__(self, rxn_type, domain=None, domain_type=None, - groups=None, by_nuclide=False, name=''): - super(FissionXSBase, self).__init__(domain, domain_type, - groups, by_nuclide, name) - self._rxn_type = rxn_type - - @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two tracklength tallies to compute the 'flux' - and 'rxn_type' reaction rates in the spatial domain and energy - groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', self._rxn_type] - estimator = 'tracklength' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies - - @property - def rxn_rate_tally(self): - if self._rxn_rate_tally is None: - self._rxn_rate_tally = self.tallies[self._rxn_type] - self._rxn_rate_tally.sparse = self.sparse - return self._rxn_rate_tally - - -class FissionXS(FissionXSBase): +class FissionXS(MGXS): """A fission multi-group cross section.""" def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): - super(FissionXS, self).__init__('fission', domain, domain_type, + super(FissionXS, self).__init__(domain, domain_type, groups, by_nuclide, name) + self._rxn_type = 'fission' -class NuFissionXS(FissionXSBase): +class NuFissionXS(MGXS): """A fission production multi-group cross section.""" def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): - super(NuFissionXS, self).__init__('nu-fission', domain, domain_type, + super(NuFissionXS, self).__init__(domain, domain_type, groups, by_nuclide, name) + self._rxn_type = 'nu-fission' -class KappaFissionXS(FissionXSBase): + +class KappaFissionXS(MGXS): """A recoverable fission energy production rate multi-group cross section.""" def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): - super(KappaFissionXS, self).__init__('kappa-fission', domain, domain_type, + super(KappaFissionXS, self).__init__(domain, domain_type, groups, by_nuclide, name) + self._rxn_type = 'kappa-fission' + class ScatterXS(MGXS): """A scatter multi-group cross section.""" @@ -1819,41 +1626,6 @@ class ScatterXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'scatter' - @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two tracklength tallies to compute the 'flux' - and 'scatter' reaction rates in the spatial domain and energy - groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'scatter'] - estimator = 'tracklength' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter]] - - # Intialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies - - @property - def rxn_rate_tally(self): - if self._rxn_rate_tally is None: - self._rxn_rate_tally = self.tallies['scatter'] - self._rxn_rate_tally.sparse = self.sparse - return self._rxn_rate_tally - class NuScatterXS(MGXS): """A nu-scatter multi-group cross section.""" @@ -1864,41 +1636,6 @@ class NuScatterXS(MGXS): groups, by_nuclide, name) self._rxn_type = 'nu-scatter' - @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. - - This method constructs two analog tallies to compute the 'flux' - and 'nu-scatter' reaction rates in the spatial domain and energy - groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['flux', 'nu-scatter'] - estimator = 'analog' - keys = scores - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - filters = [[energy_filter], [energy_filter]] - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies - - @property - def rxn_rate_tally(self): - if self._rxn_rate_tally is None: - self._rxn_rate_tally = self.tallies['nu-scatter'] - self._rxn_rate_tally.sparse = self.sparse - return self._rxn_rate_tally - class ScatterMatrixXS(MGXS): """A scattering matrix multi-group cross section for one or more Legendre @@ -1935,6 +1672,14 @@ class ScatterMatrixXS(MGXS): def legendre_order(self): return self._legendre_order + @property + def scores(self): + return ['flux', 'total', 'nu-scatter-1'] + + @property + def keys(self): + return ['flux', 'total', 'scatter-1'] + @property def tallies(self): """Construct the OpenMC tallies needed to compute this cross section. From 19feb55e6d5e8350398627f39fb55ee8e2e63011 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Thu, 12 May 2016 21:08:55 -0400 Subject: [PATCH 121/147] Major refactoring of MGXS subclasses to eliminate tallies properties --- .../pythonapi/examples/mgxs-part-i.ipynb | 75 +- .../pythonapi/examples/mgxs-part-ii.ipynb | 903 +++++++++--------- .../pythonapi/examples/mgxs-part-iii.ipynb | 280 +++--- openmc/mgxs/mgxs.py | 176 ++-- .../inputs_true.dat | 2 +- .../results_true.dat | 2 +- .../inputs_true.dat | 2 +- tests/test_mgxs_library_hdf5/inputs_true.dat | 2 +- tests/test_mgxs_library_hdf5/results_true.dat | 4 +- .../inputs_true.dat | 2 +- .../results_true.dat | 2 +- .../inputs_true.dat | 2 +- .../results_true.dat | 2 +- 13 files changed, 704 insertions(+), 750 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index e4c976718..2f2a80177 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -372,6 +372,7 @@ "\n", "* `TotalXS`\n", "* `TransportXS`\n", + "* `NuTransportXS`\n", "* `AbsorptionXS`\n", "* `CaptureXS`\n", "* `FissionXS`\n", @@ -409,7 +410,7 @@ }, { "cell_type": "code", - "execution_count": 13, + "execution_count": 26, "metadata": { "collapsed": false }, @@ -418,25 +419,27 @@ "data": { "text/plain": [ "OrderedDict([('flux', Tally\n", - " \tID =\t10000\n", - " \tName =\t\n", - " \tFilters =\t\n", - " \t\tcell\t[1]\n", - " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", - " \tNuclides =\ttotal \n", - " \tScores =\t['flux']\n", - " \tEstimator =\ttracklength), ('absorption', Tally\n", - " \tID =\t10001\n", - " \tName =\t\n", - " \tFilters =\t\n", - " \t\tcell\t[1]\n", - " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", - " \tNuclides =\ttotal \n", - " \tScores =\t['absorption']\n", - " \tEstimator =\ttracklength)])" + "\tID =\t10012\n", + "\tName =\t\n", + "\tFilters =\t\n", + " \t\tcell\t[1]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", + "\tNuclides =\ttotal \n", + "\tScores =\t[u'flux']\n", + "\tEstimator =\ttracklength\n", + "), ('absorption', Tally\n", + "\tID =\t10013\n", + "\tName =\t\n", + "\tFilters =\t\n", + " \t\tcell\t[1]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", + "\tNuclides =\ttotal \n", + "\tScores =\t[u'absorption']\n", + "\tEstimator =\ttracklength\n", + ")])" ] }, - "execution_count": 13, + "execution_count": 26, "metadata": {}, "output_type": "execute_result" } @@ -510,8 +513,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 502482dcf630ee6e290c15b8535e6e850a351c88\n", - " Date/Time: 2016-05-10 20:52:19\n", + " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", + " Date/Time: 2016-05-12 20:41:27\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -597,20 +600,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.3200E-01 seconds\n", - " Reading cross sections = 1.3300E-01 seconds\n", - " Total time in simulation = 2.3438E+01 seconds\n", - " Time in transport only = 2.3419E+01 seconds\n", - " Time in inactive batches = 2.9490E+00 seconds\n", - " Time in active batches = 2.0489E+01 seconds\n", - " Time synchronizing fission bank = 6.0000E-03 seconds\n", - " Sampling source sites = 3.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", + " Total time for initialization = 4.7500E-01 seconds\n", + " Reading cross sections = 9.7000E-02 seconds\n", + " Total time in simulation = 1.8074E+01 seconds\n", + " Time in transport only = 1.8055E+01 seconds\n", + " Time in inactive batches = 2.1180E+00 seconds\n", + " Time in active batches = 1.5956E+01 seconds\n", + " Time synchronizing fission bank = 4.0000E-03 seconds\n", + " Sampling source sites = 4.0000E-03 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Time accumulating tallies = 2.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.3985E+01 seconds\n", - " Calculation Rate (inactive) = 8477.45 neutrons/second\n", - " Calculation Rate (active) = 4880.67 neutrons/second\n", + " Total time elapsed = 1.8559E+01 seconds\n", + " Calculation Rate (inactive) = 11803.6 neutrons/second\n", + " Calculation Rate (active) = 6267.23 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1121,7 +1124,7 @@ " 6.250000e-07\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1\n", + " 1.0\n", " 0.007763\n", " \n", " \n", @@ -1131,7 +1134,7 @@ " 2.000000e+01\n", " total\n", " (((absorption / flux) / (total / flux)) + ((sc...\n", - " 1\n", + " 1.0\n", " 0.003739\n", " \n", " \n", @@ -1178,7 +1181,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython2", - "version": "2.7.11" + "version": "2.7.6" } }, "nbformat": 4, diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index 7b313da74..ca07519e5 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -445,8 +445,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 7b20f8ad4aa9e6f02f8b1d51e002f9f56ba7aa15\n", - " Date/Time: 2016-05-09 13:34:05\n", + " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", + " Date/Time: 2016-05-12 21:00:03\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -523,7 +523,7 @@ " 48/1 1.21610 1.22612 +/- 0.00251\n", " 49/1 1.22199 1.22602 +/- 0.00245\n", " 50/1 1.20860 1.22558 +/- 0.00243\n", - " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10050\n", + " Triggers unsatisfied, max unc./thresh. is 1.25496 for flux in tally 10051\n", " The estimated number of batches is 73\n", " Creating state point statepoint.050.h5...\n", " 51/1 1.21850 1.22541 +/- 0.00237\n", @@ -549,7 +549,7 @@ " 71/1 1.19720 1.22444 +/- 0.00195\n", " 72/1 1.23770 1.22465 +/- 0.00193\n", " 73/1 1.23894 1.22488 +/- 0.00191\n", - " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10050\n", + " Triggers unsatisfied, max unc./thresh. is 1.00243 for flux in tally 10051\n", " The estimated number of batches is 74\n", " 74/1 1.22437 1.22487 +/- 0.00188\n", " Triggers satisfied for batch 74\n", @@ -562,20 +562,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.8900E-01 seconds\n", - " Reading cross sections = 8.3000E-02 seconds\n", - " Total time in simulation = 2.2066E+02 seconds\n", - " Time in transport only = 2.2061E+02 seconds\n", - " Time in inactive batches = 1.5872E+01 seconds\n", - " Time in active batches = 2.0478E+02 seconds\n", - " Time synchronizing fission bank = 1.9000E-02 seconds\n", - " Sampling source sites = 1.2000E-02 seconds\n", - " SEND/RECV source sites = 6.0000E-03 seconds\n", - " Time accumulating tallies = 3.0000E-03 seconds\n", - " Total time for finalization = 1.1000E-02 seconds\n", - " Total time elapsed = 2.2111E+02 seconds\n", - " Calculation Rate (inactive) = 6300.40 neutrons/second\n", - " Calculation Rate (active) = 1953.28 neutrons/second\n", + " Total time for initialization = 4.1000E-01 seconds\n", + " Reading cross sections = 8.6000E-02 seconds\n", + " Total time in simulation = 2.2903E+02 seconds\n", + " Time in transport only = 2.2897E+02 seconds\n", + " Time in inactive batches = 1.4619E+01 seconds\n", + " Time in active batches = 2.1441E+02 seconds\n", + " Time synchronizing fission bank = 2.5000E-02 seconds\n", + " Sampling source sites = 1.6000E-02 seconds\n", + " SEND/RECV source sites = 8.0000E-03 seconds\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for finalization = 1.2000E-02 seconds\n", + " Total time elapsed = 2.2951E+02 seconds\n", + " Calculation Rate (inactive) = 6840.41 neutrons/second\n", + " Calculation Rate (active) = 1865.57 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -786,9 +786,10 @@ " group in\n", " group out\n", " nuclide\n", - " score\n", + " moment\n", " mean\n", " std. dev.\n", + " moment\n", " \n", " \n", " \n", @@ -798,9 +799,10 @@ " 1\n", " 1\n", " H-1\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.234115\n", " 0.003568\n", + " P0\n", " \n", " \n", " 127\n", @@ -808,9 +810,10 @@ " 1\n", " 1\n", " O-16\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 1.563707\n", " 0.005953\n", + " P0\n", " \n", " \n", " 124\n", @@ -818,9 +821,10 @@ " 1\n", " 2\n", " H-1\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 1.594129\n", " 0.002369\n", + " P0\n", " \n", " \n", " 125\n", @@ -828,9 +832,10 @@ " 1\n", " 2\n", " O-16\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.285761\n", " 0.001676\n", + " P0\n", " \n", " \n", " 122\n", @@ -838,9 +843,10 @@ " 1\n", " 3\n", " H-1\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.011089\n", " 0.000248\n", + " P0\n", " \n", " \n", " 123\n", @@ -848,9 +854,10 @@ " 1\n", " 3\n", " O-16\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.000000\n", " 0.000000\n", + " P0\n", " \n", " \n", " 120\n", @@ -858,9 +865,10 @@ " 1\n", " 4\n", " H-1\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.000000\n", " 0.000000\n", + " P0\n", " \n", " \n", " 121\n", @@ -868,9 +876,10 @@ " 1\n", " 4\n", " O-16\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.000000\n", " 0.000000\n", + " P0\n", " \n", " \n", " 118\n", @@ -878,9 +887,10 @@ " 1\n", " 5\n", " H-1\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.000000\n", " 0.000000\n", + " P0\n", " \n", " \n", " 119\n", @@ -888,38 +898,27 @@ " 1\n", " 5\n", " O-16\n", - " ((nu-scatter-0 - scatter-1) / flux)\n", + " P0\n", " 0.000000\n", " 0.000000\n", + " P0\n", " \n", " \n", "\n", "" ], "text/plain": [ - " cell group in group out nuclide score \\\n", - "126 10002 1 1 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", - "127 10002 1 1 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", - "124 10002 1 2 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", - "125 10002 1 2 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", - "122 10002 1 3 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", - "123 10002 1 3 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", - "120 10002 1 4 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", - "121 10002 1 4 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", - "118 10002 1 5 H-1 ((nu-scatter-0 - scatter-1) / flux) \n", - "119 10002 1 5 O-16 ((nu-scatter-0 - scatter-1) / flux) \n", - "\n", - " mean std. dev. \n", - "126 0.234115 0.003568 \n", - "127 1.563707 0.005953 \n", - "124 1.594129 0.002369 \n", - "125 0.285761 0.001676 \n", - "122 0.011089 0.000248 \n", - "123 0.000000 0.000000 \n", - "120 0.000000 0.000000 \n", - "121 0.000000 0.000000 \n", - "118 0.000000 0.000000 \n", - "119 0.000000 0.000000 " + " cell group in group out nuclide moment mean std. dev. moment\n", + "126 10002 1 1 H-1 P0 0.234115 0.003568 P0\n", + "127 10002 1 1 O-16 P0 1.563707 0.005953 P0\n", + "124 10002 1 2 H-1 P0 1.594129 0.002369 P0\n", + "125 10002 1 2 O-16 P0 0.285761 0.001676 P0\n", + "122 10002 1 3 H-1 P0 0.011089 0.000248 P0\n", + "123 10002 1 3 O-16 P0 0.000000 0.000000 P0\n", + "120 10002 1 4 H-1 P0 0.000000 0.000000 P0\n", + "121 10002 1 4 O-16 P0 0.000000 0.000000 P0\n", + "118 10002 1 5 H-1 P0 0.000000 0.000000 P0\n", + "119 10002 1 5 O-16 P0 0.000000 0.000000 P0" ] }, "execution_count": 19, @@ -1019,7 +1018,6 @@ " cell\n", " group in\n", " nuclide\n", - " score\n", " mean\n", " std. dev.\n", " \n", @@ -1030,7 +1028,6 @@ " 10000\n", " 1\n", " U-235\n", - " ((total - scatter-1) / flux)\n", " 20.611692\n", " 0.104237\n", " \n", @@ -1039,7 +1036,6 @@ " 10000\n", " 1\n", " U-238\n", - " ((total - scatter-1) / flux)\n", " 9.585358\n", " 0.013808\n", " \n", @@ -1048,7 +1044,6 @@ " 10000\n", " 1\n", " O-16\n", - " ((total - scatter-1) / flux)\n", " 3.164190\n", " 0.005049\n", " \n", @@ -1057,7 +1052,6 @@ " 10000\n", " 2\n", " U-235\n", - " ((total - scatter-1) / flux)\n", " 485.413426\n", " 0.996410\n", " \n", @@ -1066,7 +1060,6 @@ " 10000\n", " 2\n", " U-238\n", - " ((total - scatter-1) / flux)\n", " 11.190386\n", " 0.028731\n", " \n", @@ -1075,7 +1068,6 @@ " 10000\n", " 2\n", " O-16\n", - " ((total - scatter-1) / flux)\n", " 3.794859\n", " 0.011139\n", " \n", @@ -1084,13 +1076,13 @@ "" ], "text/plain": [ - " cell group in nuclide score mean std. dev.\n", - "3 10000 1 U-235 ((total - scatter-1) / flux) 2.06e+01 1.04e-01\n", - "4 10000 1 U-238 ((total - scatter-1) / flux) 9.59e+00 1.38e-02\n", - "5 10000 1 O-16 ((total - scatter-1) / flux) 3.16e+00 5.05e-03\n", - "0 10000 2 U-235 ((total - scatter-1) / flux) 4.85e+02 9.96e-01\n", - "1 10000 2 U-238 ((total - scatter-1) / flux) 1.12e+01 2.87e-02\n", - "2 10000 2 O-16 ((total - scatter-1) / flux) 3.79e+00 1.11e-02" + " cell group in nuclide mean std. dev.\n", + "3 10000 1 U-235 20.611692 0.104237\n", + "4 10000 1 U-238 9.585358 0.013808\n", + "5 10000 1 O-16 3.164190 0.005049\n", + "0 10000 2 U-235 485.413426 0.996410\n", + "1 10000 2 U-238 11.190386 0.028731\n", + "2 10000 2 O-16 3.794859 0.011139" ] }, "execution_count": 22, @@ -1202,161 +1194,161 @@ "[ NORMAL ] Iteration 5:\tk_eff = 0.625810\tres = 2.417E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.606678\tres = 2.675E-02\n", "[ NORMAL ] Iteration 7:\tk_eff = 0.587485\tres = 3.057E-02\n", - "[ NORMAL ] Iteration 8:\tk_eff = 0.569029\tres 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-255.0\n" + "openmoc keff = 1.220892\n", + "bias [pcm]: -258.1\n" ] } ], @@ -1467,235 +1459,235 @@ "[ NORMAL ] Computing the eigenvalue...\n", "[ NORMAL ] Iteration 0:\tk_eff = 0.495816\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.557477\tres = 5.042E-01\n", - "[ NORMAL ] Iteration 2:\tk_eff = 0.518301\tres = 1.244E-01\n", - "[ NORMAL ] Iteration 3:\tk_eff = 0.509212\tres = 7.027E-02\n", + "[ NORMAL ] Iteration 2:\tk_eff = 0.518300\tres = 1.244E-01\n", + "[ NORMAL ] Iteration 3:\tk_eff = 0.509211\tres = 7.027E-02\n", "[ NORMAL ] Iteration 4:\tk_eff = 0.496489\tres = 1.754E-02\n", "[ NORMAL ] Iteration 5:\tk_eff = 0.488581\tres = 2.498E-02\n", "[ NORMAL ] Iteration 6:\tk_eff = 0.482897\tres = 1.593E-02\n", "[ NORMAL ] Iteration 7:\tk_eff = 0.479775\tres = 1.163E-02\n", - "[ NORMAL ] Iteration 8:\tk_eff = 0.478835\tres = 6.464E-03\n", - "[ NORMAL ] Iteration 9:\tk_eff = 0.479872\tres = 1.960E-03\n", - "[ NORMAL ] Iteration 10:\tk_eff = 0.482685\tres = 2.166E-03\n", - "[ 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215:\tk_eff = 1.222989\tres = 1.816E-05\n", + "[ NORMAL ] Iteration 216:\tk_eff = 1.223009\tres = 1.746E-05\n", + "[ NORMAL ] Iteration 217:\tk_eff = 1.223029\tres = 1.680E-05\n", + "[ NORMAL ] Iteration 218:\tk_eff = 1.223048\tres = 1.615E-05\n", + "[ NORMAL ] Iteration 219:\tk_eff = 1.223067\tres = 1.554E-05\n", + "[ NORMAL ] Iteration 220:\tk_eff = 1.223084\tres = 1.494E-05\n", + "[ NORMAL ] Iteration 221:\tk_eff = 1.223101\tres = 1.437E-05\n", + "[ NORMAL ] Iteration 222:\tk_eff = 1.223117\tres = 1.382E-05\n", + "[ NORMAL ] Iteration 223:\tk_eff = 1.223133\tres = 1.329E-05\n", + "[ NORMAL ] Iteration 224:\tk_eff = 1.223148\tres = 1.279E-05\n", + "[ NORMAL ] Iteration 225:\tk_eff = 1.223162\tres = 1.230E-05\n", + "[ NORMAL ] Iteration 226:\tk_eff = 1.223176\tres = 1.183E-05\n", + "[ NORMAL ] Iteration 227:\tk_eff = 1.223190\tres = 1.137E-05\n", + "[ NORMAL ] Iteration 228:\tk_eff = 1.223203\tres = 1.094E-05\n", + "[ NORMAL ] Iteration 229:\tk_eff = 1.223215\tres = 1.052E-05\n", + "[ NORMAL ] Iteration 230:\tk_eff = 1.223227\tres = 1.012E-05\n" ] } ], @@ -1721,8 +1713,8 @@ "output_type": "stream", "text": [ "openmc keff = 1.223474\n", - "openmoc keff = 1.223258\n", - "bias [pcm]: -21.5\n" + "openmoc keff = 1.223227\n", + "bias [pcm]: -24.7\n" ] } ], @@ -1813,7 +1805,7 @@ "data": { "image/png": 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QJiJHAEOBeSJSCOyS3GKpXGezwaRJzc+lXLvWxpIlmb+bbaKXz6irs7XoeUol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\n+KP1PP8hsU6nNWku3KqsyVy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GugNni0h3YC/ge+9p2bHgi1I7oVMnz05tMxruRl5S4uHw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\nCqHJQSmlVAhNDkoppUL8Pzlt5uQccjZkAAAAAElFTkSuQmCC\n", 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1923,6 +1915,15 @@ "# Show the plot on screen\n", "plt.show()" ] + }, + { + "cell_type": "code", + "execution_count": null, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [] } ], "metadata": { diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index b807ab4a9..842c334a2 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -32,7 +32,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/wboyd/anaconda2/lib/python2.7/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", + "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", "because the backend has already been chosen;\n", "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", "or matplotlib.backends is imported for the first time.\n", @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -539,6 +539,7 @@ "\n", "* `TotalXS` (`\"total\"`)\n", "* `TransportXS` (`\"transport\"`)\n", + "* `NuTransportXS` (`\"nu-transport\"`)\n", "* `AbsorptionXS` (`\"absorption\"`)\n", "* `CaptureXS` (`\"capture\"`)\n", "* `FissionXS` (`\"fission\"`)\n", @@ -725,8 +726,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 502482dcf630ee6e290c15b8535e6e850a351c88\n", - " Date/Time: 2016-05-10 20:53:35\n", + " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", + " Date/Time: 2016-05-12 21:04:33\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -813,20 +814,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.8400E-01 seconds\n", - " Reading cross sections = 1.4100E-01 seconds\n", - " Total time in simulation = 7.7003E+01 seconds\n", - " Time in transport only = 7.6958E+01 seconds\n", - " Time in inactive batches = 6.4820E+00 seconds\n", - " Time in active batches = 7.0521E+01 seconds\n", - " Time synchronizing fission bank = 8.0000E-03 seconds\n", - " Sampling source sites = 6.0000E-03 seconds\n", + " Total time for initialization = 4.5500E-01 seconds\n", + " Reading cross sections = 1.1200E-01 seconds\n", + " Total time in simulation = 5.6386E+01 seconds\n", + " Time in transport only = 5.6351E+01 seconds\n", + " Time in inactive batches = 4.3700E+00 seconds\n", + " Time in active batches = 5.2016E+01 seconds\n", + " Time synchronizing fission bank = 5.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 6.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 7.7616E+01 seconds\n", - " Calculation Rate (inactive) = 3856.83 neutrons/second\n", - " Calculation Rate (active) = 1418.02 neutrons/second\n", + " Total time elapsed = 5.6857E+01 seconds\n", + " Calculation Rate (inactive) = 5720.82 neutrons/second\n", + " Calculation Rate (active) = 1922.49 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -952,8 +953,7 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/wboyd/Documents/NSE-CRPG-Codes/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", - " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n" + "/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/tallies.py:1988: RuntimeWarning: invalid value encountered in true_divide\n" ] }, { @@ -1301,122 +1301,122 @@ "[ NORMAL ] Computing the eigenvalue...\n", "[ NORMAL ] Iteration 0:\tk_eff = 0.854370\tres = 0.000E+00\n", "[ NORMAL ] Iteration 1:\tk_eff = 0.801922\tres = 1.521E-01\n", - "[ NORMAL ] Iteration 2:\tk_eff = 0.761746\tres = 6.349E-02\n", - "[ NORMAL ] Iteration 3:\tk_eff = 0.732367\tres = 5.029E-02\n", - "[ NORMAL ] Iteration 4:\tk_eff = 0.711075\tres = 3.869E-02\n", - "[ NORMAL ] Iteration 5:\tk_eff = 0.696557\tres = 2.912E-02\n", - "[ NORMAL ] Iteration 6:\tk_eff = 0.687673\tres = 2.044E-02\n", - "[ NORMAL ] Iteration 7:\tk_eff = 0.683470\tres = 1.277E-02\n", - "[ NORMAL ] Iteration 8:\tk_eff = 0.683129\tres = 6.141E-03\n", - "[ NORMAL ] Iteration 9:\tk_eff = 0.685949\tres = 7.889E-04\n", - "[ NORMAL ] Iteration 10:\tk_eff = 0.691329\tres = 4.181E-03\n", - "[ NORMAL ] Iteration 11:\tk_eff = 0.698755\tres = 7.875E-03\n", - "[ NORMAL ] Iteration 12:\tk_eff = 0.707786\tres = 1.077E-02\n", - "[ NORMAL ] Iteration 13:\tk_eff = 0.718050\tres = 1.295E-02\n", - "[ NORMAL ] Iteration 14:\tk_eff = 0.729230\tres = 1.452E-02\n", - "[ NORMAL ] Iteration 15:\tk_eff = 0.741058\tres = 1.559E-02\n", - "[ NORMAL ] Iteration 16:\tk_eff = 0.753310\tres = 1.624E-02\n", - "[ NORMAL ] Iteration 17:\tk_eff = 0.765800\tres = 1.655E-02\n", - "[ NORMAL ] Iteration 18:\tk_eff = 0.778371\tres = 1.660E-02\n", - "[ NORMAL ] Iteration 19:\tk_eff = 0.790897\tres = 1.643E-02\n", - "[ NORMAL ] Iteration 20:\tk_eff = 0.803273\tres = 1.611E-02\n", - "[ NORMAL ] Iteration 21:\tk_eff = 0.815415\tres = 1.566E-02\n", - "[ NORMAL ] Iteration 22:\tk_eff = 0.827256\tres = 1.513E-02\n", - "[ NORMAL ] Iteration 23:\tk_eff = 0.838747\tres = 1.453E-02\n", - "[ NORMAL ] Iteration 24:\tk_eff = 0.849847\tres = 1.390E-02\n", - "[ NORMAL ] Iteration 25:\tk_eff = 0.860527\tres = 1.324E-02\n", - "[ NORMAL ] Iteration 26:\tk_eff = 0.870770\tres = 1.258E-02\n", - "[ NORMAL ] Iteration 27:\tk_eff = 0.880562\tres = 1.191E-02\n", - "[ NORMAL ] Iteration 28:\tk_eff = 0.889897\tres = 1.125E-02\n", - "[ NORMAL ] Iteration 29:\tk_eff = 0.898776\tres = 1.061E-02\n", - "[ NORMAL ] Iteration 30:\tk_eff = 0.907202\tres = 9.986E-03\n", - "[ NORMAL ] Iteration 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108:\tk_eff = 1.028367\tres = 2.175E-05\n", + "[ NORMAL ] Iteration 109:\tk_eff = 1.028386\tres = 1.999E-05\n", + "[ NORMAL ] Iteration 110:\tk_eff = 1.028403\tres = 1.837E-05\n", + "[ NORMAL ] Iteration 111:\tk_eff = 1.028419\tres = 1.688E-05\n", + "[ NORMAL ] Iteration 112:\tk_eff = 1.028434\tres = 1.551E-05\n", + "[ NORMAL ] Iteration 113:\tk_eff = 1.028447\tres = 1.426E-05\n", + "[ NORMAL ] Iteration 114:\tk_eff = 1.028460\tres = 1.310E-05\n", + "[ NORMAL ] Iteration 115:\tk_eff = 1.028471\tres = 1.204E-05\n", + "[ NORMAL ] Iteration 116:\tk_eff = 1.028481\tres = 1.106E-05\n", + "[ NORMAL ] Iteration 117:\tk_eff = 1.028491\tres = 1.016E-05\n" ] } ], @@ -1449,8 +1449,8 @@ "output_type": "stream", "text": [ "openmc keff = 1.028263\n", - "openmoc keff = 1.028538\n", - "bias [pcm]: 27.5\n" + "openmoc keff = 1.028491\n", + "bias [pcm]: 22.8\n" ] } ], @@ -1558,7 +1558,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 43, @@ -1567,9 +1567,9 @@ }, { "data": { - "image/png": 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LwOXDO9vT701ffYEZcxn+ZcZs6GBPxNqmg32+8nV3hzgXM8Tk3IcHB7c162x7tuzzNs8x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\nmTHjJtxhxty74VE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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1609,7 +1609,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython2", - "version": "2.7.11" + "version": "2.7.6" } }, "nbformat": 4, diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 89f12d5ed..5b49005ec 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -227,29 +227,30 @@ class MGXS(object): domain_filter = openmc.Filter(self.domain_type, self.domain.id) # Create each Tally needed to compute the multi group cross section - for score, key, filters in zip(self.scores, self.keys, self.filters): - self.tallies[key] = openmc.Tally(name=self.name) - self.tallies[key].scores = [score] - self.tallies[key].estimator = self.estimator - self.tallies[key].filters = [domain_filter] + tally_metadata = zip(self.scores, self.tally_keys, self.filters) + for score, key, filters in tally_metadata: + self._tallies[key] = openmc.Tally(name=self.name) + self._tallies[key].scores = [score] + self._tallies[key].estimator = self.estimator + self._tallies[key].filters = [domain_filter] # If a tally trigger was specified, add it to each tally if self.tally_trigger: trigger_clone = copy.deepcopy(self.tally_trigger) trigger_clone.scores = [score] - self.tallies[key].triggers.append(trigger_clone) + self._tallies[key].triggers.append(trigger_clone) # Add non-domain specific Filters (e.g., 'energy') to the Tally for add_filter in filters: - self.tallies[key].filters.append(add_filter) + self._tallies[key].filters.append(add_filter) # If this is a by-nuclide cross-section, add nuclides to Tally if self.by_nuclide and score != 'flux': all_nuclides = self.get_all_nuclides() for nuclide in all_nuclides: - self.tallies[key].nuclides.append(nuclide) + self._tallies[key].nuclides.append(nuclide) else: - self.tallies[key].nuclides.append('total') + self._tallies[key].nuclides.append('total') return self._tallies @@ -311,7 +312,7 @@ class MGXS(object): def filters(self): group_edges = self.energy_groups.group_edges energy_filter = openmc.Filter('energy', group_edges) - return [[energy_filter] * len(self.scores)] + return [[energy_filter]] * len(self.scores) @property def tally_keys(self): @@ -1544,7 +1545,7 @@ class NuTransportXS(TransportXS): return ['flux', 'total', 'nu-scatter-1'] @property - def keys(self): + def tally_keys(self): return ['flux', 'total', 'scatter-1'] @@ -1674,50 +1675,38 @@ class ScatterMatrixXS(MGXS): @property def scores(self): - return ['flux', 'total', 'nu-scatter-1'] + scores = ['flux'] + + for moment in range(self.legendre_order+1): + scores.append('scatter-{}'.format(moment)) + + if self.correction == 'P0' and self.legendre_order == 0: + scores.append('scatter-1') + + return scores @property - def keys(self): - return ['flux', 'total', 'scatter-1'] + def filters(self): + group_edges = self.energy_groups.group_edges + energy = openmc.Filter('energy', group_edges) + energyout = openmc.Filter('energyout', group_edges) + filters = [[energy]] + + for moment in range(self.legendre_order+1): + filters.append([energy, energyout]) + + if self.correction == 'P0' and self.legendre_order == 0: + filters.append([energyout]) + + return filters @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. + def tally_keys(self): + return ['flux', 'scatter-0', 'scatter-1'] - This method constructs three analog tallies to compute the 'flux' - and Legendre scattering moment reaction rates in the spatial domain and - energy groups of interest. - - """ - - # Instantiate tallies if they do not exist - if self._tallies is None: - - group_edges = self.energy_groups.group_edges - energy = openmc.Filter('energy', group_edges) - energyout = openmc.Filter('energyout', group_edges) - - # Create lists of scores, filters for each Tally to be created - scores = ['flux'] - filters = [[energy]] - - # Create separate tallies for each moment - for moment in range(self.legendre_order+1): - scores.append('scatter-{}'.format(moment)) - filters.append([energy, energyout]) - - # Append to the lists for the P0 approximation if needed - if self.correction == 'P0' and self.legendre_order == 0: - scores.append('scatter-1') - filters.append([energyout]) - - estimator = 'analog' - keys = scores - - # Initialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + @property + def estimator(self): + return 'analog' @property def rxn_rate_tally(self): @@ -1727,7 +1716,7 @@ class ScatterMatrixXS(MGXS): # If using P0 correction subtract scatter-1 from the diagonal if self.correction == 'P0' and self.legendre_order == 0: scatter_p1 = self.tallies['scatter-1'] - scatter_p1 = scatter_p1.get_slice(scores=['scatter-1']) + scatter_p1 = scatter_p1.get_slice(scores=[self.scores[-1]]) energy_filter = self.tallies['scatter-0'].find_filter('energy') energy_filter = copy.deepcopy(energy_filter) scatter_p1 = scatter_p1.diagonalize_filter(energy_filter) @@ -1737,8 +1726,7 @@ class ScatterMatrixXS(MGXS): else: rxn_rate_tally = self.tallies['scatter-0'] for moment in range(1, self.legendre_order+1): - scatter_key = 'scatter-{}'.format(moment) - scatter_pn = self.tallies[scatter_key] + scatter_pn = self.tallies['scatter-{}'.format(moment)] rxn_rate_tally = rxn_rate_tally.merge(scatter_pn) self._rxn_rate_tally = rxn_rate_tally @@ -2188,45 +2176,16 @@ class NuScatterMatrixXS(ScatterMatrixXS): self._rxn_type = 'nu-scatter matrix' @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. + def scores(self): + scores = ['flux'] - This method constructs three analog tallies to compute the 'flux', - 'nu-scatter' and 'scatter-P1' reaction rates in the spatial domain and - energy groups of interest. + for moment in range(self.legendre_order+1): + scores.append('nu-scatter-{}'.format(moment)) - """ + if self.correction == 'P0' and self.legendre_order == 0: + scores.append('nu-scatter-1') - # Instantiate tallies if they do not exist - if self._tallies is None: - - group_edges = self.energy_groups.group_edges - energy = openmc.Filter('energy', group_edges) - energyout = openmc.Filter('energyout', group_edges) - - # Create lists of scores, filters for each Tally to be created - scores = ['flux'] - filters = [[energy]] - keys = ['flux'] - - # Create separate tallies for each moment - for moment in range(self.legendre_order+1): - scores.append('nu-scatter-{}'.format(moment)) - filters.append([energy, energyout]) - keys.append('scatter-{}'.format(moment)) - - # Append to the lists for the P0 approximation if needed - if self.correction == 'P0' and self.legendre_order == 0: - scores.append('scatter-1') - filters.append([energyout]) - keys.append('scatter-1') - - estimator = 'analog' - - # Intialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + return scores class Chi(MGXS): @@ -2238,33 +2197,24 @@ class Chi(MGXS): self._rxn_type = 'chi' @property - def tallies(self): - """Construct the OpenMC tallies needed to compute this cross section. + def scores(self): + return ['nu-fission', 'nu-fission'] - This method constructs two analog tallies to compute 'nu-fission' - reaction rates with 'energy' and 'energyout' filters in the spatial - domain and energy groups of interest. + @property + def filters(self): + # Create the non-domain specific Filters for the Tallies + group_edges = self.energy_groups.group_edges + energyout = openmc.Filter('energyout', group_edges) + energyin = openmc.Filter('energy', [group_edges[0], group_edges[-1]]) + return [[energyin], [energyout]] - """ + @property + def tally_keys(self): + return ['nu-fission-in', 'nu-fission-out'] - # Instantiate tallies if they do not exist - if self._tallies is None: - - # Create a list of scores for each Tally to be created - scores = ['nu-fission', 'nu-fission'] - estimator = 'analog' - keys = ['nu-fission-in', 'nu-fission-out'] - - # Create the non-domain specific Filters for the Tallies - group_edges = self.energy_groups.group_edges - energyout = openmc.Filter('energyout', group_edges) - energyin = openmc.Filter('energy', [group_edges[0], group_edges[-1]]) - filters = [[energyin], [energyout]] - - # Intialize the Tallies - self._create_tallies(scores, filters, keys, estimator) - - return self._tallies + @property + def estimator(self): + return 'analog' @property def rxn_rate_tally(self): diff --git a/tests/test_mgxs_library_condense/inputs_true.dat b/tests/test_mgxs_library_condense/inputs_true.dat index 708ec114e..064981fa9 100644 --- a/tests/test_mgxs_library_condense/inputs_true.dat +++ b/tests/test_mgxs_library_condense/inputs_true.dat @@ -1 +1 @@ -e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file +ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 5f1d886b0..89e4dbb3e 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,7 +1,7 @@ material group in nuclide mean std. dev. 0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. 0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev. moment -0 1 1 1 total P0 0.345643 0.021487 P0 material group out nuclide mean std. dev. +0 1 1 1 total P0 0.345503 0.021465 P0 material group out nuclide mean std. dev. 0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. 0 2 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment diff --git a/tests/test_mgxs_library_distribcell/inputs_true.dat b/tests/test_mgxs_library_distribcell/inputs_true.dat index 4ab730274..5ffea7f8f 100644 --- a/tests/test_mgxs_library_distribcell/inputs_true.dat +++ b/tests/test_mgxs_library_distribcell/inputs_true.dat @@ -1 +1 @@ -aadb1e94492741c091bff4b5e17634ee327c718fc9fd1f27aa22fe8406fb70f732750dfdceb30eb40b5e4f406061bea6bd5235ba613c3c81009f5857a9051728 \ No newline at end of file +c46381a2d86bd849ca20dc64022ffcf836ba0f236f392bba6335c42559df61d14d09a616bc3a9590d954a5bf099610eb071982296b75b10d1c168cc3e343d383 \ No newline at end of file diff --git a/tests/test_mgxs_library_hdf5/inputs_true.dat b/tests/test_mgxs_library_hdf5/inputs_true.dat index 708ec114e..064981fa9 100644 --- a/tests/test_mgxs_library_hdf5/inputs_true.dat +++ b/tests/test_mgxs_library_hdf5/inputs_true.dat @@ -1 +1 @@ -e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file +ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file diff --git a/tests/test_mgxs_library_hdf5/results_true.dat b/tests/test_mgxs_library_hdf5/results_true.dat index e19b9ffa5..93aceba7d 100644 --- a/tests/test_mgxs_library_hdf5/results_true.dat +++ b/tests/test_mgxs_library_hdf5/results_true.dat @@ -5,9 +5,9 @@ domain=1 type=nu-fission [ 0.02178897 0.71407658] [ 0.00118187 0.04055185] domain=1 type=nu-scatter matrix -[[ 0.3373971 0.00155945] +[[ 0.33724504 0.00155945] [ 0. 0.42205129]] -[[ 0.02303884 0.00051015] +[[ 0.02301463 0.00051015] [ 0. 0.02161702]] domain=1 type=chi [ 1. 0.] diff --git a/tests/test_mgxs_library_no_nuclides/inputs_true.dat b/tests/test_mgxs_library_no_nuclides/inputs_true.dat index 708ec114e..064981fa9 100644 --- a/tests/test_mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_no_nuclides/inputs_true.dat @@ -1 +1 @@ -e3834da92fc6ae57ce109621e3f692a186a03820b61332fa9ed898bc07fb8a63484ace095713d5b88196b1d2f1430d2e7b27a505944c7c3027f6365801f58146 \ No newline at end of file +ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 4e6d88208..0ad8e04aa 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -3,7 +3,7 @@ 0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. 1 1 1 total 0.021789 0.001182 0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean std. dev. moment -3 1 1 1 total P0 0.337397 0.023039 P0 +3 1 1 1 total P0 0.337245 0.023015 P0 2 1 1 2 total P0 0.001559 0.000510 P0 1 1 2 1 total P0 0.000000 0.000000 P0 0 1 2 2 total P0 0.422051 0.021617 P0 material group out nuclide mean std. dev. diff --git a/tests/test_mgxs_library_nuclides/inputs_true.dat b/tests/test_mgxs_library_nuclides/inputs_true.dat index 5b7a83037..d2c11978a 100644 --- a/tests/test_mgxs_library_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_nuclides/inputs_true.dat @@ -1 +1 @@ -f1c203fb7f0b141ee608d7bb9223aa5f7ab84966b6a80525879df730d19179f6c6a1a4bc7038d84e6b366b360f43a1ca17a0af8d02f96eb23e53b93a2445380e \ No newline at end of file +f4abbd7867b0f0d2d9d93ed089c95904541f970522e1ef3a843373b60094ef4571a64a7b5f68efe9e51fd49754bc9e20a3bcc85c0bde3a8224608f8b97c01b85 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index ff34c9fff..9cef6fdd8 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -138,7 +138,7 @@ 102 1 1 1 U-234 P0 0.000000 0.000000 P0 103 1 1 1 U-235 P0 0.003226 0.001139 P0 104 1 1 1 U-236 P0 0.001697 0.000923 P0 -105 1 1 1 U-238 P0 0.194620 0.013297 P0 +105 1 1 1 U-238 P0 0.194468 0.013279 P0 106 1 1 1 Np-237 P0 0.000000 0.000000 P0 107 1 1 1 Pu-238 P0 0.000000 0.000000 P0 108 1 1 1 Pu-239 P0 0.001005 0.000477 P0 From e9fc744ba597a28d72dcbe204f60167e85eaa3c8 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Thu, 12 May 2016 21:34:03 -0400 Subject: [PATCH 122/147] Updated example notebook and changed default value of return_names in write_mg_library to False and updated the docstring accordingly. --- .../pythonapi/examples/mgxs-part-iv.ipynb | 1423 ++++++++++++----- openmc/mgxs/library.py | 4 +- 2 files changed, 997 insertions(+), 430 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index bc85af5c2..823d67ae1 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -6,10 +6,10 @@ "source": [ "This Notebook illustrates the use of the openmc.mgxs.Library class specifically for application in OpenMC's multi-group mode. This example notebook follows the same process as was done in MGXS Part III, but instead uses OpenMC as the multi-group solver. This Notebook illustrates the following features:\n", "\n", - " Calculation of multi-group cross sections for a fuel assembly\n", - " Automated creation, manipulation and storage of MGXS with openmc.mgxs.Library\n", - " Validation of multi-group cross sections with OpenMC\n", - " Steady-state pin-by-pin fission rates comparison between Continuous-Energy mode and Multi-Group OpenMC.\n", + " - Calculation of multi-group cross sections for a fuel assembly\n", + " - Automated creation, manipulation and storage of MGXS with openmc.mgxs.Library\n", + " - Validation of multi-group cross sections with OpenMC\n", + " - Steady-state pin-by-pin fission rates comparison between Continuous-Energy mode and Multi-Group OpenMC.\n", "\n", "Note: This Notebook illustrates the use of Pandas DataFrames to containerize multi-group cross section data. We recommend using Pandas >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of Pandas.\n" ] @@ -170,22 +170,22 @@ "outputs": [], "source": [ "# Create a Universe to encapsulate a fuel pin\n", - "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin')\n", + "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin', universe_id=10)\n", "\n", "# Create fuel Cell\n", - "fuel_cell = openmc.Cell(name='1.6% Fuel')\n", + "fuel_cell = openmc.Cell(name='1.6% Fuel', cell_id=1)\n", "fuel_cell.fill = fuel\n", "fuel_cell.region = -fuel_outer_radius\n", "fuel_pin_universe.add_cell(fuel_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='1.6% Clad')\n", + "clad_cell = openmc.Cell(name='1.6% Clad', cell_id=2)\n", "clad_cell.fill = zircaloy\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "fuel_pin_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='1.6% Moderator')\n", + "moderator_cell = openmc.Cell(name='1.6% Moderator', cell_id=3)\n", "moderator_cell.fill = water\n", "moderator_cell.region = +clad_outer_radius\n", "fuel_pin_universe.add_cell(moderator_cell)" @@ -207,22 +207,22 @@ "outputs": [], "source": [ "# Create a Universe to encapsulate a control rod guide tube\n", - "guide_tube_universe = openmc.Universe(name='Guide Tube')\n", + "guide_tube_universe = openmc.Universe(name='Guide Tube', universe_id=20)\n", "\n", "# Create guide tube Cell\n", - "guide_tube_cell = openmc.Cell(name='Guide Tube Water')\n", + "guide_tube_cell = openmc.Cell(name='Guide Tube Water', cell_id=4)\n", "guide_tube_cell.fill = water\n", "guide_tube_cell.region = -fuel_outer_radius\n", "guide_tube_universe.add_cell(guide_tube_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='Guide Clad')\n", + "clad_cell = openmc.Cell(name='Guide Clad', cell_id=5)\n", "clad_cell.fill = zircaloy\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "guide_tube_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='Guide Tube Moderator')\n", + "moderator_cell = openmc.Cell(name='Guide Tube Moderator', cell_id=6)\n", "moderator_cell.fill = water\n", "moderator_cell.region = +clad_outer_radius\n", "guide_tube_universe.add_cell(moderator_cell)" @@ -239,12 +239,12 @@ "cell_type": "code", "execution_count": 8, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ "# Create fuel assembly Lattice\n", - "assembly = openmc.RectLattice(name='1.6% Fuel Assembly')\n", + "assembly = openmc.RectLattice(name='1.6% Fuel Assembly', lattice_id=100)\n", "assembly.dimension = (17, 17)\n", "assembly.pitch = (1.26, 1.26)\n", "assembly.lower_left = [-1.26 * 17. / 2.0] * 2" @@ -298,7 +298,7 @@ "outputs": [], "source": [ "# Create root Cell\n", - "root_cell = openmc.Cell(name='root cell')\n", + "root_cell = openmc.Cell(name='root cell', cell_id=0)\n", "root_cell.fill = assembly\n", "\n", "# Add boundary planes\n", @@ -347,7 +347,7 @@ "outputs": [], "source": [ "# OpenMC simulation parameters\n", - "batches = 200\n", + "batches = 500\n", "inactive = 10\n", "particles = 5000\n", "\n", @@ -434,7 +434,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -554,7 +554,7 @@ "cell_type": "code", "execution_count": 20, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ @@ -566,12 +566,31 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Lastly, we use the `Library` to construct the tallies needed to compute all of the requested multi-group cross sections in each domain and nuclide." + "Now that the `Library` has been setup, lets make sure it contains the types of cross sections which meet the needs of OpenMC's multi-group solver. Note that this step is done automatically when writing the Multi-Group Library file later in the process (as part of the `mgxs_lib.write_mg_library()`), but it is a good practice to also run this before spending all the time running OpenMC to generate the cross sections." ] }, { "cell_type": "code", "execution_count": 21, + "metadata": { + "collapsed": false + }, + "outputs": [], + "source": [ + "# Check the library - if no errors are raised, then the library is satisfactory.\n", + "mgxs_lib.check_library_for_openmc_mgxs()" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Lastly, we use the `Library` to construct the tallies needed to compute all of the requested multi-group cross sections in each domain and nuclide." + ] + }, + { + "cell_type": "code", + "execution_count": 22, "metadata": { "collapsed": true }, @@ -592,7 +611,7 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 23, "metadata": { "collapsed": true }, @@ -612,7 +631,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 24, "metadata": { "collapsed": true }, @@ -640,7 +659,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 25, "metadata": { "collapsed": true }, @@ -652,7 +671,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 26, "metadata": { "collapsed": false }, @@ -677,8 +696,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 179e9ab147e505563d118ed58096b3d225160ffa\n", - " Date/Time: 2016-05-07 14:22:04\n", + " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", + " Date/Time: 2016-05-12 21:15:02\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -906,7 +925,307 @@ " 198/1 1.01366 1.02596 +/- 0.00130\n", " 199/1 1.04471 1.02605 +/- 0.00130\n", " 200/1 1.02416 1.02604 +/- 0.00129\n", - " Creating state point statepoint.200.h5...\n", + " 201/1 1.01172 1.02597 +/- 0.00129\n", + " 202/1 1.01683 1.02592 +/- 0.00128\n", + " 203/1 1.01341 1.02586 +/- 0.00128\n", + " 204/1 1.01507 1.02580 +/- 0.00127\n", + " 205/1 1.02540 1.02580 +/- 0.00127\n", + " 206/1 1.00310 1.02568 +/- 0.00127\n", + " 207/1 1.02822 1.02570 +/- 0.00126\n", + " 208/1 1.01023 1.02562 +/- 0.00126\n", + " 209/1 1.04603 1.02572 +/- 0.00125\n", + " 210/1 1.00775 1.02563 +/- 0.00125\n", + " 211/1 1.01706 1.02559 +/- 0.00125\n", + " 212/1 0.99434 1.02543 +/- 0.00125\n", + " 213/1 1.03346 1.02547 +/- 0.00124\n", + " 214/1 1.05322 1.02561 +/- 0.00124\n", + " 215/1 1.03057 1.02563 +/- 0.00124\n", + " 216/1 1.00976 1.02556 +/- 0.00123\n", + " 217/1 1.02760 1.02557 +/- 0.00123\n", + " 218/1 1.01259 1.02550 +/- 0.00122\n", + " 219/1 1.02829 1.02552 +/- 0.00122\n", + " 220/1 1.02228 1.02550 +/- 0.00121\n", + " 221/1 1.06679 1.02570 +/- 0.00122\n", + " 222/1 1.03417 1.02574 +/- 0.00122\n", + " 223/1 1.04239 1.02582 +/- 0.00121\n", + " 224/1 1.02062 1.02579 +/- 0.00121\n", + " 225/1 1.00331 1.02569 +/- 0.00121\n", + " 226/1 1.00131 1.02557 +/- 0.00121\n", + " 227/1 1.01768 1.02554 +/- 0.00120\n", + " 228/1 1.00813 1.02546 +/- 0.00120\n", + " 229/1 1.05320 1.02558 +/- 0.00120\n", + " 230/1 1.03472 1.02563 +/- 0.00120\n", + " 231/1 1.01426 1.02557 +/- 0.00119\n", + " 232/1 1.00782 1.02549 +/- 0.00119\n", + " 233/1 1.02813 1.02551 +/- 0.00118\n", + " 234/1 1.01184 1.02545 +/- 0.00118\n", + " 235/1 1.02156 1.02543 +/- 0.00118\n", + " 236/1 0.99029 1.02527 +/- 0.00118\n", + " 237/1 1.04196 1.02535 +/- 0.00118\n", + " 238/1 1.01594 1.02531 +/- 0.00117\n", + " 239/1 1.02732 1.02531 +/- 0.00117\n", + " 240/1 0.98987 1.02516 +/- 0.00117\n", + " 241/1 1.03388 1.02520 +/- 0.00117\n", + " 242/1 1.01319 1.02515 +/- 0.00116\n", + " 243/1 1.02870 1.02516 +/- 0.00116\n", + " 244/1 1.01943 1.02514 +/- 0.00115\n", + " 245/1 1.04463 1.02522 +/- 0.00115\n", + " 246/1 1.03551 1.02526 +/- 0.00115\n", + " 247/1 1.00436 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1.02633 1.02506 +/- 0.00108\n", + " 272/1 1.04811 1.02514 +/- 0.00108\n", + " 273/1 1.02851 1.02516 +/- 0.00107\n", + " 274/1 1.01270 1.02511 +/- 0.00107\n", + " 275/1 1.06222 1.02525 +/- 0.00107\n", + " 276/1 1.02778 1.02526 +/- 0.00107\n", + " 277/1 1.02601 1.02526 +/- 0.00107\n", + " 278/1 1.02356 1.02526 +/- 0.00106\n", + " 279/1 1.00792 1.02519 +/- 0.00106\n", + " 280/1 1.02331 1.02518 +/- 0.00106\n", + " 281/1 1.00985 1.02513 +/- 0.00105\n", + " 282/1 1.02035 1.02511 +/- 0.00105\n", + " 283/1 0.98181 1.02495 +/- 0.00106\n", + " 284/1 1.01829 1.02493 +/- 0.00106\n", + " 285/1 1.02929 1.02494 +/- 0.00105\n", + " 286/1 1.03524 1.02498 +/- 0.00105\n", + " 287/1 1.01212 1.02493 +/- 0.00105\n", + " 288/1 1.03584 1.02497 +/- 0.00104\n", + " 289/1 1.02961 1.02499 +/- 0.00104\n", + " 290/1 0.99692 1.02489 +/- 0.00104\n", + " 291/1 1.03966 1.02494 +/- 0.00104\n", + " 292/1 1.00965 1.02489 +/- 0.00104\n", + " 293/1 1.02601 1.02489 +/- 0.00103\n", + " 294/1 1.03224 1.02492 +/- 0.00103\n", + 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0.00088\n", + " 414/1 1.04183 1.02482 +/- 0.00088\n", + " 415/1 1.02279 1.02481 +/- 0.00088\n", + " 416/1 1.04197 1.02485 +/- 0.00088\n", + " 417/1 1.04617 1.02491 +/- 0.00088\n", + " 418/1 1.01311 1.02488 +/- 0.00088\n", + " 419/1 1.03904 1.02491 +/- 0.00087\n", + " 420/1 1.00458 1.02486 +/- 0.00087\n", + " 421/1 0.98580 1.02477 +/- 0.00088\n", + " 422/1 1.01850 1.02475 +/- 0.00087\n", + " 423/1 1.03739 1.02478 +/- 0.00087\n", + " 424/1 1.02716 1.02479 +/- 0.00087\n", + " 425/1 1.00711 1.02475 +/- 0.00087\n", + " 426/1 1.01008 1.02471 +/- 0.00087\n", + " 427/1 1.03332 1.02473 +/- 0.00087\n", + " 428/1 1.00501 1.02468 +/- 0.00087\n", + " 429/1 1.04549 1.02473 +/- 0.00086\n", + " 430/1 1.00582 1.02469 +/- 0.00086\n", + " 431/1 1.00586 1.02464 +/- 0.00086\n", + " 432/1 1.00082 1.02459 +/- 0.00086\n", + " 433/1 1.00835 1.02455 +/- 0.00086\n", + " 434/1 1.03965 1.02458 +/- 0.00086\n", + " 435/1 1.02385 1.02458 +/- 0.00086\n", + " 436/1 1.01440 1.02456 +/- 0.00086\n", + " 437/1 1.03127 1.02458 +/- 0.00085\n", + " 438/1 1.02961 1.02459 +/- 0.00085\n", + " 439/1 0.99584 1.02452 +/- 0.00085\n", + " 440/1 1.04964 1.02458 +/- 0.00085\n", + " 441/1 0.99792 1.02452 +/- 0.00085\n", + " 442/1 1.04971 1.02457 +/- 0.00085\n", + " 443/1 1.01504 1.02455 +/- 0.00085\n", + " 444/1 1.04359 1.02460 +/- 0.00085\n", + " 445/1 1.01148 1.02457 +/- 0.00085\n", + " 446/1 1.01203 1.02454 +/- 0.00085\n", + " 447/1 1.02353 1.02454 +/- 0.00085\n", + " 448/1 1.06299 1.02462 +/- 0.00085\n", + " 449/1 1.00017 1.02457 +/- 0.00085\n", + " 450/1 1.01193 1.02454 +/- 0.00085\n", + " 451/1 1.00179 1.02449 +/- 0.00085\n", + " 452/1 1.02425 1.02449 +/- 0.00085\n", + " 453/1 1.03629 1.02451 +/- 0.00084\n", + " 454/1 1.01955 1.02450 +/- 0.00084\n", + " 455/1 1.00870 1.02447 +/- 0.00084\n", + " 456/1 1.04230 1.02451 +/- 0.00084\n", + " 457/1 1.05081 1.02457 +/- 0.00084\n", + " 458/1 1.00271 1.02452 +/- 0.00084\n", + " 459/1 1.01010 1.02448 +/- 0.00084\n", + " 460/1 1.04656 1.02453 +/- 0.00084\n", + " 461/1 1.00790 1.02450 +/- 0.00084\n", + " 462/1 1.02214 1.02449 +/- 0.00084\n", + " 463/1 1.04401 1.02453 +/- 0.00083\n", + " 464/1 1.02863 1.02454 +/- 0.00083\n", + " 465/1 0.99971 1.02449 +/- 0.00083\n", + " 466/1 1.00344 1.02444 +/- 0.00083\n", + " 467/1 1.02810 1.02445 +/- 0.00083\n", + " 468/1 1.02091 1.02444 +/- 0.00083\n", + " 469/1 1.00545 1.02440 +/- 0.00083\n", + " 470/1 1.01590 1.02438 +/- 0.00083\n", + " 471/1 1.04465 1.02443 +/- 0.00083\n", + " 472/1 1.02028 1.02442 +/- 0.00082\n", + " 473/1 1.01951 1.02441 +/- 0.00082\n", + " 474/1 1.03280 1.02443 +/- 0.00082\n", + " 475/1 1.04722 1.02447 +/- 0.00082\n", + " 476/1 1.03587 1.02450 +/- 0.00082\n", + " 477/1 1.02234 1.02449 +/- 0.00082\n", + " 478/1 1.07848 1.02461 +/- 0.00082\n", + " 479/1 1.04759 1.02466 +/- 0.00082\n", + " 480/1 1.07189 1.02476 +/- 0.00083\n", + " 481/1 1.05811 1.02483 +/- 0.00083\n", + " 482/1 1.04554 1.02487 +/- 0.00083\n", + " 483/1 1.01956 1.02486 +/- 0.00083\n", + " 484/1 1.01055 1.02483 +/- 0.00083\n", + " 485/1 1.00845 1.02480 +/- 0.00082\n", + " 486/1 1.04607 1.02484 +/- 0.00082\n", + " 487/1 1.05955 1.02492 +/- 0.00083\n", + " 488/1 1.02245 1.02491 +/- 0.00082\n", + " 489/1 0.98206 1.02482 +/- 0.00083\n", + " 490/1 1.03786 1.02485 +/- 0.00083\n", + " 491/1 1.02973 1.02486 +/- 0.00082\n", + " 492/1 1.02890 1.02487 +/- 0.00082\n", + " 493/1 1.02086 1.02486 +/- 0.00082\n", + " 494/1 1.01194 1.02483 +/- 0.00082\n", + " 495/1 1.01902 1.02482 +/- 0.00082\n", + " 496/1 1.01783 1.02481 +/- 0.00082\n", + " 497/1 1.02129 1.02480 +/- 0.00081\n", + " 498/1 1.02407 1.02480 +/- 0.00081\n", + " 499/1 1.02873 1.02480 +/- 0.00081\n", + " 500/1 1.00998 1.02477 +/- 0.00081\n", + " Creating state point statepoint.500.h5...\n", "\n", " ===========================================================================\n", " ======================> SIMULATION FINISHED <======================\n", @@ -915,27 +1234,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4810E+00 seconds\n", - " Reading cross sections = 1.1600E+00 seconds\n", - " Total time in simulation = 9.8823E+01 seconds\n", - " Time in transport only = 9.8622E+01 seconds\n", - " Time in inactive batches = 2.1290E+00 seconds\n", - " Time in active batches = 9.6694E+01 seconds\n", - " Time synchronizing fission bank = 1.4000E-02 seconds\n", - " Sampling source sites = 1.1000E-02 seconds\n", - " SEND/RECV source sites = 3.0000E-03 seconds\n", + " Total time for initialization = 1.5880E+00 seconds\n", + " Reading cross sections = 1.2650E+00 seconds\n", + " Total time in simulation = 2.6051E+02 seconds\n", + " Time in transport only = 2.6013E+02 seconds\n", + " Time in inactive batches = 2.0990E+00 seconds\n", + " Time in active batches = 2.5841E+02 seconds\n", + " Time synchronizing fission bank = 6.5000E-02 seconds\n", + " Sampling source sites = 4.4000E-02 seconds\n", + " SEND/RECV source sites = 2.1000E-02 seconds\n", " Time accumulating tallies = 2.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.0031E+02 seconds\n", - " Calculation Rate (inactive) = 23485.2 neutrons/second\n", - " Calculation Rate (active) = 9824.81 neutrons/second\n", + " Total time elapsed = 2.6211E+02 seconds\n", + " Calculation Rate (inactive) = 23820.9 neutrons/second\n", + " Calculation Rate (active) = 9480.98 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02505 +/- 0.00122\n", - " k-effective (Track-length) = 1.02604 +/- 0.00129\n", - " k-effective (Absorption) = 1.02501 +/- 0.00111\n", - " Combined k-effective = 1.02544 +/- 0.00091\n", + " k-effective (Collision) = 1.02480 +/- 0.00073\n", + " k-effective (Track-length) = 1.02477 +/- 0.00081\n", + " k-effective (Absorption) = 1.02552 +/- 0.00068\n", + " Combined k-effective = 1.02519 +/- 0.00055\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -946,7 +1265,7 @@ "0" ] }, - "execution_count": 25, + "execution_count": 26, "metadata": {}, "output_type": "execute_result" } @@ -965,14 +1284,14 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 27, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ "# Move the StatePoint File\n", - "ce_spfile = './ce.h5'\n", + "ce_spfile = './ce_statepoint.h5'\n", "os.rename('statepoint.' + str(batches) + '.h5', ce_spfile)\n", "# Move the Summary file\n", "ce_sumfile = './ce_summary.h5'\n", @@ -985,44 +1304,26 @@ "source": [ "# Tally Data Processing\n", "\n", - "Our simulation ran successfully and created statepoint and summary output files. We begin our analysis by instantiating a `StatePoint` object." - ] - }, - { - "cell_type": "code", - "execution_count": 27, - "metadata": { - "collapsed": true - }, - "outputs": [], - "source": [ - "# Load the statepoint file\n", - "sp = openmc.StatePoint(ce_spfile)" - ] - }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "Next we will save the value of keff from the continuous-energy calculation for later comparison" + "Our simulation ran successfully and created statepoint and summary output files. Let's begin by loading the StatePoint file, but not automatically linking the summary file." ] }, { "cell_type": "code", "execution_count": 28, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ - "ce_keff = sp.k_combined" + "# Load the statepoint file, but not the summary file, as it is a different filename than expected.\n", + "sp = openmc.StatePoint(ce_spfile, autolink=False)" ] }, { "cell_type": "markdown", "metadata": {}, "source": [ - "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint." + "In addition to the statepoint file, our simulation also created a summary file which encapsulates information about the materials and geometry. This is necessary for the `openmc.mgxs` module to properly process the tally data. We first create a `Summary` object and link it with the statepoint. Normally this would not need to be performed, but since we have renamed our summary file to avoid conflicts with the Multi-Group calculation's summary file, we will load this in explicitly." ] }, { @@ -1037,32 +1338,6 @@ "sp.link_with_summary(su)" ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "Next we will extract our fission distribution results from the statepoint for later comparison." - ] - }, - { - "cell_type": "code", - "execution_count": 30, - "metadata": { - "collapsed": false - }, - "outputs": [], - "source": [ - "# Get the OpenMC fission rate mesh tally data\n", - "mesh_tally = sp.get_tally(name='mesh tally')\n", - "openmc_fission_rates = mesh_tally.get_values(scores=['fission'])\n", - "\n", - "# Reshape array to 2D for plotting\n", - "openmc_fission_rates.shape = (17,17)\n", - "\n", - "# Normalize to the average pin power\n", - "openmc_fission_rates /= np.mean(openmc_fission_rates)" - ] - }, { "cell_type": "markdown", "metadata": {}, @@ -1072,7 +1347,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 30, "metadata": { "collapsed": false }, @@ -1105,7 +1380,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -1114,53 +1389,38 @@ "name": "stderr", "output_type": "stream", "text": [ - "/home/nelsonag/git/openmc/openmc/tallies.py:1996: RuntimeWarning: invalid value encountered in true_divide\n", + "/home/nelsonag/git/openmc/openmc/tallies.py:1988: RuntimeWarning: invalid value encountered in true_divide\n", " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n", - "/home/nelsonag/git/openmc/openmc/tallies.py:1997: RuntimeWarning: invalid value encountered in true_divide\n", + "/home/nelsonag/git/openmc/openmc/tallies.py:1989: RuntimeWarning: invalid value encountered in true_divide\n", " other_rel_err = data['other']['std. dev.'] / data['other']['mean']\n", - "/home/nelsonag/git/openmc/openmc/tallies.py:1998: RuntimeWarning: invalid value encountered in true_divide\n", + "/home/nelsonag/git/openmc/openmc/tallies.py:1990: RuntimeWarning: invalid value encountered in true_divide\n", " new_tally._mean = data['self']['mean'] / data['other']['mean']\n" ] - }, - { - "data": { - "text/plain": [ - "{10000: 'fuel.2g',\n", - " 10001: 'fuel_clad.2g',\n", - " 10002: 'fuel_mod.2g',\n", - " 10003: 'gt_inmod.2g',\n", - " 10004: 'gt_clad.2g',\n", - " 10005: 'gt_outmod.2g'}" - ] - }, - "execution_count": 32, - "metadata": {}, - "output_type": "execute_result" } ], "source": [ "mgxs_lib.write_mg_library(filename='mgxs', xs_type='macro',\n", " domain_names=['fuel', 'fuel_clad', 'fuel_mod',\n", " 'gt_inmod', 'gt_clad', 'gt_outmod'],\n", - " xs_ids='2g')" + " xs_ids='2m')" ] }, { "cell_type": "markdown", "metadata": {}, "source": [ - "Now we will need to recreate similar xml files from above, beginning with materials.xml" + "Now we will need to recreate similar xml files from above, beginning with materials.xml. Similar to how continuous-energy cross section libraries are named, the `openmc.Macroscopic` quantities below can either have their `xs_id` included (i.e., `'.2m'`), or this can be left off but the `default_xs` parameter of the materials file be used instead to be set to the `'xs_id'` of interest (which is `'.2m'` in this case as defined in the previous cell)." ] }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 32, "metadata": { "collapsed": false }, "outputs": [], "source": [ - "# Instantiate our Macroscopic Data\n", + "# Instantiate our Macroscopic Data using mat_names for the name\n", "fuel_macro = openmc.Macroscopic('fuel')\n", "fuel_clad_macro = openmc.Macroscopic('fuel_clad')\n", "fuel_mod_macro = openmc.Macroscopic('fuel_mod')\n", @@ -1171,39 +1431,39 @@ "# Now define the materials\n", "\n", "# 1.6 enriched fuel UO2\n", - "fuel = openmc.Material(name='1.6% Fuel UO2')\n", + "fuel = openmc.Material(name='1.6% Fuel UO2', material_id=1)\n", "fuel.set_density('macro', 1.0)\n", "fuel.add_macroscopic(fuel_macro)\n", "\n", "# 1.6 enriched fuel cladding\n", - "fuel_clad = openmc.Material(name='1.6% Fuel Clad')\n", + "fuel_clad = openmc.Material(name='1.6% Fuel Clad', material_id=2)\n", "fuel_clad.set_density('macro', 1.0)\n", "fuel_clad.add_macroscopic(fuel_clad_macro)\n", "\n", "# 1.6 enriched fuel moderator\n", - "fuel_mod = openmc.Material(name='1.6% Fuel Water')\n", + "fuel_mod = openmc.Material(name='1.6% Fuel Water', material_id=3)\n", "fuel_mod.set_density('macro', 1.0)\n", "fuel_mod.add_macroscopic(fuel_mod_macro)\n", "\n", "# Guide Tube Inner Moderator\n", - "gt_inmod = openmc.Material(name='GT Inner Water')\n", + "gt_inmod = openmc.Material(name='GT Inner Water', material_id=4)\n", "gt_inmod.set_density('macro', 1.0)\n", "gt_inmod.add_macroscopic(gt_inmod_macro)\n", "\n", "# Guide Tube Cladding\n", - "gt_clad = openmc.Material(name='GT Clad')\n", + "gt_clad = openmc.Material(name='GT Clad', material_id=5)\n", "gt_clad.set_density('macro', 1.0)\n", "gt_clad.add_macroscopic(gt_clad_macro)\n", "\n", "# Guide Tube Outer Moderator\n", - "gt_outmod = openmc.Material(name='GT Outer Water')\n", + "gt_outmod = openmc.Material(name='GT Outer Water', material_id=6)\n", "gt_outmod.set_density('macro', 1.0)\n", "gt_outmod.add_macroscopic(gt_outmod_macro)\n", "\n", "# Finally, instantiate our Materials object\n", "materials_file = openmc.Materials((fuel, fuel_clad, fuel_mod,\n", " gt_inmod, gt_clad, gt_outmod))\n", - "materials_file.default_xs = '2g'\n", + "materials_file.default_xs = '2m'\n", "\n", "# Export to \"materials.xml\"\n", "materials_file.export_to_xml()\n" @@ -1213,61 +1473,62 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "For our geometry files we will simply repeat what as done for continuous-energy mode, except change the cell fill (i.e., the material) to use our newly defined materials." + "\n", + "For our geometry files we will do the same as before but now we will be pointing at our newly created materials instead." ] }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 33, "metadata": { "collapsed": false }, "outputs": [], "source": [ "# Create a Universe to encapsulate a fuel pin\n", - "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin')\n", + "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin', universe_id=10)\n", "\n", "# Create fuel Cell\n", - "fuel_cell = openmc.Cell(name='1.6% Fuel')\n", + "fuel_cell = openmc.Cell(name='1.6% Fuel', cell_id=1)\n", "fuel_cell.fill = fuel\n", "fuel_cell.region = -fuel_outer_radius\n", "fuel_pin_universe.add_cell(fuel_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='1.6% Clad')\n", + "clad_cell = openmc.Cell(name='1.6% Clad', cell_id=2)\n", "clad_cell.fill = fuel_clad\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "fuel_pin_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='1.6% Moderator')\n", + "moderator_cell = openmc.Cell(name='1.6% Moderator', cell_id=3)\n", "moderator_cell.fill = fuel_mod\n", "moderator_cell.region = +clad_outer_radius\n", "fuel_pin_universe.add_cell(moderator_cell)\n", "\n", "# Create a Universe to encapsulate a control rod guide tube\n", - "guide_tube_universe = openmc.Universe(name='Guide Tube')\n", + "guide_tube_universe = openmc.Universe(name='Guide Tube', universe_id=20)\n", "\n", "# Create guide tube Cell\n", - "guide_tube_cell = openmc.Cell(name='Guide Tube Water')\n", + "guide_tube_cell = openmc.Cell(name='Guide Tube Water', cell_id=4)\n", "guide_tube_cell.fill = gt_inmod\n", "guide_tube_cell.region = -fuel_outer_radius\n", "guide_tube_universe.add_cell(guide_tube_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='Guide Clad')\n", + "clad_cell = openmc.Cell(name='Guide Clad', cell_id=5)\n", "clad_cell.fill = gt_clad\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "guide_tube_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='Guide Tube Moderator')\n", + "moderator_cell = openmc.Cell(name='Guide Tube Moderator', cell_id=6)\n", "moderator_cell.fill = gt_outmod\n", "moderator_cell.region = +clad_outer_radius\n", "guide_tube_universe.add_cell(moderator_cell)\n", "\n", "# Create fuel assembly Lattice\n", - "assembly = openmc.RectLattice(name='1.6% Fuel Assembly')\n", + "assembly = openmc.RectLattice(name='1.6% Fuel Assembly', lattice_id=100)\n", "assembly.dimension = (17, 17)\n", "assembly.pitch = (1.26, 1.26)\n", "assembly.lower_left = [-1.26 * 17. / 2.0] * 2\n", @@ -1289,7 +1550,7 @@ "assembly.universes = universes\n", "\n", "# Create root Cell\n", - "root_cell = openmc.Cell(name='root cell')\n", + "root_cell = openmc.Cell(name='root cell', cell_id=0)\n", "root_cell.fill = assembly\n", "\n", "# Add boundary planes\n", @@ -1316,7 +1577,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { "collapsed": true }, @@ -1334,50 +1595,14 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Finally, lets tell OpenMC we want to tally fissions over a mesh for comparison. " + "Finally, since we want similar tally data in the end, we will leave our pre-existing `tallies.xml` file for this calculation.\n", + "\n", + "At this point, the problem is set up and we can run the multi-group calculation." ] }, { "cell_type": "code", - "execution_count": 36, - "metadata": { - "collapsed": true - }, - "outputs": [], - "source": [ - "# Instantiate a tally Mesh\n", - "mesh = openmc.Mesh(mesh_id=1)\n", - "mesh.type = 'regular'\n", - "mesh.dimension = [17, 17]\n", - "mesh.lower_left = [-10.71, -10.71]\n", - "mesh.upper_right = [+10.71, +10.71]\n", - "\n", - "# Instantiate tally Filter\n", - "mesh_filter = openmc.Filter()\n", - "mesh_filter.mesh = mesh\n", - "\n", - "# Instantiate the Tally\n", - "tally = openmc.Tally(name='mesh tally')\n", - "tally.filters = [mesh_filter]\n", - "tally.scores = ['fission']\n", - "\n", - "# Add tally to collection\n", - "tallies_file.append(tally)\n", - "\n", - "# Export all tallies to a \"tallies.xml\" file\n", - "tallies_file.export_to_xml()" - ] - }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "Before we run the calculation we will close the StatePoint file (as we are about to over-write it), and then we can run the multi-group calculation." - ] - }, - { - "cell_type": "code", - "execution_count": 37, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -1402,8 +1627,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 179e9ab147e505563d118ed58096b3d225160ffa\n", - " Date/Time: 2016-05-07 14:23:45\n", + " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", + " Date/Time: 2016-05-12 21:19:25\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1417,12 +1642,12 @@ " Reading tallies XML file...\n", " Building neighboring cells lists for each surface...\n", " Loading Cross Section Data...\n", - " Loading fuel.2g Data...\n", - " Loading fuel_clad.2g Data...\n", - " Loading fuel_mod.2g Data...\n", - " Loading gt_inmod.2g Data...\n", - " Loading gt_clad.2g Data...\n", - " Loading gt_outmod.2g Data...\n", + " Loading fuel.2m Data...\n", + " Loading fuel_clad.2m Data...\n", + " Loading fuel_mod.2m Data...\n", + " Loading gt_inmod.2m Data...\n", + " Loading gt_clad.2m Data...\n", + " Loading gt_outmod.2m Data...\n", " Initializing source particles...\n", "\n", " ===========================================================================\n", @@ -1431,207 +1656,507 @@ "\n", " Bat./Gen. k Average k \n", " ========= ======== ==================== \n", - " 1/1 1.01863 \n", - " 2/1 1.02630 \n", - " 3/1 1.03077 \n", - " 4/1 0.99715 \n", - " 5/1 1.02328 \n", - " 6/1 1.02283 \n", - " 7/1 1.00540 \n", - " 8/1 1.02232 \n", - " 9/1 0.99782 \n", - " 10/1 1.00838 \n", - " 11/1 1.01803 \n", - " 12/1 1.02530 1.02167 +/- 0.00363\n", - " 13/1 1.00514 1.01616 +/- 0.00589\n", - " 14/1 0.98994 1.00960 +/- 0.00777\n", - " 15/1 1.01028 1.00974 +/- 0.00602\n", - " 16/1 1.04607 1.01580 +/- 0.00780\n", - " 17/1 1.03300 1.01825 +/- 0.00703\n", - " 18/1 1.03149 1.01991 +/- 0.00631\n", - " 19/1 0.98692 1.01624 +/- 0.00667\n", - " 20/1 1.05205 1.01982 +/- 0.00695\n", - " 21/1 1.01572 1.01945 +/- 0.00630\n", - " 22/1 1.02517 1.01993 +/- 0.00577\n", - " 23/1 1.00274 1.01861 +/- 0.00547\n", - " 24/1 1.04739 1.02066 +/- 0.00547\n", - " 25/1 1.01883 1.02054 +/- 0.00509\n", - " 26/1 1.02021 1.02052 +/- 0.00476\n", - " 27/1 1.04696 1.02207 +/- 0.00474\n", - " 28/1 1.02751 1.02238 +/- 0.00448\n", - " 29/1 1.09537 1.02622 +/- 0.00572\n", - " 30/1 1.03685 1.02675 +/- 0.00545\n", - " 31/1 0.99812 1.02539 +/- 0.00536\n", - " 32/1 1.02526 1.02538 +/- 0.00511\n", - " 33/1 1.05466 1.02665 +/- 0.00505\n", - " 34/1 1.04816 1.02755 +/- 0.00491\n", - " 35/1 1.00148 1.02651 +/- 0.00483\n", - " 36/1 1.02315 1.02638 +/- 0.00464\n", - " 37/1 1.05771 1.02754 +/- 0.00461\n", - " 38/1 1.01675 1.02715 +/- 0.00446\n", - " 39/1 1.03707 1.02749 +/- 0.00432\n", - " 40/1 1.01903 1.02721 +/- 0.00418\n", - " 41/1 1.00332 1.02644 +/- 0.00412\n", - " 42/1 1.02533 1.02641 +/- 0.00399\n", - " 43/1 0.98531 1.02516 +/- 0.00406\n", - " 44/1 1.00406 1.02454 +/- 0.00399\n", - " 45/1 1.01057 1.02414 +/- 0.00389\n", - " 46/1 1.02755 1.02424 +/- 0.00378\n", - " 47/1 1.02783 1.02433 +/- 0.00368\n", - " 48/1 1.00003 1.02369 +/- 0.00364\n", - " 49/1 1.00442 1.02320 +/- 0.00358\n", - " 50/1 1.03215 1.02342 +/- 0.00350\n", - " 51/1 1.01672 1.02326 +/- 0.00341\n", - " 52/1 1.03702 1.02359 +/- 0.00335\n", - " 53/1 1.02063 1.02352 +/- 0.00327\n", - " 54/1 1.04596 1.02403 +/- 0.00323\n", - " 55/1 1.01926 1.02392 +/- 0.00316\n", - " 56/1 1.03058 1.02407 +/- 0.00310\n", - " 57/1 1.06126 1.02486 +/- 0.00313\n", - " 58/1 1.06411 1.02568 +/- 0.00317\n", - " 59/1 1.03278 1.02582 +/- 0.00311\n", - " 60/1 1.04472 1.02620 +/- 0.00307\n", - " 61/1 1.00186 1.02572 +/- 0.00305\n", - " 62/1 1.01133 1.02545 +/- 0.00300\n", - " 63/1 1.03713 1.02567 +/- 0.00295\n", - " 64/1 1.01363 1.02544 +/- 0.00291\n", - " 65/1 0.98126 1.02464 +/- 0.00296\n", - " 66/1 1.01500 1.02447 +/- 0.00292\n", - " 67/1 1.02437 1.02447 +/- 0.00286\n", - " 68/1 1.05057 1.02492 +/- 0.00285\n", - " 69/1 1.04903 1.02533 +/- 0.00283\n", - " 70/1 1.02199 1.02527 +/- 0.00278\n", - " 71/1 1.00536 1.02494 +/- 0.00276\n", - " 72/1 1.01658 1.02481 +/- 0.00272\n", - " 73/1 1.00866 1.02455 +/- 0.00268\n", - " 74/1 1.01800 1.02445 +/- 0.00264\n", - " 75/1 0.99176 1.02395 +/- 0.00265\n", - " 76/1 1.03336 1.02409 +/- 0.00262\n", - " 77/1 1.02699 1.02413 +/- 0.00258\n", - " 78/1 1.01596 1.02401 +/- 0.00254\n", - " 79/1 1.02292 1.02400 +/- 0.00250\n", - " 80/1 1.04804 1.02434 +/- 0.00249\n", - " 81/1 0.99494 1.02393 +/- 0.00249\n", - " 82/1 1.02646 1.02396 +/- 0.00246\n", - " 83/1 1.01223 1.02380 +/- 0.00243\n", - " 84/1 1.02572 1.02383 +/- 0.00239\n", - " 85/1 1.02709 1.02387 +/- 0.00236\n", - " 86/1 1.00315 1.02360 +/- 0.00235\n", - " 87/1 1.01809 1.02353 +/- 0.00232\n", - " 88/1 1.01566 1.02342 +/- 0.00229\n", - " 89/1 1.01093 1.02327 +/- 0.00227\n", - " 90/1 1.02812 1.02333 +/- 0.00224\n", - " 91/1 1.02288 1.02332 +/- 0.00221\n", - " 92/1 1.04070 1.02353 +/- 0.00219\n", - " 93/1 1.03697 1.02370 +/- 0.00217\n", - " 94/1 1.03486 1.02383 +/- 0.00215\n", - " 95/1 1.06359 1.02430 +/- 0.00218\n", - " 96/1 1.04811 1.02457 +/- 0.00217\n", - " 97/1 1.01303 1.02444 +/- 0.00215\n", - " 98/1 1.01243 1.02430 +/- 0.00213\n", - " 99/1 1.03238 1.02439 +/- 0.00211\n", - " 100/1 1.02054 1.02435 +/- 0.00208\n", - " 101/1 1.00402 1.02413 +/- 0.00207\n", - " 102/1 1.03800 1.02428 +/- 0.00206\n", - " 103/1 1.02541 1.02429 +/- 0.00203\n", - " 104/1 1.06867 1.02476 +/- 0.00207\n", - " 105/1 1.03192 1.02484 +/- 0.00205\n", - " 106/1 1.00100 1.02459 +/- 0.00204\n", - " 107/1 1.01098 1.02445 +/- 0.00202\n", - " 108/1 1.02930 1.02450 +/- 0.00200\n", - " 109/1 1.02173 1.02447 +/- 0.00198\n", - " 110/1 1.01411 1.02437 +/- 0.00197\n", - " 111/1 1.03920 1.02452 +/- 0.00195\n", - " 112/1 1.01984 1.02447 +/- 0.00193\n", - " 113/1 1.03912 1.02461 +/- 0.00192\n", - " 114/1 1.04124 1.02477 +/- 0.00191\n", - " 115/1 1.04802 1.02499 +/- 0.00190\n", - " 116/1 1.04129 1.02515 +/- 0.00189\n", - " 117/1 1.03072 1.02520 +/- 0.00187\n", - " 118/1 1.05167 1.02544 +/- 0.00187\n", - " 119/1 0.99954 1.02521 +/- 0.00187\n", - " 120/1 1.00093 1.02499 +/- 0.00187\n", - " 121/1 1.04929 1.02520 +/- 0.00186\n", - " 122/1 1.04556 1.02539 +/- 0.00185\n", - " 123/1 1.03298 1.02545 +/- 0.00184\n", - " 124/1 1.01603 1.02537 +/- 0.00182\n", - " 125/1 1.03522 1.02546 +/- 0.00181\n", - " 126/1 1.05644 1.02572 +/- 0.00181\n", - " 127/1 1.03754 1.02582 +/- 0.00180\n", - " 128/1 1.01524 1.02573 +/- 0.00179\n", - " 129/1 1.01263 1.02562 +/- 0.00178\n", - " 130/1 0.99835 1.02540 +/- 0.00178\n", - " 131/1 1.01268 1.02529 +/- 0.00177\n", - " 132/1 1.03975 1.02541 +/- 0.00175\n", - " 133/1 1.00702 1.02526 +/- 0.00175\n", - " 134/1 1.02335 1.02525 +/- 0.00173\n", - " 135/1 1.04378 1.02539 +/- 0.00173\n", - " 136/1 1.04610 1.02556 +/- 0.00172\n", - " 137/1 1.02284 1.02554 +/- 0.00171\n", - " 138/1 1.05720 1.02578 +/- 0.00171\n", - " 139/1 1.00965 1.02566 +/- 0.00170\n", - " 140/1 1.03719 1.02575 +/- 0.00169\n", - " 141/1 1.02413 1.02574 +/- 0.00168\n", - " 142/1 1.03125 1.02578 +/- 0.00167\n", - " 143/1 1.03641 1.02586 +/- 0.00166\n", - " 144/1 1.02137 1.02582 +/- 0.00164\n", - " 145/1 1.01522 1.02575 +/- 0.00163\n", - " 146/1 1.05163 1.02594 +/- 0.00163\n", - " 147/1 1.03612 1.02601 +/- 0.00162\n", - " 148/1 1.03346 1.02606 +/- 0.00161\n", - " 149/1 1.02306 1.02604 +/- 0.00160\n", - " 150/1 1.01764 1.02598 +/- 0.00159\n", - " 151/1 1.01787 1.02592 +/- 0.00158\n", - " 152/1 1.03263 1.02597 +/- 0.00157\n", - " 153/1 1.01877 1.02592 +/- 0.00156\n", - " 154/1 1.02870 1.02594 +/- 0.00155\n", - " 155/1 1.03071 1.02597 +/- 0.00154\n", - " 156/1 1.04229 1.02609 +/- 0.00153\n", - " 157/1 1.03973 1.02618 +/- 0.00152\n", - " 158/1 1.02180 1.02615 +/- 0.00151\n", - " 159/1 1.01067 1.02604 +/- 0.00151\n", - " 160/1 1.02888 1.02606 +/- 0.00150\n", - " 161/1 1.01711 1.02600 +/- 0.00149\n", - " 162/1 1.01087 1.02590 +/- 0.00148\n", - " 163/1 1.01886 1.02586 +/- 0.00147\n", - " 164/1 1.02210 1.02583 +/- 0.00146\n", - " 165/1 1.04020 1.02593 +/- 0.00146\n", - " 166/1 1.03658 1.02600 +/- 0.00145\n", - " 167/1 1.03222 1.02603 +/- 0.00144\n", - " 168/1 1.03247 1.02608 +/- 0.00143\n", - " 169/1 0.99739 1.02590 +/- 0.00143\n", - " 170/1 1.02464 1.02589 +/- 0.00142\n", - " 171/1 1.04623 1.02601 +/- 0.00142\n", - " 172/1 1.04328 1.02612 +/- 0.00142\n", - " 173/1 1.00812 1.02601 +/- 0.00141\n", - " 174/1 1.01224 1.02593 +/- 0.00141\n", - " 175/1 1.00882 1.02582 +/- 0.00140\n", - " 176/1 1.01286 1.02574 +/- 0.00140\n", - " 177/1 1.02048 1.02571 +/- 0.00139\n", - " 178/1 1.04269 1.02581 +/- 0.00138\n", - " 179/1 1.05862 1.02601 +/- 0.00139\n", - " 180/1 1.02924 1.02603 +/- 0.00138\n", - " 181/1 1.01491 1.02596 +/- 0.00137\n", - " 182/1 1.04255 1.02606 +/- 0.00137\n", - " 183/1 0.99191 1.02586 +/- 0.00137\n", - " 184/1 1.00392 1.02573 +/- 0.00137\n", - " 185/1 1.02982 1.02576 +/- 0.00137\n", - " 186/1 1.02682 1.02576 +/- 0.00136\n", - " 187/1 1.01484 1.02570 +/- 0.00135\n", - " 188/1 1.02825 1.02572 +/- 0.00134\n", - " 189/1 0.98954 1.02551 +/- 0.00135\n", - " 190/1 1.00522 1.02540 +/- 0.00135\n", - " 191/1 1.03762 1.02547 +/- 0.00134\n", - " 192/1 1.02091 1.02544 +/- 0.00134\n", - " 193/1 1.04549 1.02555 +/- 0.00133\n", - " 194/1 1.05531 1.02572 +/- 0.00134\n", - " 195/1 1.01479 1.02566 +/- 0.00133\n", - " 196/1 1.01337 1.02559 +/- 0.00132\n", - " 197/1 0.99187 1.02541 +/- 0.00133\n", - " 198/1 1.01280 1.02534 +/- 0.00132\n", - " 199/1 1.00049 1.02521 +/- 0.00132\n", - " 200/1 1.01879 1.02518 +/- 0.00132\n", - " Creating state point statepoint.200.h5...\n", + " 1/1 1.01702 \n", + " 2/1 0.99463 \n", + " 3/1 1.02321 \n", + " 4/1 0.98628 \n", + " 5/1 1.03122 \n", + " 6/1 1.00774 \n", + " 7/1 1.05616 \n", + " 8/1 1.03051 \n", + " 9/1 1.02321 \n", + " 10/1 1.04380 \n", + " 11/1 1.05837 \n", + " 12/1 1.01514 1.03676 +/- 0.02161\n", + " 13/1 1.06720 1.04690 +/- 0.01608\n", + " 14/1 1.01696 1.03942 +/- 0.01361\n", + " 15/1 1.03549 1.03863 +/- 0.01057\n", + " 16/1 1.01599 1.03486 +/- 0.00942\n", + " 17/1 1.03070 1.03427 +/- 0.00799\n", + " 18/1 1.03778 1.03470 +/- 0.00693\n", + " 19/1 1.03042 1.03423 +/- 0.00613\n", + " 20/1 1.01047 1.03185 +/- 0.00598\n", + " 21/1 1.03251 1.03191 +/- 0.00541\n", + " 22/1 1.02047 1.03096 +/- 0.00503\n", + " 23/1 1.01729 1.02991 +/- 0.00474\n", + " 24/1 1.02948 1.02988 +/- 0.00439\n", + " 25/1 1.01963 1.02919 +/- 0.00414\n", + " 26/1 1.00626 1.02776 +/- 0.00413\n", + " 27/1 1.04531 1.02879 +/- 0.00402\n", + " 28/1 0.99936 1.02716 +/- 0.00412\n", + " 29/1 1.04497 1.02809 +/- 0.00401\n", + " 30/1 1.02429 1.02790 +/- 0.00381\n", + " 31/1 1.05112 1.02901 +/- 0.00379\n", + " 32/1 1.01843 1.02853 +/- 0.00365\n", + " 33/1 1.04478 1.02924 +/- 0.00355\n", + " 34/1 1.01719 1.02873 +/- 0.00344\n", + " 35/1 0.99873 1.02753 +/- 0.00351\n", + " 36/1 1.00054 1.02649 +/- 0.00353\n", + " 37/1 1.03986 1.02699 +/- 0.00343\n", + " 38/1 1.02243 1.02683 +/- 0.00331\n", + " 39/1 1.02744 1.02685 +/- 0.00319\n", + " 40/1 1.01174 1.02634 +/- 0.00313\n", + " 41/1 1.04973 1.02710 +/- 0.00312\n", + " 42/1 0.99564 1.02612 +/- 0.00317\n", + " 43/1 1.03022 1.02624 +/- 0.00308\n", + " 44/1 1.03526 1.02650 +/- 0.00300\n", + " 45/1 1.02143 1.02636 +/- 0.00292\n", + " 46/1 1.03264 1.02653 +/- 0.00284\n", + " 47/1 1.03868 1.02686 +/- 0.00278\n", + " 48/1 1.02385 1.02678 +/- 0.00271\n", + " 49/1 1.03897 1.02710 +/- 0.00266\n", + " 50/1 1.01267 1.02674 +/- 0.00261\n", + " 51/1 0.99683 1.02601 +/- 0.00265\n", + " 52/1 1.04189 1.02638 +/- 0.00261\n", + " 53/1 1.02871 1.02644 +/- 0.00255\n", + " 54/1 1.02564 1.02642 +/- 0.00250\n", + " 55/1 1.02955 1.02649 +/- 0.00244\n", + " 56/1 1.02390 1.02643 +/- 0.00239\n", + " 57/1 1.03342 1.02658 +/- 0.00234\n", + " 58/1 1.01430 1.02633 +/- 0.00231\n", + " 59/1 0.99242 1.02563 +/- 0.00236\n", + " 60/1 1.00442 1.02521 +/- 0.00235\n", + " 61/1 1.03870 1.02547 +/- 0.00232\n", + " 62/1 1.02146 1.02540 +/- 0.00228\n", + " 63/1 1.04782 1.02582 +/- 0.00227\n", + " 64/1 1.02872 1.02587 +/- 0.00223\n", + " 65/1 1.02420 1.02584 +/- 0.00219\n", + " 66/1 1.01974 1.02573 +/- 0.00215\n", + " 67/1 1.00774 1.02542 +/- 0.00214\n", + " 68/1 1.01323 1.02521 +/- 0.00211\n", + " 69/1 1.01468 1.02503 +/- 0.00208\n", + " 70/1 1.02869 1.02509 +/- 0.00205\n", + " 71/1 1.02284 1.02505 +/- 0.00202\n", + " 72/1 1.04815 1.02543 +/- 0.00202\n", + " 73/1 1.01119 1.02520 +/- 0.00200\n", + " 74/1 1.03314 1.02533 +/- 0.00197\n", + " 75/1 1.02333 1.02529 +/- 0.00194\n", + " 76/1 1.04030 1.02552 +/- 0.00193\n", + " 77/1 1.02537 1.02552 +/- 0.00190\n", + " 78/1 1.02875 1.02557 +/- 0.00187\n", + " 79/1 1.03588 1.02572 +/- 0.00185\n", + " 80/1 1.05250 1.02610 +/- 0.00186\n", + " 81/1 1.00477 1.02580 +/- 0.00186\n", + " 82/1 1.03903 1.02598 +/- 0.00184\n", + " 83/1 1.02378 1.02595 +/- 0.00182\n", + " 84/1 1.01107 1.02575 +/- 0.00180\n", + " 85/1 1.01550 1.02561 +/- 0.00178\n", + " 86/1 1.00540 1.02535 +/- 0.00178\n", + " 87/1 1.03056 1.02542 +/- 0.00176\n", + " 88/1 1.01742 1.02531 +/- 0.00174\n", + " 89/1 0.99730 1.02496 +/- 0.00175\n", + " 90/1 1.03569 1.02509 +/- 0.00174\n", + " 91/1 1.04514 1.02534 +/- 0.00173\n", + " 92/1 1.02757 1.02537 +/- 0.00171\n", + " 93/1 1.00610 1.02514 +/- 0.00171\n", + " 94/1 1.03576 1.02526 +/- 0.00169\n", + " 95/1 1.03732 1.02540 +/- 0.00168\n", + " 96/1 1.04784 1.02567 +/- 0.00168\n", + " 97/1 1.06507 1.02612 +/- 0.00172\n", + " 98/1 1.03673 1.02624 +/- 0.00170\n", + " 99/1 1.01270 1.02609 +/- 0.00169\n", + " 100/1 1.01980 1.02602 +/- 0.00167\n", + " 101/1 1.01357 1.02588 +/- 0.00166\n", + " 102/1 1.03125 1.02594 +/- 0.00164\n", + " 103/1 1.01527 1.02582 +/- 0.00163\n", + " 104/1 1.02403 1.02580 +/- 0.00161\n", + " 105/1 1.03435 1.02589 +/- 0.00160\n", + " 106/1 1.04113 1.02605 +/- 0.00159\n", + " 107/1 1.03291 1.02612 +/- 0.00157\n", + " 108/1 1.02478 1.02611 +/- 0.00156\n", + " 109/1 1.05814 1.02643 +/- 0.00158\n", + " 110/1 1.02647 1.02643 +/- 0.00156\n", + " 111/1 0.98951 1.02607 +/- 0.00159\n", + " 112/1 1.00739 1.02589 +/- 0.00158\n", + " 113/1 1.04165 1.02604 +/- 0.00157\n", + " 114/1 1.00047 1.02579 +/- 0.00158\n", + " 115/1 1.02550 1.02579 +/- 0.00156\n", + " 116/1 1.02408 1.02577 +/- 0.00155\n", + " 117/1 1.03110 1.02582 +/- 0.00153\n", + " 118/1 1.02874 1.02585 +/- 0.00152\n", + " 119/1 1.02348 1.02583 +/- 0.00151\n", + " 120/1 1.01969 1.02577 +/- 0.00149\n", + " 121/1 1.02312 1.02575 +/- 0.00148\n", + " 122/1 1.03261 1.02581 +/- 0.00147\n", + " 123/1 0.98394 1.02544 +/- 0.00150\n", + " 124/1 1.03771 1.02555 +/- 0.00149\n", + " 125/1 1.01857 1.02549 +/- 0.00148\n", + " 126/1 1.00066 1.02527 +/- 0.00148\n", + " 127/1 1.02372 1.02526 +/- 0.00147\n", + " 128/1 1.03307 1.02533 +/- 0.00146\n", + " 129/1 1.00889 1.02519 +/- 0.00145\n", + " 130/1 1.02053 1.02515 +/- 0.00144\n", + " 131/1 1.00943 1.02502 +/- 0.00144\n", + " 132/1 1.07225 1.02541 +/- 0.00148\n", + " 133/1 1.04068 1.02553 +/- 0.00147\n", + " 134/1 1.03509 1.02561 +/- 0.00146\n", + " 135/1 1.01250 1.02550 +/- 0.00145\n", + " 136/1 1.02179 1.02547 +/- 0.00144\n", + " 137/1 1.05685 1.02572 +/- 0.00145\n", + " 138/1 1.04217 1.02585 +/- 0.00144\n", + " 139/1 1.02793 1.02586 +/- 0.00143\n", + " 140/1 1.01207 1.02576 +/- 0.00143\n", + " 141/1 1.03445 1.02582 +/- 0.00142\n", + " 142/1 1.03579 1.02590 +/- 0.00141\n", + " 143/1 1.00786 1.02576 +/- 0.00140\n", + " 144/1 0.99089 1.02550 +/- 0.00142\n", + " 145/1 1.02617 1.02551 +/- 0.00141\n", + " 146/1 1.01691 1.02545 +/- 0.00140\n", + " 147/1 1.00692 1.02531 +/- 0.00139\n", + " 148/1 0.97702 1.02496 +/- 0.00143\n", + " 149/1 1.04002 1.02507 +/- 0.00142\n", + " 150/1 1.01262 1.02498 +/- 0.00141\n", + " 151/1 1.03613 1.02506 +/- 0.00141\n", + " 152/1 1.02920 1.02509 +/- 0.00140\n", + " 153/1 1.02199 1.02507 +/- 0.00139\n", + " 154/1 1.03421 1.02513 +/- 0.00138\n", + " 155/1 1.05882 1.02536 +/- 0.00139\n", + " 156/1 1.02649 1.02537 +/- 0.00138\n", + " 157/1 1.01933 1.02533 +/- 0.00137\n", + " 158/1 1.04269 1.02545 +/- 0.00137\n", + " 159/1 0.99604 1.02525 +/- 0.00137\n", + " 160/1 1.04748 1.02540 +/- 0.00137\n", + " 161/1 1.00501 1.02526 +/- 0.00137\n", + " 162/1 1.00550 1.02513 +/- 0.00137\n", + " 163/1 1.00115 1.02498 +/- 0.00137\n", + " 164/1 1.02283 1.02496 +/- 0.00136\n", + " 165/1 1.01964 1.02493 +/- 0.00135\n", + " 166/1 1.02287 1.02491 +/- 0.00134\n", + " 167/1 1.05498 1.02511 +/- 0.00134\n", + " 168/1 1.05267 1.02528 +/- 0.00135\n", + " 169/1 1.00474 1.02515 +/- 0.00135\n", + " 170/1 1.03469 1.02521 +/- 0.00134\n", + " 171/1 1.02499 1.02521 +/- 0.00133\n", + " 172/1 1.03961 1.02530 +/- 0.00132\n", + " 173/1 1.01240 1.02522 +/- 0.00132\n", + " 174/1 1.00762 1.02511 +/- 0.00132\n", + " 175/1 1.00200 1.02497 +/- 0.00131\n", + " 176/1 1.01449 1.02491 +/- 0.00131\n", + " 177/1 1.01111 1.02483 +/- 0.00130\n", + " 178/1 1.01208 1.02475 +/- 0.00130\n", + " 179/1 1.03304 1.02480 +/- 0.00129\n", + " 180/1 1.04504 1.02492 +/- 0.00129\n", + " 181/1 1.03476 1.02498 +/- 0.00128\n", + " 182/1 1.02124 1.02495 +/- 0.00128\n", + " 183/1 0.98855 1.02474 +/- 0.00128\n", + " 184/1 1.04689 1.02487 +/- 0.00128\n", + " 185/1 1.00618 1.02476 +/- 0.00128\n", + " 186/1 1.02012 1.02474 +/- 0.00127\n", + " 187/1 1.00162 1.02461 +/- 0.00127\n", + " 188/1 1.03269 1.02465 +/- 0.00127\n", + " 189/1 1.04772 1.02478 +/- 0.00127\n", + " 190/1 1.01132 1.02471 +/- 0.00126\n", + " 191/1 1.02669 1.02472 +/- 0.00125\n", + " 192/1 1.01154 1.02464 +/- 0.00125\n", + " 193/1 1.05795 1.02483 +/- 0.00126\n", + " 194/1 1.01615 1.02478 +/- 0.00125\n", + " 195/1 1.03828 1.02485 +/- 0.00125\n", + " 196/1 1.00695 1.02476 +/- 0.00124\n", + " 197/1 1.04126 1.02484 +/- 0.00124\n", + " 198/1 1.02834 1.02486 +/- 0.00123\n", + " 199/1 1.01000 1.02478 +/- 0.00123\n", + " 200/1 0.99294 1.02462 +/- 0.00123\n", + " 201/1 1.00248 1.02450 +/- 0.00123\n", + " 202/1 1.03461 1.02455 +/- 0.00123\n", + " 203/1 1.06289 1.02475 +/- 0.00124\n", + " 204/1 1.03010 1.02478 +/- 0.00123\n", + " 205/1 1.04636 1.02489 +/- 0.00123\n", + " 206/1 1.05434 1.02504 +/- 0.00123\n", + " 207/1 1.03993 1.02512 +/- 0.00123\n", + " 208/1 1.02672 1.02512 +/- 0.00122\n", + " 209/1 1.04958 1.02525 +/- 0.00122\n", + " 210/1 0.99194 1.02508 +/- 0.00123\n", + " 211/1 1.01570 1.02503 +/- 0.00122\n", + " 212/1 1.04079 1.02511 +/- 0.00122\n", + " 213/1 1.02961 1.02513 +/- 0.00121\n", + " 214/1 1.03797 1.02520 +/- 0.00121\n", + " 215/1 1.03714 1.02526 +/- 0.00120\n", + " 216/1 1.03299 1.02529 +/- 0.00120\n", + " 217/1 1.00461 1.02519 +/- 0.00120\n", + " 218/1 1.02386 1.02519 +/- 0.00119\n", + " 219/1 1.01955 1.02516 +/- 0.00119\n", + " 220/1 1.04372 1.02525 +/- 0.00118\n", + " 221/1 1.01694 1.02521 +/- 0.00118\n", + " 222/1 0.99642 1.02507 +/- 0.00118\n", + " 223/1 1.00999 1.02500 +/- 0.00118\n", + " 224/1 1.02703 1.02501 +/- 0.00117\n", + " 225/1 1.00236 1.02491 +/- 0.00117\n", + " 226/1 1.02825 1.02492 +/- 0.00117\n", + " 227/1 1.04535 1.02502 +/- 0.00116\n", + " 228/1 1.01779 1.02498 +/- 0.00116\n", + " 229/1 1.01058 1.02492 +/- 0.00116\n", + " 230/1 1.00391 1.02482 +/- 0.00115\n", + " 231/1 1.05990 1.02498 +/- 0.00116\n", + " 232/1 1.01885 1.02495 +/- 0.00116\n", + " 233/1 1.03204 1.02498 +/- 0.00115\n", + " 234/1 0.99396 1.02485 +/- 0.00115\n", + " 235/1 1.01828 1.02482 +/- 0.00115\n", + " 236/1 1.08225 1.02507 +/- 0.00117\n", + " 237/1 1.00335 1.02498 +/- 0.00117\n", + " 238/1 1.03097 1.02500 +/- 0.00117\n", + " 239/1 1.01738 1.02497 +/- 0.00116\n", + " 240/1 1.02261 1.02496 +/- 0.00116\n", + " 241/1 1.02814 1.02497 +/- 0.00115\n", + " 242/1 1.01158 1.02491 +/- 0.00115\n", + " 243/1 1.03507 1.02496 +/- 0.00114\n", + " 244/1 1.01914 1.02493 +/- 0.00114\n", + " 245/1 1.04555 1.02502 +/- 0.00114\n", + " 246/1 1.02459 1.02502 +/- 0.00113\n", + " 247/1 1.05827 1.02516 +/- 0.00114\n", + " 248/1 1.02549 1.02516 +/- 0.00113\n", + " 249/1 1.03354 1.02520 +/- 0.00113\n", + " 250/1 1.04186 1.02526 +/- 0.00113\n", + " 251/1 1.00466 1.02518 +/- 0.00112\n", + " 252/1 0.99065 1.02504 +/- 0.00113\n", + " 253/1 1.03065 1.02506 +/- 0.00112\n", + " 254/1 1.02167 1.02505 +/- 0.00112\n", + " 255/1 1.01700 1.02501 +/- 0.00112\n", + " 256/1 1.03619 1.02506 +/- 0.00111\n", + " 257/1 1.01833 1.02503 +/- 0.00111\n", + " 258/1 1.02211 1.02502 +/- 0.00110\n", + " 259/1 1.04348 1.02509 +/- 0.00110\n", + " 260/1 1.03444 1.02513 +/- 0.00110\n", + " 261/1 1.05597 1.02525 +/- 0.00110\n", + " 262/1 1.02085 1.02524 +/- 0.00110\n", + " 263/1 1.00552 1.02516 +/- 0.00109\n", + " 264/1 1.03976 1.02522 +/- 0.00109\n", + " 265/1 1.02810 1.02523 +/- 0.00109\n", + " 266/1 1.00911 1.02516 +/- 0.00108\n", + " 267/1 1.01963 1.02514 +/- 0.00108\n", + " 268/1 1.03732 1.02519 +/- 0.00108\n", + " 269/1 1.02422 1.02519 +/- 0.00107\n", + " 270/1 1.01546 1.02515 +/- 0.00107\n", + " 271/1 1.05488 1.02526 +/- 0.00107\n", + " 272/1 1.01709 1.02523 +/- 0.00107\n", + " 273/1 1.05629 1.02535 +/- 0.00107\n", + " 274/1 1.03864 1.02540 +/- 0.00107\n", + " 275/1 1.01472 1.02536 +/- 0.00106\n", + " 276/1 1.03425 1.02539 +/- 0.00106\n", + " 277/1 1.00663 1.02532 +/- 0.00106\n", + " 278/1 1.03326 1.02535 +/- 0.00106\n", + " 279/1 1.02571 1.02535 +/- 0.00105\n", + " 280/1 1.00525 1.02528 +/- 0.00105\n", + " 281/1 1.00451 1.02520 +/- 0.00105\n", + " 282/1 1.04016 1.02526 +/- 0.00105\n", + " 283/1 0.98343 1.02510 +/- 0.00105\n", + " 284/1 1.04843 1.02519 +/- 0.00105\n", + " 285/1 1.01807 1.02516 +/- 0.00105\n", + " 286/1 1.02393 1.02516 +/- 0.00105\n", + " 287/1 1.01851 1.02514 +/- 0.00104\n", + " 288/1 1.03976 1.02519 +/- 0.00104\n", + " 289/1 1.03153 1.02521 +/- 0.00104\n", + " 290/1 1.00416 1.02514 +/- 0.00104\n", + " 291/1 1.01426 1.02510 +/- 0.00103\n", + " 292/1 1.02583 1.02510 +/- 0.00103\n", + " 293/1 1.01680 1.02507 +/- 0.00103\n", + " 294/1 1.04578 1.02514 +/- 0.00103\n", + " 295/1 1.03162 1.02517 +/- 0.00102\n", + " 296/1 1.01682 1.02514 +/- 0.00102\n", + " 297/1 1.00488 1.02507 +/- 0.00102\n", + " 298/1 1.03057 1.02508 +/- 0.00101\n", + " 299/1 1.01126 1.02504 +/- 0.00101\n", + " 300/1 1.03528 1.02507 +/- 0.00101\n", + " 301/1 1.05548 1.02518 +/- 0.00101\n", + " 302/1 1.02994 1.02519 +/- 0.00101\n", + " 303/1 1.03010 1.02521 +/- 0.00100\n", + " 304/1 1.04031 1.02526 +/- 0.00100\n", + " 305/1 1.05866 1.02537 +/- 0.00101\n", + " 306/1 1.03602 1.02541 +/- 0.00100\n", + " 307/1 1.01362 1.02537 +/- 0.00100\n", + " 308/1 1.01318 1.02533 +/- 0.00100\n", + " 309/1 1.04262 1.02539 +/- 0.00100\n", + " 310/1 1.01626 1.02536 +/- 0.00099\n", + " 311/1 1.00285 1.02528 +/- 0.00099\n", + " 312/1 0.98155 1.02514 +/- 0.00100\n", + " 313/1 1.05649 1.02524 +/- 0.00100\n", + " 314/1 1.00960 1.02519 +/- 0.00100\n", + " 315/1 1.05350 1.02528 +/- 0.00100\n", + " 316/1 1.03842 1.02533 +/- 0.00100\n", + " 317/1 1.01394 1.02529 +/- 0.00100\n", + " 318/1 1.01830 1.02527 +/- 0.00099\n", + " 319/1 1.02050 1.02525 +/- 0.00099\n", + " 320/1 1.03402 1.02528 +/- 0.00099\n", + " 321/1 1.04547 1.02534 +/- 0.00099\n", + " 322/1 1.02579 1.02534 +/- 0.00098\n", + " 323/1 1.01922 1.02533 +/- 0.00098\n", + " 324/1 1.01050 1.02528 +/- 0.00098\n", + " 325/1 1.01426 1.02524 +/- 0.00098\n", + " 326/1 1.03283 1.02527 +/- 0.00097\n", + " 327/1 1.03859 1.02531 +/- 0.00097\n", + " 328/1 1.01536 1.02528 +/- 0.00097\n", + " 329/1 1.03149 1.02530 +/- 0.00097\n", + " 330/1 1.04328 1.02535 +/- 0.00096\n", + " 331/1 1.01949 1.02534 +/- 0.00096\n", + " 332/1 1.02319 1.02533 +/- 0.00096\n", + " 333/1 1.01704 1.02530 +/- 0.00096\n", + " 334/1 1.02691 1.02531 +/- 0.00095\n", + " 335/1 1.03188 1.02533 +/- 0.00095\n", + " 336/1 1.03107 1.02535 +/- 0.00095\n", + " 337/1 1.02410 1.02534 +/- 0.00094\n", + " 338/1 0.99917 1.02526 +/- 0.00094\n", + " 339/1 1.03593 1.02529 +/- 0.00094\n", + " 340/1 1.02286 1.02529 +/- 0.00094\n", + " 341/1 1.04154 1.02534 +/- 0.00094\n", + " 342/1 1.01664 1.02531 +/- 0.00094\n", + " 343/1 1.01041 1.02527 +/- 0.00093\n", + " 344/1 1.02033 1.02525 +/- 0.00093\n", + " 345/1 1.03137 1.02527 +/- 0.00093\n", + " 346/1 1.02162 1.02526 +/- 0.00093\n", + " 347/1 1.00835 1.02521 +/- 0.00092\n", + " 348/1 1.01168 1.02517 +/- 0.00092\n", + " 349/1 1.01168 1.02513 +/- 0.00092\n", + " 350/1 1.03509 1.02516 +/- 0.00092\n", + " 351/1 1.01883 1.02514 +/- 0.00092\n", + " 352/1 1.04314 1.02519 +/- 0.00091\n", + " 353/1 0.99067 1.02509 +/- 0.00092\n", + " 354/1 1.03100 1.02511 +/- 0.00091\n", + " 355/1 1.01664 1.02508 +/- 0.00091\n", + " 356/1 1.02193 1.02507 +/- 0.00091\n", + " 357/1 1.03213 1.02509 +/- 0.00091\n", + " 358/1 1.00555 1.02504 +/- 0.00091\n", + " 359/1 1.04849 1.02511 +/- 0.00091\n", + " 360/1 1.02174 1.02510 +/- 0.00090\n", + " 361/1 1.05064 1.02517 +/- 0.00090\n", + " 362/1 1.05274 1.02525 +/- 0.00091\n", + " 363/1 1.00932 1.02520 +/- 0.00090\n", + " 364/1 1.03400 1.02523 +/- 0.00090\n", + " 365/1 1.00149 1.02516 +/- 0.00090\n", + " 366/1 1.01631 1.02514 +/- 0.00090\n", + " 367/1 1.03928 1.02517 +/- 0.00090\n", + " 368/1 1.01318 1.02514 +/- 0.00090\n", + " 369/1 1.04610 1.02520 +/- 0.00090\n", + " 370/1 1.04338 1.02525 +/- 0.00089\n", + " 371/1 1.01638 1.02523 +/- 0.00089\n", + " 372/1 1.04056 1.02527 +/- 0.00089\n", + " 373/1 1.00090 1.02520 +/- 0.00089\n", + " 374/1 1.01261 1.02517 +/- 0.00089\n", + " 375/1 1.03919 1.02520 +/- 0.00089\n", + " 376/1 0.99900 1.02513 +/- 0.00089\n", + " 377/1 1.00168 1.02507 +/- 0.00089\n", + " 378/1 0.99476 1.02499 +/- 0.00089\n", + " 379/1 1.04960 1.02505 +/- 0.00089\n", + " 380/1 0.99797 1.02498 +/- 0.00089\n", + " 381/1 1.04956 1.02505 +/- 0.00089\n", + " 382/1 1.02803 1.02505 +/- 0.00089\n", + " 383/1 0.99388 1.02497 +/- 0.00089\n", + " 384/1 1.00767 1.02492 +/- 0.00089\n", + " 385/1 1.00856 1.02488 +/- 0.00089\n", + " 386/1 1.02997 1.02489 +/- 0.00088\n", + " 387/1 0.97841 1.02477 +/- 0.00089\n", + " 388/1 0.99712 1.02470 +/- 0.00089\n", + " 389/1 0.99072 1.02461 +/- 0.00089\n", + " 390/1 1.02439 1.02461 +/- 0.00089\n", + " 391/1 1.02769 1.02462 +/- 0.00089\n", + " 392/1 1.02205 1.02461 +/- 0.00089\n", + " 393/1 1.03702 1.02464 +/- 0.00088\n", + " 394/1 1.00274 1.02458 +/- 0.00088\n", + " 395/1 1.00131 1.02452 +/- 0.00088\n", + " 396/1 1.00130 1.02446 +/- 0.00088\n", + " 397/1 1.00472 1.02441 +/- 0.00088\n", + " 398/1 1.00724 1.02437 +/- 0.00088\n", + " 399/1 1.03061 1.02438 +/- 0.00088\n", + " 400/1 0.99651 1.02431 +/- 0.00088\n", + " 401/1 0.99290 1.02423 +/- 0.00088\n", + " 402/1 1.02166 1.02423 +/- 0.00088\n", + " 403/1 1.01691 1.02421 +/- 0.00088\n", + " 404/1 1.00492 1.02416 +/- 0.00088\n", + " 405/1 1.00663 1.02411 +/- 0.00088\n", + " 406/1 1.01865 1.02410 +/- 0.00087\n", + " 407/1 1.02717 1.02411 +/- 0.00087\n", + " 408/1 1.01793 1.02409 +/- 0.00087\n", + " 409/1 1.02606 1.02410 +/- 0.00087\n", + " 410/1 1.03809 1.02413 +/- 0.00087\n", + " 411/1 1.03780 1.02417 +/- 0.00086\n", + " 412/1 1.02782 1.02418 +/- 0.00086\n", + " 413/1 1.03077 1.02419 +/- 0.00086\n", + " 414/1 1.00651 1.02415 +/- 0.00086\n", + " 415/1 1.05594 1.02423 +/- 0.00086\n", + " 416/1 0.99558 1.02416 +/- 0.00086\n", + " 417/1 1.00689 1.02411 +/- 0.00086\n", + " 418/1 1.02932 1.02413 +/- 0.00086\n", + " 419/1 1.03552 1.02415 +/- 0.00086\n", + " 420/1 1.03735 1.02419 +/- 0.00085\n", + " 421/1 1.02402 1.02419 +/- 0.00085\n", + " 422/1 1.04227 1.02423 +/- 0.00085\n", + " 423/1 1.03087 1.02425 +/- 0.00085\n", + " 424/1 1.04363 1.02429 +/- 0.00085\n", + " 425/1 1.02676 1.02430 +/- 0.00085\n", + " 426/1 1.03739 1.02433 +/- 0.00085\n", + " 427/1 1.02977 1.02434 +/- 0.00084\n", + " 428/1 1.02547 1.02435 +/- 0.00084\n", + " 429/1 1.03552 1.02437 +/- 0.00084\n", + " 430/1 1.04282 1.02442 +/- 0.00084\n", + " 431/1 1.03171 1.02443 +/- 0.00084\n", + " 432/1 1.01030 1.02440 +/- 0.00084\n", + " 433/1 1.04168 1.02444 +/- 0.00084\n", + " 434/1 0.98994 1.02436 +/- 0.00084\n", + " 435/1 0.98166 1.02426 +/- 0.00084\n", + " 436/1 1.00178 1.02421 +/- 0.00084\n", + " 437/1 1.03801 1.02424 +/- 0.00084\n", + " 438/1 1.02099 1.02423 +/- 0.00084\n", + " 439/1 1.01305 1.02421 +/- 0.00084\n", + " 440/1 1.02286 1.02420 +/- 0.00083\n", + " 441/1 1.03697 1.02423 +/- 0.00083\n", + " 442/1 0.99050 1.02415 +/- 0.00083\n", + " 443/1 1.02238 1.02415 +/- 0.00083\n", + " 444/1 1.05188 1.02421 +/- 0.00083\n", + " 445/1 1.03150 1.02423 +/- 0.00083\n", + " 446/1 1.01071 1.02420 +/- 0.00083\n", + " 447/1 1.03713 1.02423 +/- 0.00083\n", + " 448/1 1.03631 1.02426 +/- 0.00083\n", + " 449/1 1.02968 1.02427 +/- 0.00083\n", + " 450/1 1.03031 1.02428 +/- 0.00082\n", + " 451/1 1.02161 1.02428 +/- 0.00082\n", + " 452/1 0.99036 1.02420 +/- 0.00082\n", + " 453/1 1.02581 1.02420 +/- 0.00082\n", + " 454/1 1.03140 1.02422 +/- 0.00082\n", + " 455/1 1.01962 1.02421 +/- 0.00082\n", + " 456/1 1.00680 1.02417 +/- 0.00082\n", + " 457/1 1.00178 1.02412 +/- 0.00082\n", + " 458/1 1.02306 1.02412 +/- 0.00082\n", + " 459/1 1.02653 1.02412 +/- 0.00081\n", + " 460/1 1.02934 1.02413 +/- 0.00081\n", + " 461/1 1.00872 1.02410 +/- 0.00081\n", + " 462/1 1.00012 1.02405 +/- 0.00081\n", + " 463/1 0.99057 1.02397 +/- 0.00081\n", + " 464/1 1.02353 1.02397 +/- 0.00081\n", + " 465/1 1.01402 1.02395 +/- 0.00081\n", + " 466/1 1.01651 1.02393 +/- 0.00081\n", + " 467/1 1.01024 1.02390 +/- 0.00081\n", + " 468/1 1.02504 1.02391 +/- 0.00080\n", + " 469/1 1.00891 1.02387 +/- 0.00080\n", + " 470/1 1.04038 1.02391 +/- 0.00080\n", + " 471/1 1.04346 1.02395 +/- 0.00080\n", + " 472/1 1.02634 1.02396 +/- 0.00080\n", + " 473/1 1.01207 1.02393 +/- 0.00080\n", + " 474/1 1.00787 1.02390 +/- 0.00080\n", + " 475/1 1.03591 1.02392 +/- 0.00080\n", + " 476/1 1.04257 1.02396 +/- 0.00080\n", + " 477/1 1.00536 1.02392 +/- 0.00079\n", + " 478/1 1.07545 1.02403 +/- 0.00080\n", + " 479/1 1.02306 1.02403 +/- 0.00080\n", + " 480/1 1.02733 1.02404 +/- 0.00080\n", + " 481/1 1.00990 1.02401 +/- 0.00080\n", + " 482/1 0.99031 1.02394 +/- 0.00080\n", + " 483/1 0.98006 1.02384 +/- 0.00080\n", + " 484/1 1.05635 1.02391 +/- 0.00080\n", + " 485/1 1.02410 1.02391 +/- 0.00080\n", + " 486/1 1.01227 1.02389 +/- 0.00080\n", + " 487/1 1.00614 1.02385 +/- 0.00080\n", + " 488/1 1.01837 1.02384 +/- 0.00080\n", + " 489/1 1.02565 1.02384 +/- 0.00080\n", + " 490/1 1.00530 1.02381 +/- 0.00079\n", + " 491/1 1.01958 1.02380 +/- 0.00079\n", + " 492/1 1.04490 1.02384 +/- 0.00079\n", + " 493/1 1.02567 1.02384 +/- 0.00079\n", + " 494/1 1.03865 1.02387 +/- 0.00079\n", + " 495/1 1.03990 1.02391 +/- 0.00079\n", + " 496/1 0.98352 1.02382 +/- 0.00079\n", + " 497/1 1.00909 1.02379 +/- 0.00079\n", + " 498/1 1.03661 1.02382 +/- 0.00079\n", + " 499/1 1.04423 1.02386 +/- 0.00079\n", + " 500/1 1.06406 1.02394 +/- 0.00079\n", + " Creating state point statepoint.500.h5...\n", "\n", " ===========================================================================\n", " ======================> SIMULATION FINISHED <======================\n", @@ -1640,27 +2165,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 6.3000E-02 seconds\n", + " Total time for initialization = 5.3000E-02 seconds\n", " Reading cross sections = 5.0000E-03 seconds\n", - " Total time in simulation = 7.3280E+01 seconds\n", - " Time in transport only = 7.3104E+01 seconds\n", - " Time in inactive batches = 1.1200E+00 seconds\n", - " Time in active batches = 7.2160E+01 seconds\n", - " Time synchronizing fission bank = 2.5000E-02 seconds\n", - " Sampling source sites = 1.8000E-02 seconds\n", - " SEND/RECV source sites = 7.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", + " Total time in simulation = 1.8631E+02 seconds\n", + " Time in transport only = 1.8590E+02 seconds\n", + " Time in inactive batches = 1.1710E+00 seconds\n", + " Time in active batches = 1.8514E+02 seconds\n", + " Time synchronizing fission bank = 7.3000E-02 seconds\n", + " Sampling source sites = 5.1000E-02 seconds\n", + " SEND/RECV source sites = 2.2000E-02 seconds\n", + " Time accumulating tallies = 4.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 7.3353E+01 seconds\n", - " Calculation Rate (inactive) = 44642.9 neutrons/second\n", - " Calculation Rate (active) = 13165.2 neutrons/second\n", + " Total time elapsed = 1.8637E+02 seconds\n", + " Calculation Rate (inactive) = 42698.5 neutrons/second\n", + " Calculation Rate (active) = 13233.2 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02597 +/- 0.00117\n", - " k-effective (Track-length) = 1.02518 +/- 0.00132\n", - " k-effective (Absorption) = 1.02581 +/- 0.00070\n", - " Combined k-effective = 1.02562 +/- 0.00068\n", + " k-effective (Collision) = 1.02403 +/- 0.00071\n", + " k-effective (Track-length) = 1.02394 +/- 0.00079\n", + " k-effective (Absorption) = 1.02539 +/- 0.00044\n", + " Combined k-effective = 1.02518 +/- 0.00042\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -1671,15 +2196,12 @@ "0" ] }, - "execution_count": 37, + "execution_count": 35, "metadata": {}, "output_type": "execute_result" } ], "source": [ - "# Close the StatePoint File\n", - "sp._f.close()\n", - "\n", "# Run the Multi-Group OpenMC Simulation\n", "openmc.run()" ] @@ -1691,12 +2213,13 @@ "# Results Comparison\n", "Now we can compare the multi-group and continuous-energy results.\n", "\n", - "We will begin by loading the multi-group statepoint file we just finished writing and extracting the calculated keff." + "We will begin by loading the multi-group statepoint file we just finished writing and extracting the calculated keff.\n", + "Since we did not rename the summary file, we do not need to load it separately this time." ] }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -1704,11 +2227,27 @@ "source": [ "# Load the last statepoint file and keff value\n", "mgsp = openmc.StatePoint('statepoint.' + str(batches) + '.h5')\n", - "mgsu = openmc.Summary('summary.h5')\n", - "mgsp.link_with_summary(mgsu)\n", "mg_keff = mgsp.k_combined" ] }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Next, we can load the continuous-energy eigenvalue for comparison." + ] + }, + { + "cell_type": "code", + "execution_count": 37, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "ce_keff = sp.k_combined" + ] + }, { "cell_type": "markdown", "metadata": {}, @@ -1718,7 +2257,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -1727,9 +2266,9 @@ "name": "stdout", "output_type": "stream", "text": [ - "Continuous-Energy keff = 1.025440\n", - "Multi-Group keff = 1.025621\n", - "bias [pcm]: -18.1\n" + "Continuous-Energy keff = 1.025194\n", + "Multi-Group keff = 1.025183\n", + "bias [pcm]: 1.1\n" ] } ], @@ -1745,7 +2284,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We see quite good agreement with only an 18pcm difference between the two." + "We see quite good agreement with only an 1 pcm difference between the two. While these results are quite favorable, due to the high degree of approximations inherent in practical application of multi-group theory, one should not expect results of such fidelity always for multi-group Monte Carlo calculations." ] }, { @@ -1764,16 +2303,9 @@ "First, we extract volume-integrated fission rates from the Multi-Group calculation's mesh fission rate tally for each pin cell in the fuel assembly." ] }, - { - "cell_type": "markdown", - "metadata": {}, - "source": [ - "Now we can do the same for the Multi-Group results." - ] - }, { "cell_type": "code", - "execution_count": 40, + "execution_count": 39, "metadata": { "collapsed": false }, @@ -1790,6 +2322,32 @@ "mgopenmc_fission_rates /= np.mean(mgopenmc_fission_rates)" ] }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now we can do the same for the Multi-Group results." + ] + }, + { + "cell_type": "code", + "execution_count": 40, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [ + "# Get the OpenMC fission rate mesh tally data\n", + "mesh_tally = sp.get_tally(name='mesh tally')\n", + "openmc_fission_rates = mesh_tally.get_values(scores=['fission'])\n", + "\n", + "# Reshape array to 2D for plotting\n", + "openmc_fission_rates.shape = (17,17)\n", + "\n", + "# Normalize to the average pin power\n", + "openmc_fission_rates /= np.mean(openmc_fission_rates)" + ] + }, { "cell_type": "markdown", "metadata": {}, @@ -1807,7 +2365,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 41, @@ -1816,9 +2374,9 @@ }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1845,6 +2403,15 @@ "source": [ "We also see very good agreement between the fission rate distributions." ] + }, + { + "cell_type": "code", + "execution_count": null, + "metadata": { + "collapsed": true + }, + "outputs": [], + "source": [] } ], "metadata": { diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 82b761673..334a0fa9c 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -724,7 +724,7 @@ class Library(object): def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, filename='mg_cross_sections', directory='./', - return_names=True): + return_names=False): """Creates a cross-section data library file for the Multi-Group mode of OpenMC. @@ -749,7 +749,7 @@ class Library(object): return_names : bool Flag to indicate if the user would like the names of the materials generated by this function returned with completion. - Defaults to True. + Defaults to False, indicating that no names will be returned. Returns ------- From 7ed772d6c3b59e633fbb9201f100a27d8008c15d Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 10:08:54 -0400 Subject: [PATCH 123/147] Now using scatter-PN scores in ScatterMatrixXS for tallying efficiency --- .../pythonapi/examples/mgxs-part-i.ipynb | 40 +- .../pythonapi/examples/mgxs-part-ii.ipynb | 78 +- .../pythonapi/examples/mgxs-part-iii.ipynb | 36 +- openmc/mgxs/mgxs.py | 192 +- .../results_true.dat | 48 +- .../results_true.dat | 4 +- .../results_true.dat | 120 +- .../results_true.dat | 1600 ++++++++--------- 8 files changed, 1075 insertions(+), 1043 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index 2f2a80177..2d44d95cd 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -410,7 +410,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 13, "metadata": { "collapsed": false }, @@ -419,27 +419,27 @@ "data": { "text/plain": [ "OrderedDict([('flux', Tally\n", - "\tID =\t10012\n", + "\tID =\t10000\n", "\tName =\t\n", "\tFilters =\t\n", " \t\tcell\t[1]\n", " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'flux']\n", + "\tScores =\t['flux']\n", "\tEstimator =\ttracklength\n", "), ('absorption', Tally\n", - "\tID =\t10013\n", + "\tID =\t10001\n", "\tName =\t\n", "\tFilters =\t\n", " \t\tcell\t[1]\n", " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", "\tNuclides =\ttotal \n", - "\tScores =\t[u'absorption']\n", + "\tScores =\t['absorption']\n", "\tEstimator =\ttracklength\n", ")])" ] }, - "execution_count": 26, + "execution_count": 13, "metadata": {}, "output_type": "execute_result" } @@ -513,8 +513,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", - " Date/Time: 2016-05-12 20:41:27\n", + " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", + " Date/Time: 2016-05-13 09:02:04\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -600,20 +600,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.7500E-01 seconds\n", - " Reading cross sections = 9.7000E-02 seconds\n", - " Total time in simulation = 1.8074E+01 seconds\n", - " Time in transport only = 1.8055E+01 seconds\n", - " Time in inactive batches = 2.1180E+00 seconds\n", - " Time in active batches = 1.5956E+01 seconds\n", + " Total time for initialization = 4.2500E-01 seconds\n", + " Reading cross sections = 8.5000E-02 seconds\n", + " Total time in simulation = 1.6642E+01 seconds\n", + " Time in transport only = 1.6628E+01 seconds\n", + " Time in inactive batches = 1.9160E+00 seconds\n", + " Time in active batches = 1.4726E+01 seconds\n", " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 4.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", - " Time accumulating tallies = 2.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.8559E+01 seconds\n", - " Calculation Rate (inactive) = 11803.6 neutrons/second\n", - " Calculation Rate (active) = 6267.23 neutrons/second\n", + " Total time elapsed = 1.7076E+01 seconds\n", + " Calculation Rate (inactive) = 13048.0 neutrons/second\n", + " Calculation Rate (active) = 6790.71 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index ca07519e5..d57f2a1f3 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -445,8 +445,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", - " Date/Time: 2016-05-12 21:00:03\n", + " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", + " Date/Time: 2016-05-13 10:04:37\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -562,20 +562,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.1000E-01 seconds\n", - " Reading cross sections = 8.6000E-02 seconds\n", - " Total time in simulation = 2.2903E+02 seconds\n", - " Time in transport only = 2.2897E+02 seconds\n", - " Time in inactive batches = 1.4619E+01 seconds\n", - " Time in active batches = 2.1441E+02 seconds\n", - " Time synchronizing fission bank = 2.5000E-02 seconds\n", - " Sampling source sites = 1.6000E-02 seconds\n", - " SEND/RECV source sites = 8.0000E-03 seconds\n", + " Total time for initialization = 4.9300E-01 seconds\n", + " Reading cross sections = 1.0800E-01 seconds\n", + " Total time in simulation = 2.2830E+02 seconds\n", + " Time in transport only = 2.2826E+02 seconds\n", + " Time in inactive batches = 1.5534E+01 seconds\n", + " Time in active batches = 2.1277E+02 seconds\n", + " Time synchronizing fission bank = 1.8000E-02 seconds\n", + " Sampling source sites = 1.3000E-02 seconds\n", + " SEND/RECV source sites = 4.0000E-03 seconds\n", " Time accumulating tallies = 1.0000E-03 seconds\n", - " Total time for finalization = 1.2000E-02 seconds\n", - " Total time elapsed = 2.2951E+02 seconds\n", - " Calculation Rate (inactive) = 6840.41 neutrons/second\n", - " Calculation Rate (active) = 1865.57 neutrons/second\n", + " Total time for finalization = 1.1000E-02 seconds\n", + " Total time elapsed = 2.2887E+02 seconds\n", + " Calculation Rate (inactive) = 6437.49 neutrons/second\n", + " Calculation Rate (active) = 1879.96 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -786,10 +786,8 @@ " group in\n", " group out\n", " nuclide\n", - " moment\n", " mean\n", " std. dev.\n", - " moment\n", " \n", " \n", " \n", @@ -799,10 +797,8 @@ " 1\n", " 1\n", " H-1\n", - " P0\n", " 0.234115\n", " 0.003568\n", - " P0\n", " \n", " \n", " 127\n", @@ -810,10 +806,8 @@ " 1\n", " 1\n", " O-16\n", - " P0\n", " 1.563707\n", " 0.005953\n", - " P0\n", " \n", " \n", " 124\n", @@ -821,10 +815,8 @@ " 1\n", " 2\n", " H-1\n", - " P0\n", " 1.594129\n", " 0.002369\n", - " P0\n", " \n", " \n", " 125\n", @@ -832,10 +824,8 @@ " 1\n", " 2\n", " O-16\n", - " P0\n", " 0.285761\n", " 0.001676\n", - " P0\n", " \n", " \n", " 122\n", @@ -843,10 +833,8 @@ " 1\n", " 3\n", " H-1\n", - " P0\n", " 0.011089\n", " 0.000248\n", - " P0\n", " \n", " \n", " 123\n", @@ -854,10 +842,8 @@ " 1\n", " 3\n", " O-16\n", - " P0\n", " 0.000000\n", " 0.000000\n", - " P0\n", " \n", " \n", " 120\n", @@ -865,10 +851,8 @@ " 1\n", " 4\n", " H-1\n", - " P0\n", " 0.000000\n", " 0.000000\n", - " P0\n", " \n", " \n", " 121\n", @@ -876,10 +860,8 @@ " 1\n", " 4\n", " O-16\n", - " P0\n", " 0.000000\n", " 0.000000\n", - " P0\n", " \n", " \n", " 118\n", @@ -887,10 +869,8 @@ " 1\n", " 5\n", " H-1\n", - " P0\n", " 0.000000\n", " 0.000000\n", - " P0\n", " \n", " \n", " 119\n", @@ -898,27 +878,25 @@ " 1\n", " 5\n", " O-16\n", - " P0\n", " 0.000000\n", " 0.000000\n", - " P0\n", " \n", " \n", "\n", "" ], "text/plain": [ - " cell group in group out nuclide moment mean std. dev. moment\n", - "126 10002 1 1 H-1 P0 0.234115 0.003568 P0\n", - "127 10002 1 1 O-16 P0 1.563707 0.005953 P0\n", - "124 10002 1 2 H-1 P0 1.594129 0.002369 P0\n", - "125 10002 1 2 O-16 P0 0.285761 0.001676 P0\n", - "122 10002 1 3 H-1 P0 0.011089 0.000248 P0\n", - "123 10002 1 3 O-16 P0 0.000000 0.000000 P0\n", - "120 10002 1 4 H-1 P0 0.000000 0.000000 P0\n", - "121 10002 1 4 O-16 P0 0.000000 0.000000 P0\n", - "118 10002 1 5 H-1 P0 0.000000 0.000000 P0\n", - "119 10002 1 5 O-16 P0 0.000000 0.000000 P0" + " cell group in group out nuclide mean std. dev.\n", + "126 10002 1 1 H-1 0.234115 0.003568\n", + "127 10002 1 1 O-16 1.563707 0.005953\n", + "124 10002 1 2 H-1 1.594129 0.002369\n", + "125 10002 1 2 O-16 0.285761 0.001676\n", + "122 10002 1 3 H-1 0.011089 0.000248\n", + "123 10002 1 3 O-16 0.000000 0.000000\n", + "120 10002 1 4 H-1 0.000000 0.000000\n", + "121 10002 1 4 O-16 0.000000 0.000000\n", + "118 10002 1 5 H-1 0.000000 0.000000\n", + "119 10002 1 5 O-16 0.000000 0.000000" ] }, "execution_count": 19, @@ -1805,7 +1783,7 @@ "data": { "image/png": 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QJiJHAEOBeSJSCOyS3GKpXGezwaRJzc+lXLvWxpIlmb+bbaKXz6irs7XoeUol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\n+KP1PP8hsU6nNWku3KqsyVy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GugNni0h3YC/ge+9p2bHgi1I7oVMnz05tMxruRl5S4uHw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\nCqHJQSmlVAhNDkoppUL8Pzlt5uQccjZkAAAAAElFTkSuQmCC\n", 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 842c334a2..15bf06b24 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -726,8 +726,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: ae588276014a905ecc6e0967bf08288ecec5b550\n", - " Date/Time: 2016-05-12 21:04:33\n", + " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", + " Date/Time: 2016-05-13 09:04:22\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -814,20 +814,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.5500E-01 seconds\n", - " Reading cross sections = 1.1200E-01 seconds\n", - " Total time in simulation = 5.6386E+01 seconds\n", - " Time in transport only = 5.6351E+01 seconds\n", - " Time in inactive batches = 4.3700E+00 seconds\n", - " Time in active batches = 5.2016E+01 seconds\n", + " Total time for initialization = 5.4100E-01 seconds\n", + " Reading cross sections = 1.0500E-01 seconds\n", + " Total time in simulation = 5.1887E+01 seconds\n", + " Time in transport only = 5.1864E+01 seconds\n", + " Time in inactive batches = 3.9000E+00 seconds\n", + " Time in active batches = 4.7987E+01 seconds\n", " Time synchronizing fission bank = 5.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", + " Sampling source sites = 1.0000E-03 seconds\n", + " SEND/RECV source sites = 4.0000E-03 seconds\n", + " Time accumulating tallies = 2.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 5.6857E+01 seconds\n", - " Calculation Rate (inactive) = 5720.82 neutrons/second\n", - " Calculation Rate (active) = 1922.49 neutrons/second\n", + " Total time elapsed = 5.2448E+01 seconds\n", + " Calculation Rate (inactive) = 6410.26 neutrons/second\n", + " Calculation Rate (active) = 2083.90 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1101,7 +1101,7 @@ "cell_type": "code", "execution_count": 32, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ @@ -1558,7 +1558,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 43, @@ -1569,7 +1569,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 5b49005ec..eff0bde0a 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -90,6 +90,15 @@ class MGXS(object): tally_trigger : openmc.Trigger An (optional) tally precision trigger given to each tally used to compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section tallies : collections.OrderedDict OpenMC tallies needed to compute the multi-group cross section rxn_rate_tally : openmc.Tally @@ -115,8 +124,12 @@ class MGXS(object): sparse : bool Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data derived : bool Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store """ @@ -138,7 +151,9 @@ class MGXS(object): self._rxn_rate_tally = None self._xs_tally = None self._sparse = False + self._loaded_sp = False self._derived = False + self._hdf5_key = None self.name = name self.by_nuclide = by_nuclide @@ -213,6 +228,24 @@ class MGXS(object): def num_groups(self): return self.energy_groups.num_groups + @property + def scores(self): + return ['flux', self.rxn_type] + + @property + def filters(self): + group_edges = self.energy_groups.group_edges + energy_filter = openmc.Filter('energy', group_edges) + return [[energy_filter]] * len(self.scores) + + @property + def tally_keys(self): + return self.scores + + @property + def estimator(self): + return 'tracklength' + @property def tallies(self): """Construct the OpenMC tallies needed to compute the cross section.""" @@ -300,27 +333,20 @@ class MGXS(object): else: return 'sum' + @property + def loaded_sp(self): + return self._loaded_sp + @property def derived(self): return self._derived @property - def scores(self): - return ['flux', self.rxn_type] - - @property - def filters(self): - group_edges = self.energy_groups.group_edges - energy_filter = openmc.Filter('energy', group_edges) - return [[energy_filter]] * len(self.scores) - - @property - def tally_keys(self): - return self.scores - - @property - def estimator(self): - return 'tracklength' + def hdf5_key(self): + if self._hdf5_key is not None: + return self._hdf5_key + else: + return self._rxn_type @name.setter def name(self, name): @@ -644,9 +670,11 @@ class MGXS(object): filter_bins = [] # Clear any tallies previously loaded from a statepoint - self._tallies = None - self._xs_tally = None - self._rxn_rate_tally = None + if self.loaded_sp: + self._tallies = None + self._xs_tally = None + self._rxn_rate_tally = None + self._loaded_sp = False # Find, slice and store Tallies from StatePoint # The tally slicing is needed if tally merging was used @@ -659,6 +687,8 @@ class MGXS(object): sp_tally.sparse = self.sparse self.tallies[tally_type] = sp_tally + self._loaded_sp = True + def get_xs(self, groups='all', subdomains='all', nuclides='all', xs_type='macro', order_groups='increasing', value='mean', **kwargs): @@ -1253,8 +1283,8 @@ class MGXS(object): else: subdomain_group = domain_group - # Create a separate HDF5 group for the rxn type - rxn_group = subdomain_group.require_group(self.rxn_type) + # Create a separate HDF5 group for this cross section + rxn_group = subdomain_group.require_group(self.hdf5_key) # Create a separate HDF5 group for each nuclide for j, nuclide in enumerate(nuclides): @@ -1655,9 +1685,10 @@ class ScatterMatrixXS(MGXS): groups=None, by_nuclide=False, name=''): super(ScatterMatrixXS, self).__init__(domain, domain_type, groups, by_nuclide, name) - self._rxn_type = 'scatter matrix' + self._rxn_type = 'scatter' self._correction = 'P0' self._legendre_order = 0 + self._hdf5_key = 'scatter matrix' def __deepcopy__(self, memo): clone = super(ScatterMatrixXS, self).__deepcopy__(memo) @@ -1677,11 +1708,11 @@ class ScatterMatrixXS(MGXS): def scores(self): scores = ['flux'] - for moment in range(self.legendre_order+1): - scores.append('scatter-{}'.format(moment)) - if self.correction == 'P0' and self.legendre_order == 0: - scores.append('scatter-1') + scores += ['{}-0'.format(self.rxn_type), + '{}-1'.format(self.rxn_type)] + else: + scores += ['{}-P{}'.format(self.rxn_type, self.legendre_order)] return scores @@ -1690,20 +1721,14 @@ class ScatterMatrixXS(MGXS): group_edges = self.energy_groups.group_edges energy = openmc.Filter('energy', group_edges) energyout = openmc.Filter('energyout', group_edges) - filters = [[energy]] - - for moment in range(self.legendre_order+1): - filters.append([energy, energyout]) if self.correction == 'P0' and self.legendre_order == 0: - filters.append([energyout]) + filters = [[energy], [energy, energyout], [energyout]] + else: + filters = [[energy], [energy, energyout]] return filters - @property - def tally_keys(self): - return ['flux', 'scatter-0', 'scatter-1'] - @property def estimator(self): return 'analog' @@ -1715,21 +1740,17 @@ class ScatterMatrixXS(MGXS): # If using P0 correction subtract scatter-1 from the diagonal if self.correction == 'P0' and self.legendre_order == 0: - scatter_p1 = self.tallies['scatter-1'] - scatter_p1 = scatter_p1.get_slice(scores=[self.scores[-1]]) - energy_filter = self.tallies['scatter-0'].find_filter('energy') + scatter_p0 = self.tallies['{}-0'.format(self.rxn_type)] + scatter_p1 = self.tallies['{}-1'.format(self.rxn_type)] + energy_filter = scatter_p0.find_filter('energy') energy_filter = copy.deepcopy(energy_filter) scatter_p1 = scatter_p1.diagonalize_filter(energy_filter) - self._rxn_rate_tally = self.tallies['scatter-0'] - scatter_p1 + self._rxn_rate_tally = scatter_p0 - scatter_p1 - # Merge all scattering moments into a single reaction rate Tally + # Extract scattering moment reaction rate Tally else: - rxn_rate_tally = self.tallies['scatter-0'] - for moment in range(1, self.legendre_order+1): - scatter_pn = self.tallies['scatter-{}'.format(moment)] - rxn_rate_tally = rxn_rate_tally.merge(scatter_pn) - - self._rxn_rate_tally = rxn_rate_tally + tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) + self._rxn_rate_tally = self.tallies[tally_key] self._rxn_rate_tally.sparse = self.sparse @@ -1760,6 +1781,44 @@ class ScatterMatrixXS(MGXS): self._legendre_order = legendre_order + def load_from_statepoint(self, statepoint): + """Extracts tallies in an OpenMC StatePoint with the data needed to + compute multi-group cross sections. + + This method is needed to compute cross section data from tallies + in an OpenMC StatePoint object. + + NOTE: The statepoint must first be linked with an OpenMC Summary object. + + Parameters + ---------- + statepoint : openmc.StatePoint + An OpenMC StatePoint object with tally data + + Raises + ------ + ValueError + When this method is called with a statepoint that has not been + linked with a summary object. + + """ + + # Clear any tallies previously loaded from a statepoint + if self.loaded_sp: + self._tallies = None + self._xs_tally = None + self._rxn_rate_tally = None + self._loaded_sp = False + + # Expand scores to match the format in the statepoint + # e.g., "scatter-P2" -> "scatter-0", "scatter-1", "scatter-2" + if self.legendre_order != 0: + tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) + self.tallies[tally_key].scores = \ + [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] + + super(ScatterMatrixXS, self).load_from_statepoint(statepoint) + def get_slice(self, nuclides=[], in_groups=[], out_groups=[], legendre_order='same'): """Build a sliced ScatterMatrix for the specified nuclides and @@ -1808,8 +1867,12 @@ class ScatterMatrixXS(MGXS): self.legendre_order, equality=True) slice_xs.legendre_order = legendre_order - for moment in range(legendre_order+1, self.legendre_order+1): - del slice_xs.tallies['scatter-{}'.format(moment)] + # Slice the scattering tally + tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) + expand_scores = \ + [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] + slice_xs.tallies[tally_key] = \ + slice_xs.tallies[tally_key].get_slice(scores=expand_scores) # Slice outgoing energy groups if needed if len(out_groups) != 0: @@ -2034,14 +2097,16 @@ class ScatterMatrixXS(MGXS): groups, nuclides, xs_type, distribcell_paths) # Add a moment column to dataframe - moments = np.array(['P{}'.format(i) for i in range(self.legendre_order+1)]) - moments = np.tile(moments, df.shape[0] / moments.size) - df['moment'] = moments + if self.legendre_order > 0: + # Insert a column corresponding to the Legendre moments + moments = ['P{}'.format(i) for i in range(self.legendre_order+1)] + moments = np.tile(moments, df.shape[0] / len(moments)) + df['moment'] = moments - # Place the moment column before the mean column - mean_index = df.columns.get_loc('mean') - columns = df.columns.tolist() - df = df[columns[:mean_index] + ['moment'] + columns[mean_index:]] + # Place the moment column before the mean column + mean_index = df.columns.get_loc('mean') + columns = df.columns.tolist() + df = df[columns[:mean_index] + ['moment'] + columns[mean_index:-2]] # Select rows corresponding to requested scattering moment if moment != 'all': @@ -2049,7 +2114,7 @@ class ScatterMatrixXS(MGXS): cv.check_greater_than('moment', moment, 0, equality=True) cv.check_less_than( 'moment', moment, self.legendre_order, equality=True) - df = df.iloc[moment:self.legendre_order:] + df = df[df['moment'] == 'P{}'.format(moment)] return df @@ -2173,19 +2238,8 @@ class NuScatterMatrixXS(ScatterMatrixXS): groups=None, by_nuclide=False, name=''): super(NuScatterMatrixXS, self).__init__(domain, domain_type, groups, by_nuclide, name) - self._rxn_type = 'nu-scatter matrix' - - @property - def scores(self): - scores = ['flux'] - - for moment in range(self.legendre_order+1): - scores.append('nu-scatter-{}'.format(moment)) - - if self.correction == 'P0' and self.legendre_order == 0: - scores.append('nu-scatter-1') - - return scores + self._rxn_type = 'nu-scatter' + self._hdf5_key = 'nu-scatter matrix' class Chi(MGXS): diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 89e4dbb3e..8296aca11 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,49 +1,49 @@ material group in nuclide mean std. dev. 0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. -0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev. moment -0 1 1 1 total P0 0.345503 0.021465 P0 material group out nuclide mean std. dev. +0 1 1 total 0.076425 0.003691 material group in group out nuclide mean std. dev. +0 1 1 1 total 0.345503 0.021465 material group out nuclide mean std. dev. 0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 2 1 1 total P0 0.241262 0.00841 P0 material group out nuclide mean std. dev. +0 2 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 2 1 1 total 0.241262 0.00841 material group out nuclide mean std. dev. 0 2 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 3 1 1 total P0 0.393462 0.033646 P0 material group out nuclide mean std. dev. +0 3 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 3 1 1 total 0.393462 0.033646 material group out nuclide mean std. dev. 0 3 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 4 1 1 total P0 0.371473 0.071226 P0 material group out nuclide mean std. dev. +0 4 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 4 1 1 total 0.371473 0.071226 material group out nuclide mean std. dev. 0 4 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 5 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 5 1 1 total 0.0 0.0 material group out nuclide mean std. dev. 0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 6 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 6 1 1 total 0.0 0.0 material group out nuclide mean std. dev. 0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 7 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 7 1 1 total 0.0 0.0 material group out nuclide mean std. dev. 0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 8 1 1 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 8 1 1 total 0.0 0.0 material group out nuclide mean std. dev. 0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 9 1 1 total P0 0.600536 0.748875 P0 material group out nuclide mean std. dev. +0 9 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 9 1 1 total 0.600536 0.748875 material group out nuclide mean std. dev. 0 9 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 10 1 1 total P0 0.235515 0.613974 P0 material group out nuclide mean std. dev. +0 10 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 10 1 1 total 0.235515 0.613974 material group out nuclide mean std. dev. 0 10 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 11 1 1 total P0 0.491857 0.715554 P0 material group out nuclide mean std. dev. +0 11 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 11 1 1 total 0.491857 0.715554 material group out nuclide mean std. dev. 0 11 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -0 12 1 1 total P0 0.723265 0.808231 P0 material group out nuclide mean std. dev. +0 12 1 total 0.0 0.0 material group in group out nuclide mean std. dev. +0 12 1 1 total 0.723265 0.808231 material group out nuclide mean std. dev. 0 12 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index 014eabfa5..0d5c7c7b4 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,5 +1,5 @@ avg(distribcell) group in nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide moment mean std. dev. moment -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 0.695166 0.510606 P0 avg(distribcell) group out nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.695166 0.510606 avg(distribcell) group out nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 0ad8e04aa..7361c60be 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -2,120 +2,120 @@ 1 1 1 total 0.372745 0.024269 0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. 1 1 1 total 0.021789 0.001182 -0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean std. dev. moment -3 1 1 1 total P0 0.337245 0.023015 P0 -2 1 1 2 total P0 0.001559 0.000510 P0 -1 1 2 1 total P0 0.000000 0.000000 P0 -0 1 2 2 total P0 0.422051 0.021617 P0 material group out nuclide mean std. dev. +0 1 2 total 0.714077 0.040552 material group in group out nuclide mean std. dev. +3 1 1 1 total 0.337245 0.023015 +2 1 1 2 total 0.001559 0.000510 +1 1 2 1 total 0.000000 0.000000 +0 1 2 2 total 0.422051 0.021617 material group out nuclide mean std. dev. 1 1 1 total 1.0 0.055333 0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev. 1 2 1 total 0.237254 0.008184 0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. 1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 2 1 1 total P0 0.237254 0.008184 P0 -2 2 1 2 total P0 0.000000 0.000000 P0 -1 2 2 1 total P0 0.000000 0.000000 P0 -0 2 2 2 total P0 0.285930 0.048796 P0 material group out nuclide mean std. dev. +0 2 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 2 1 1 total 0.237254 0.008184 +2 2 1 2 total 0.000000 0.000000 +1 2 2 1 total 0.000000 0.000000 +0 2 2 2 total 0.285930 0.048796 material group out nuclide mean std. dev. 1 2 1 total 0.0 0.0 0 2 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 3 1 total 0.286906 0.027401 0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. 1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 3 1 1 total P0 0.259937 0.026115 P0 -2 3 1 2 total P0 0.026187 0.001665 P0 -1 3 2 1 total P0 0.000000 0.000000 P0 -0 3 2 2 total P0 1.359521 0.258505 P0 material group out nuclide mean std. dev. +0 3 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 3 1 1 total 0.259937 0.026115 +2 3 1 2 total 0.026187 0.001665 +1 3 2 1 total 0.000000 0.000000 +0 3 2 2 total 1.359521 0.258505 material group out nuclide mean std. dev. 1 3 1 total 0.0 0.0 0 3 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 4 1 total 0.242447 0.061031 0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. 1 4 1 total 0.0 0.0 -0 4 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 4 1 1 total P0 0.217930 0.058565 P0 -2 4 1 2 total P0 0.023662 0.003083 P0 -1 4 2 1 total P0 0.000000 0.000000 P0 -0 4 2 2 total P0 1.215074 0.381025 P0 material group out nuclide mean std. dev. +0 4 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 4 1 1 total 0.217930 0.058565 +2 4 1 2 total 0.023662 0.003083 +1 4 2 1 total 0.000000 0.000000 +0 4 2 2 total 1.215074 0.381025 material group out nuclide mean std. dev. 1 4 1 total 0.0 0.0 0 4 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 5 1 total 0.0 0.0 0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 5 1 1 total P0 0.0 0.0 P0 -2 5 1 2 total P0 0.0 0.0 P0 -1 5 2 1 total P0 0.0 0.0 P0 -0 5 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 5 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 5 1 1 total 0.0 0.0 +2 5 1 2 total 0.0 0.0 +1 5 2 1 total 0.0 0.0 +0 5 2 2 total 0.0 0.0 material group out nuclide mean std. dev. 1 5 1 total 0.0 0.0 0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 6 1 total 0.0 0.0 0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 6 1 1 total P0 0.0 0.0 P0 -2 6 1 2 total P0 0.0 0.0 P0 -1 6 2 1 total P0 0.0 0.0 P0 -0 6 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 6 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 6 1 1 total 0.0 0.0 +2 6 1 2 total 0.0 0.0 +1 6 2 1 total 0.0 0.0 +0 6 2 2 total 0.0 0.0 material group out nuclide mean std. dev. 1 6 1 total 0.0 0.0 0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 7 1 total 0.0 0.0 0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 7 1 1 total P0 0.0 0.0 P0 -2 7 1 2 total P0 0.0 0.0 P0 -1 7 2 1 total P0 0.0 0.0 P0 -0 7 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 7 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 7 1 1 total 0.0 0.0 +2 7 1 2 total 0.0 0.0 +1 7 2 1 total 0.0 0.0 +0 7 2 2 total 0.0 0.0 material group out nuclide mean std. dev. 1 7 1 total 0.0 0.0 0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 8 1 total 0.0 0.0 0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 8 1 1 total P0 0.0 0.0 P0 -2 8 1 2 total P0 0.0 0.0 P0 -1 8 2 1 total P0 0.0 0.0 P0 -0 8 2 2 total P0 0.0 0.0 P0 material group out nuclide mean std. dev. +0 8 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 8 1 1 total 0.0 0.0 +2 8 1 2 total 0.0 0.0 +1 8 2 1 total 0.0 0.0 +0 8 2 2 total 0.0 0.0 material group out nuclide mean std. dev. 1 8 1 total 0.0 0.0 0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 9 1 total 0.600536 0.748875 0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. 1 9 1 total 0.0 0.0 -0 9 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 9 1 1 total P0 0.600536 0.748875 P0 -2 9 1 2 total P0 0.000000 0.000000 P0 -1 9 2 1 total P0 0.000000 0.000000 P0 -0 9 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +0 9 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 9 1 1 total 0.600536 0.748875 +2 9 1 2 total 0.000000 0.000000 +1 9 2 1 total 0.000000 0.000000 +0 9 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. 1 9 1 total 0.0 0.0 0 9 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 10 1 total 0.235515 0.613974 0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. 1 10 1 total 0.0 0.0 -0 10 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 10 1 1 total P0 0.235515 0.613974 P0 -2 10 1 2 total P0 0.000000 0.000000 P0 -1 10 2 1 total P0 0.000000 0.000000 P0 -0 10 2 2 total P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +0 10 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 10 1 1 total 0.235515 0.613974 +2 10 1 2 total 0.000000 0.000000 +1 10 2 1 total 0.000000 0.000000 +0 10 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. 1 10 1 total 0.0 0.0 0 10 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 11 1 total 0.186324 0.632129 0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. 1 11 1 total 0.0 0.0 -0 11 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 11 1 1 total P0 0.154449 0.597686 P0 -2 11 1 2 total P0 0.031875 0.045078 P0 -1 11 2 1 total P0 0.000000 0.000000 P0 -0 11 2 2 total P0 0.903085 1.532144 P0 material group out nuclide mean std. dev. +0 11 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 11 1 1 total 0.154449 0.597686 +2 11 1 2 total 0.031875 0.045078 +1 11 2 1 total 0.000000 0.000000 +0 11 2 2 total 0.903085 1.532144 material group out nuclide mean std. dev. 1 11 1 total 0.0 0.0 0 11 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 12 1 total 0.213292 0.271444 0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. 1 12 1 total 0.0 0.0 -0 12 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -3 12 1 1 total P0 0.186052 0.257633 P0 -2 12 1 2 total P0 0.027240 0.029555 P0 -1 12 2 1 total P0 0.000000 0.000000 P0 -0 12 2 2 total P0 1.357118 2.089846 P0 material group out nuclide mean std. dev. +0 12 2 total 0.0 0.0 material group in group out nuclide mean std. dev. +3 12 1 1 total 0.186052 0.257633 +2 12 1 2 total 0.027240 0.029555 +1 12 2 1 total 0.000000 0.000000 +0 12 2 2 total 1.357118 2.089846 material group out nuclide mean std. dev. 1 12 1 total 0.0 0.0 0 12 2 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index 9cef6fdd8..b0d62ebd0 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -134,143 +134,143 @@ 30 1 2 Sm-152 0.000000e+00 0.000000e+00 31 1 2 Eu-153 0.000000e+00 0.000000e+00 32 1 2 Gd-155 0.000000e+00 0.000000e+00 -33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide moment mean std. dev. moment -102 1 1 1 U-234 P0 0.000000 0.000000 P0 -103 1 1 1 U-235 P0 0.003226 0.001139 P0 -104 1 1 1 U-236 P0 0.001697 0.000923 P0 -105 1 1 1 U-238 P0 0.194468 0.013279 P0 -106 1 1 1 Np-237 P0 0.000000 0.000000 P0 -107 1 1 1 Pu-238 P0 0.000000 0.000000 P0 -108 1 1 1 Pu-239 P0 0.001005 0.000477 P0 -109 1 1 1 Pu-240 P0 0.001307 0.000295 P0 -110 1 1 1 Pu-241 P0 0.000344 0.000244 P0 -111 1 1 1 Pu-242 P0 0.000000 0.000000 P0 -112 1 1 1 Am-241 P0 0.000000 0.000000 P0 -113 1 1 1 Am-242m P0 0.000000 0.000000 P0 -114 1 1 1 Am-243 P0 0.000000 0.000000 P0 -115 1 1 1 Cm-242 P0 0.000000 0.000000 P0 -116 1 1 1 Cm-243 P0 0.000000 0.000000 P0 -117 1 1 1 Cm-244 P0 0.000000 0.000000 P0 -118 1 1 1 Cm-245 P0 0.000000 0.000000 P0 -119 1 1 1 Mo-95 P0 0.000000 0.000000 P0 -120 1 1 1 Tc-99 P0 0.000000 0.000000 P0 -121 1 1 1 Ru-101 P0 0.000238 0.000254 P0 -122 1 1 1 Ru-103 P0 0.000002 0.000243 P0 -123 1 1 1 Ag-109 P0 0.000000 0.000000 P0 -124 1 1 1 Xe-135 P0 0.000000 0.000000 P0 -125 1 1 1 Cs-133 P0 0.000000 0.000000 P0 -126 1 1 1 Nd-143 P0 0.000447 0.000292 P0 -127 1 1 1 Nd-145 P0 0.000564 0.000294 P0 -128 1 1 1 Sm-147 P0 0.000000 0.000000 P0 -129 1 1 1 Sm-149 P0 0.000000 0.000000 P0 -130 1 1 1 Sm-150 P0 0.000299 0.000238 P0 -131 1 1 1 Sm-151 P0 0.000000 0.000000 P0 -132 1 1 1 Sm-152 P0 0.000492 0.000352 P0 -133 1 1 1 Eu-153 P0 0.000000 0.000000 P0 -134 1 1 1 Gd-155 P0 0.000000 0.000000 P0 -135 1 1 1 O-16 P0 0.133156 0.009821 P0 -68 1 1 2 U-234 P0 0.000000 0.000000 P0 -69 1 1 2 U-235 P0 0.000000 0.000000 P0 -70 1 1 2 U-236 P0 0.000000 0.000000 P0 -71 1 1 2 U-238 P0 0.000173 0.000173 P0 -72 1 1 2 Np-237 P0 0.000000 0.000000 P0 -73 1 1 2 Pu-238 P0 0.000000 0.000000 P0 -74 1 1 2 Pu-239 P0 0.000000 0.000000 P0 -75 1 1 2 Pu-240 P0 0.000000 0.000000 P0 -76 1 1 2 Pu-241 P0 0.000000 0.000000 P0 -77 1 1 2 Pu-242 P0 0.000000 0.000000 P0 -78 1 1 2 Am-241 P0 0.000000 0.000000 P0 -79 1 1 2 Am-242m P0 0.000000 0.000000 P0 -80 1 1 2 Am-243 P0 0.000000 0.000000 P0 -81 1 1 2 Cm-242 P0 0.000000 0.000000 P0 -82 1 1 2 Cm-243 P0 0.000000 0.000000 P0 -83 1 1 2 Cm-244 P0 0.000000 0.000000 P0 -84 1 1 2 Cm-245 P0 0.000000 0.000000 P0 -85 1 1 2 Mo-95 P0 0.000000 0.000000 P0 -86 1 1 2 Tc-99 P0 0.000000 0.000000 P0 -87 1 1 2 Ru-101 P0 0.000000 0.000000 P0 -88 1 1 2 Ru-103 P0 0.000000 0.000000 P0 -89 1 1 2 Ag-109 P0 0.000000 0.000000 P0 -90 1 1 2 Xe-135 P0 0.000000 0.000000 P0 -91 1 1 2 Cs-133 P0 0.000000 0.000000 P0 -92 1 1 2 Nd-143 P0 0.000000 0.000000 P0 -93 1 1 2 Nd-145 P0 0.000000 0.000000 P0 -94 1 1 2 Sm-147 P0 0.000000 0.000000 P0 -95 1 1 2 Sm-149 P0 0.000000 0.000000 P0 -96 1 1 2 Sm-150 P0 0.000000 0.000000 P0 -97 1 1 2 Sm-151 P0 0.000000 0.000000 P0 -98 1 1 2 Sm-152 P0 0.000000 0.000000 P0 -99 1 1 2 Eu-153 P0 0.000000 0.000000 P0 -100 1 1 2 Gd-155 P0 0.000000 0.000000 P0 -101 1 1 2 O-16 P0 0.001386 0.000446 P0 -34 1 2 1 U-234 P0 0.000000 0.000000 P0 -35 1 2 1 U-235 P0 0.000000 0.000000 P0 -36 1 2 1 U-236 P0 0.000000 0.000000 P0 -37 1 2 1 U-238 P0 0.000000 0.000000 P0 -38 1 2 1 Np-237 P0 0.000000 0.000000 P0 -39 1 2 1 Pu-238 P0 0.000000 0.000000 P0 -40 1 2 1 Pu-239 P0 0.000000 0.000000 P0 -41 1 2 1 Pu-240 P0 0.000000 0.000000 P0 -42 1 2 1 Pu-241 P0 0.000000 0.000000 P0 -43 1 2 1 Pu-242 P0 0.000000 0.000000 P0 -44 1 2 1 Am-241 P0 0.000000 0.000000 P0 -45 1 2 1 Am-242m P0 0.000000 0.000000 P0 -46 1 2 1 Am-243 P0 0.000000 0.000000 P0 -47 1 2 1 Cm-242 P0 0.000000 0.000000 P0 -48 1 2 1 Cm-243 P0 0.000000 0.000000 P0 -49 1 2 1 Cm-244 P0 0.000000 0.000000 P0 -50 1 2 1 Cm-245 P0 0.000000 0.000000 P0 -51 1 2 1 Mo-95 P0 0.000000 0.000000 P0 -52 1 2 1 Tc-99 P0 0.000000 0.000000 P0 -53 1 2 1 Ru-101 P0 0.000000 0.000000 P0 -54 1 2 1 Ru-103 P0 0.000000 0.000000 P0 -55 1 2 1 Ag-109 P0 0.000000 0.000000 P0 -56 1 2 1 Xe-135 P0 0.000000 0.000000 P0 -57 1 2 1 Cs-133 P0 0.000000 0.000000 P0 -58 1 2 1 Nd-143 P0 0.000000 0.000000 P0 -59 1 2 1 Nd-145 P0 0.000000 0.000000 P0 -60 1 2 1 Sm-147 P0 0.000000 0.000000 P0 -61 1 2 1 Sm-149 P0 0.000000 0.000000 P0 -62 1 2 1 Sm-150 P0 0.000000 0.000000 P0 -63 1 2 1 Sm-151 P0 0.000000 0.000000 P0 -64 1 2 1 Sm-152 P0 0.000000 0.000000 P0 -65 1 2 1 Eu-153 P0 0.000000 0.000000 P0 -66 1 2 1 Gd-155 P0 0.000000 0.000000 P0 -67 1 2 1 O-16 P0 0.000000 0.000000 P0 -0 1 2 2 U-234 P0 0.000000 0.000000 P0 -1 1 2 2 U-235 P0 0.003889 0.003962 P0 -2 1 2 2 U-236 P0 0.001501 0.002037 P0 -3 1 2 2 U-238 P0 0.219715 0.025984 P0 -4 1 2 2 Np-237 P0 0.000000 0.000000 P0 -5 1 2 2 Pu-238 P0 0.000000 0.000000 P0 -6 1 2 2 Pu-239 P0 0.000000 0.000000 P0 -7 1 2 2 Pu-240 P0 0.000000 0.000000 P0 -8 1 2 2 Pu-241 P0 0.000000 0.000000 P0 -9 1 2 2 Pu-242 P0 0.000000 0.000000 P0 -10 1 2 2 Am-241 P0 0.000000 0.000000 P0 -11 1 2 2 Am-242m P0 0.000000 0.000000 P0 -12 1 2 2 Am-243 P0 0.000000 0.000000 P0 -13 1 2 2 Cm-242 P0 0.000000 0.000000 P0 -14 1 2 2 Cm-243 P0 0.000000 0.000000 P0 -15 1 2 2 Cm-244 P0 0.000000 0.000000 P0 -16 1 2 2 Cm-245 P0 0.000000 0.000000 P0 -17 1 2 2 Mo-95 P0 0.000000 0.000000 P0 -18 1 2 2 Tc-99 P0 0.000000 0.000000 P0 -19 1 2 2 Ru-101 P0 0.000000 0.000000 P0 -20 1 2 2 Ru-103 P0 0.000000 0.000000 P0 -21 1 2 2 Ag-109 P0 0.000000 0.000000 P0 -22 1 2 2 Xe-135 P0 0.000000 0.000000 P0 -23 1 2 2 Cs-133 P0 0.000000 0.000000 P0 -24 1 2 2 Nd-143 P0 0.000000 0.000000 P0 -25 1 2 2 Nd-145 P0 0.000000 0.000000 P0 -26 1 2 2 Sm-147 P0 0.000000 0.000000 P0 -27 1 2 2 Sm-149 P0 0.000000 0.000000 P0 -28 1 2 2 Sm-150 P0 0.000000 0.000000 P0 -29 1 2 2 Sm-151 P0 0.000000 0.000000 P0 -30 1 2 2 Sm-152 P0 0.000000 0.000000 P0 -31 1 2 2 Eu-153 P0 0.000000 0.000000 P0 -32 1 2 2 Gd-155 P0 0.000000 0.000000 P0 -33 1 2 2 O-16 P0 0.196946 0.014729 P0 material group out nuclide mean std. dev. +33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide mean std. dev. +102 1 1 1 U-234 0.000000 0.000000 +103 1 1 1 U-235 0.003226 0.001139 +104 1 1 1 U-236 0.001697 0.000923 +105 1 1 1 U-238 0.194468 0.013279 +106 1 1 1 Np-237 0.000000 0.000000 +107 1 1 1 Pu-238 0.000000 0.000000 +108 1 1 1 Pu-239 0.001005 0.000477 +109 1 1 1 Pu-240 0.001307 0.000295 +110 1 1 1 Pu-241 0.000344 0.000244 +111 1 1 1 Pu-242 0.000000 0.000000 +112 1 1 1 Am-241 0.000000 0.000000 +113 1 1 1 Am-242m 0.000000 0.000000 +114 1 1 1 Am-243 0.000000 0.000000 +115 1 1 1 Cm-242 0.000000 0.000000 +116 1 1 1 Cm-243 0.000000 0.000000 +117 1 1 1 Cm-244 0.000000 0.000000 +118 1 1 1 Cm-245 0.000000 0.000000 +119 1 1 1 Mo-95 0.000000 0.000000 +120 1 1 1 Tc-99 0.000000 0.000000 +121 1 1 1 Ru-101 0.000238 0.000254 +122 1 1 1 Ru-103 0.000002 0.000243 +123 1 1 1 Ag-109 0.000000 0.000000 +124 1 1 1 Xe-135 0.000000 0.000000 +125 1 1 1 Cs-133 0.000000 0.000000 +126 1 1 1 Nd-143 0.000447 0.000292 +127 1 1 1 Nd-145 0.000564 0.000294 +128 1 1 1 Sm-147 0.000000 0.000000 +129 1 1 1 Sm-149 0.000000 0.000000 +130 1 1 1 Sm-150 0.000299 0.000238 +131 1 1 1 Sm-151 0.000000 0.000000 +132 1 1 1 Sm-152 0.000492 0.000352 +133 1 1 1 Eu-153 0.000000 0.000000 +134 1 1 1 Gd-155 0.000000 0.000000 +135 1 1 1 O-16 0.133156 0.009821 +68 1 1 2 U-234 0.000000 0.000000 +69 1 1 2 U-235 0.000000 0.000000 +70 1 1 2 U-236 0.000000 0.000000 +71 1 1 2 U-238 0.000173 0.000173 +72 1 1 2 Np-237 0.000000 0.000000 +73 1 1 2 Pu-238 0.000000 0.000000 +74 1 1 2 Pu-239 0.000000 0.000000 +75 1 1 2 Pu-240 0.000000 0.000000 +76 1 1 2 Pu-241 0.000000 0.000000 +77 1 1 2 Pu-242 0.000000 0.000000 +78 1 1 2 Am-241 0.000000 0.000000 +79 1 1 2 Am-242m 0.000000 0.000000 +80 1 1 2 Am-243 0.000000 0.000000 +81 1 1 2 Cm-242 0.000000 0.000000 +82 1 1 2 Cm-243 0.000000 0.000000 +83 1 1 2 Cm-244 0.000000 0.000000 +84 1 1 2 Cm-245 0.000000 0.000000 +85 1 1 2 Mo-95 0.000000 0.000000 +86 1 1 2 Tc-99 0.000000 0.000000 +87 1 1 2 Ru-101 0.000000 0.000000 +88 1 1 2 Ru-103 0.000000 0.000000 +89 1 1 2 Ag-109 0.000000 0.000000 +90 1 1 2 Xe-135 0.000000 0.000000 +91 1 1 2 Cs-133 0.000000 0.000000 +92 1 1 2 Nd-143 0.000000 0.000000 +93 1 1 2 Nd-145 0.000000 0.000000 +94 1 1 2 Sm-147 0.000000 0.000000 +95 1 1 2 Sm-149 0.000000 0.000000 +96 1 1 2 Sm-150 0.000000 0.000000 +97 1 1 2 Sm-151 0.000000 0.000000 +98 1 1 2 Sm-152 0.000000 0.000000 +99 1 1 2 Eu-153 0.000000 0.000000 +100 1 1 2 Gd-155 0.000000 0.000000 +101 1 1 2 O-16 0.001386 0.000446 +34 1 2 1 U-234 0.000000 0.000000 +35 1 2 1 U-235 0.000000 0.000000 +36 1 2 1 U-236 0.000000 0.000000 +37 1 2 1 U-238 0.000000 0.000000 +38 1 2 1 Np-237 0.000000 0.000000 +39 1 2 1 Pu-238 0.000000 0.000000 +40 1 2 1 Pu-239 0.000000 0.000000 +41 1 2 1 Pu-240 0.000000 0.000000 +42 1 2 1 Pu-241 0.000000 0.000000 +43 1 2 1 Pu-242 0.000000 0.000000 +44 1 2 1 Am-241 0.000000 0.000000 +45 1 2 1 Am-242m 0.000000 0.000000 +46 1 2 1 Am-243 0.000000 0.000000 +47 1 2 1 Cm-242 0.000000 0.000000 +48 1 2 1 Cm-243 0.000000 0.000000 +49 1 2 1 Cm-244 0.000000 0.000000 +50 1 2 1 Cm-245 0.000000 0.000000 +51 1 2 1 Mo-95 0.000000 0.000000 +52 1 2 1 Tc-99 0.000000 0.000000 +53 1 2 1 Ru-101 0.000000 0.000000 +54 1 2 1 Ru-103 0.000000 0.000000 +55 1 2 1 Ag-109 0.000000 0.000000 +56 1 2 1 Xe-135 0.000000 0.000000 +57 1 2 1 Cs-133 0.000000 0.000000 +58 1 2 1 Nd-143 0.000000 0.000000 +59 1 2 1 Nd-145 0.000000 0.000000 +60 1 2 1 Sm-147 0.000000 0.000000 +61 1 2 1 Sm-149 0.000000 0.000000 +62 1 2 1 Sm-150 0.000000 0.000000 +63 1 2 1 Sm-151 0.000000 0.000000 +64 1 2 1 Sm-152 0.000000 0.000000 +65 1 2 1 Eu-153 0.000000 0.000000 +66 1 2 1 Gd-155 0.000000 0.000000 +67 1 2 1 O-16 0.000000 0.000000 +0 1 2 2 U-234 0.000000 0.000000 +1 1 2 2 U-235 0.003889 0.003962 +2 1 2 2 U-236 0.001501 0.002037 +3 1 2 2 U-238 0.219715 0.025984 +4 1 2 2 Np-237 0.000000 0.000000 +5 1 2 2 Pu-238 0.000000 0.000000 +6 1 2 2 Pu-239 0.000000 0.000000 +7 1 2 2 Pu-240 0.000000 0.000000 +8 1 2 2 Pu-241 0.000000 0.000000 +9 1 2 2 Pu-242 0.000000 0.000000 +10 1 2 2 Am-241 0.000000 0.000000 +11 1 2 2 Am-242m 0.000000 0.000000 +12 1 2 2 Am-243 0.000000 0.000000 +13 1 2 2 Cm-242 0.000000 0.000000 +14 1 2 2 Cm-243 0.000000 0.000000 +15 1 2 2 Cm-244 0.000000 0.000000 +16 1 2 2 Cm-245 0.000000 0.000000 +17 1 2 2 Mo-95 0.000000 0.000000 +18 1 2 2 Tc-99 0.000000 0.000000 +19 1 2 2 Ru-101 0.000000 0.000000 +20 1 2 2 Ru-103 0.000000 0.000000 +21 1 2 2 Ag-109 0.000000 0.000000 +22 1 2 2 Xe-135 0.000000 0.000000 +23 1 2 2 Cs-133 0.000000 0.000000 +24 1 2 2 Nd-143 0.000000 0.000000 +25 1 2 2 Nd-145 0.000000 0.000000 +26 1 2 2 Sm-147 0.000000 0.000000 +27 1 2 2 Sm-149 0.000000 0.000000 +28 1 2 2 Sm-150 0.000000 0.000000 +29 1 2 2 Sm-151 0.000000 0.000000 +30 1 2 2 Sm-152 0.000000 0.000000 +31 1 2 2 Eu-153 0.000000 0.000000 +32 1 2 2 Gd-155 0.000000 0.000000 +33 1 2 2 O-16 0.196946 0.014729 material group out nuclide mean std. dev. 34 1 1 U-234 0.0 0.000000 35 1 1 U-235 1.0 0.066362 36 1 1 U-236 0.0 0.000000 @@ -358,27 +358,27 @@ 1 2 2 Zr-91 0.0 0.0 2 2 2 Zr-92 0.0 0.0 3 2 2 Zr-94 0.0 0.0 -4 2 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -15 2 1 1 Zr-90 P0 0.104734 0.008915 P0 -16 2 1 1 Zr-91 P0 0.036155 0.003735 P0 -17 2 1 1 Zr-92 P0 0.042422 0.003029 P0 -18 2 1 1 Zr-94 P0 0.046148 0.006251 P0 -19 2 1 1 Zr-96 P0 0.007794 0.001536 P0 -10 2 1 2 Zr-90 P0 0.000000 0.000000 P0 -11 2 1 2 Zr-91 P0 0.000000 0.000000 P0 -12 2 1 2 Zr-92 P0 0.000000 0.000000 P0 -13 2 1 2 Zr-94 P0 0.000000 0.000000 P0 -14 2 1 2 Zr-96 P0 0.000000 0.000000 P0 -5 2 2 1 Zr-90 P0 0.000000 0.000000 P0 -6 2 2 1 Zr-91 P0 0.000000 0.000000 P0 -7 2 2 1 Zr-92 P0 0.000000 0.000000 P0 -8 2 2 1 Zr-94 P0 0.000000 0.000000 P0 -9 2 2 1 Zr-96 P0 0.000000 0.000000 P0 -0 2 2 2 Zr-90 P0 0.121688 0.034934 P0 -1 2 2 2 Zr-91 P0 0.061792 0.024317 P0 -2 2 2 2 Zr-92 P0 0.041633 0.016323 P0 -3 2 2 2 Zr-94 P0 0.060818 0.021483 P0 -4 2 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +4 2 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. +15 2 1 1 Zr-90 0.104734 0.008915 +16 2 1 1 Zr-91 0.036155 0.003735 +17 2 1 1 Zr-92 0.042422 0.003029 +18 2 1 1 Zr-94 0.046148 0.006251 +19 2 1 1 Zr-96 0.007794 0.001536 +10 2 1 2 Zr-90 0.000000 0.000000 +11 2 1 2 Zr-91 0.000000 0.000000 +12 2 1 2 Zr-92 0.000000 0.000000 +13 2 1 2 Zr-94 0.000000 0.000000 +14 2 1 2 Zr-96 0.000000 0.000000 +5 2 2 1 Zr-90 0.000000 0.000000 +6 2 2 1 Zr-91 0.000000 0.000000 +7 2 2 1 Zr-92 0.000000 0.000000 +8 2 2 1 Zr-94 0.000000 0.000000 +9 2 2 1 Zr-96 0.000000 0.000000 +0 2 2 2 Zr-90 0.121688 0.034934 +1 2 2 2 Zr-91 0.061792 0.024317 +2 2 2 2 Zr-92 0.041633 0.016323 +3 2 2 2 Zr-94 0.060818 0.021483 +4 2 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. 5 2 1 Zr-90 0.0 0.0 6 2 1 Zr-91 0.0 0.0 7 2 1 Zr-92 0.0 0.0 @@ -404,23 +404,23 @@ 0 3 2 H-1 0.0 0.0 1 3 2 O-16 0.0 0.0 2 3 2 B-10 0.0 0.0 -3 3 2 B-11 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -12 3 1 1 H-1 P0 0.181306 0.022102 P0 -13 3 1 1 O-16 P0 0.078631 0.005044 P0 -14 3 1 1 B-10 P0 0.000000 0.000000 P0 -15 3 1 1 B-11 P0 0.000000 0.000000 P0 -8 3 1 2 H-1 P0 0.025666 0.001582 P0 -9 3 1 2 O-16 P0 0.000521 0.000131 P0 -10 3 1 2 B-10 P0 0.000000 0.000000 P0 -11 3 1 2 B-11 P0 0.000000 0.000000 P0 -4 3 2 1 H-1 P0 0.000000 0.000000 P0 -5 3 2 1 O-16 P0 0.000000 0.000000 P0 -6 3 2 1 B-10 P0 0.000000 0.000000 P0 -7 3 2 1 B-11 P0 0.000000 0.000000 P0 -0 3 2 2 H-1 P0 1.273963 0.250623 P0 -1 3 2 2 O-16 P0 0.085363 0.014001 P0 -2 3 2 2 B-10 P0 0.000000 0.000000 P0 -3 3 2 2 B-11 P0 0.000195 0.001527 P0 material group out nuclide mean std. dev. +3 3 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. +12 3 1 1 H-1 0.181306 0.022102 +13 3 1 1 O-16 0.078631 0.005044 +14 3 1 1 B-10 0.000000 0.000000 +15 3 1 1 B-11 0.000000 0.000000 +8 3 1 2 H-1 0.025666 0.001582 +9 3 1 2 O-16 0.000521 0.000131 +10 3 1 2 B-10 0.000000 0.000000 +11 3 1 2 B-11 0.000000 0.000000 +4 3 2 1 H-1 0.000000 0.000000 +5 3 2 1 O-16 0.000000 0.000000 +6 3 2 1 B-10 0.000000 0.000000 +7 3 2 1 B-11 0.000000 0.000000 +0 3 2 2 H-1 1.273963 0.250623 +1 3 2 2 O-16 0.085363 0.014001 +2 3 2 2 B-10 0.000000 0.000000 +3 3 2 2 B-11 0.000195 0.001527 material group out nuclide mean std. dev. 4 3 1 H-1 0.0 0.0 5 3 1 O-16 0.0 0.0 6 3 1 B-10 0.0 0.0 @@ -444,23 +444,23 @@ 0 4 2 H-1 0.0 0.0 1 4 2 O-16 0.0 0.0 2 4 2 B-10 0.0 0.0 -3 4 2 B-11 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -12 4 1 1 H-1 P0 0.151295 0.051491 P0 -13 4 1 1 O-16 P0 0.066545 0.010083 P0 -14 4 1 1 B-10 P0 0.000000 0.000000 P0 -15 4 1 1 B-11 P0 0.000089 0.000346 P0 -8 4 1 2 H-1 P0 0.023662 0.003083 P0 -9 4 1 2 O-16 P0 0.000000 0.000000 P0 -10 4 1 2 B-10 P0 0.000000 0.000000 P0 -11 4 1 2 B-11 P0 0.000000 0.000000 P0 -4 4 2 1 H-1 P0 0.000000 0.000000 P0 -5 4 2 1 O-16 P0 0.000000 0.000000 P0 -6 4 2 1 B-10 P0 0.000000 0.000000 P0 -7 4 2 1 B-11 P0 0.000000 0.000000 P0 -0 4 2 2 H-1 P0 1.129933 0.361681 P0 -1 4 2 2 O-16 P0 0.085141 0.028073 P0 -2 4 2 2 B-10 P0 0.000000 0.000000 P0 -3 4 2 2 B-11 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +3 4 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. +12 4 1 1 H-1 0.151295 0.051491 +13 4 1 1 O-16 0.066545 0.010083 +14 4 1 1 B-10 0.000000 0.000000 +15 4 1 1 B-11 0.000089 0.000346 +8 4 1 2 H-1 0.023662 0.003083 +9 4 1 2 O-16 0.000000 0.000000 +10 4 1 2 B-10 0.000000 0.000000 +11 4 1 2 B-11 0.000000 0.000000 +4 4 2 1 H-1 0.000000 0.000000 +5 4 2 1 O-16 0.000000 0.000000 +6 4 2 1 B-10 0.000000 0.000000 +7 4 2 1 B-11 0.000000 0.000000 +0 4 2 2 H-1 1.129933 0.361681 +1 4 2 2 O-16 0.085141 0.028073 +2 4 2 2 B-10 0.000000 0.000000 +3 4 2 2 B-11 0.000000 0.000000 material group out nuclide mean std. dev. 4 4 1 H-1 0.0 0.0 5 4 1 O-16 0.0 0.0 6 4 1 B-10 0.0 0.0 @@ -576,115 +576,115 @@ 23 5 2 Cr-54 0.0 0.0 24 5 2 C-Nat 0.0 0.0 25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -81 5 1 1 Fe-54 P0 0.0 0.0 P0 -82 5 1 1 Fe-56 P0 0.0 0.0 P0 -83 5 1 1 Fe-57 P0 0.0 0.0 P0 -84 5 1 1 Fe-58 P0 0.0 0.0 P0 -85 5 1 1 Ni-58 P0 0.0 0.0 P0 -86 5 1 1 Ni-60 P0 0.0 0.0 P0 -87 5 1 1 Ni-61 P0 0.0 0.0 P0 -88 5 1 1 Ni-62 P0 0.0 0.0 P0 -89 5 1 1 Ni-64 P0 0.0 0.0 P0 -90 5 1 1 Mn-55 P0 0.0 0.0 P0 -91 5 1 1 Mo-92 P0 0.0 0.0 P0 -92 5 1 1 Mo-94 P0 0.0 0.0 P0 -93 5 1 1 Mo-95 P0 0.0 0.0 P0 -94 5 1 1 Mo-96 P0 0.0 0.0 P0 -95 5 1 1 Mo-97 P0 0.0 0.0 P0 -96 5 1 1 Mo-98 P0 0.0 0.0 P0 -97 5 1 1 Mo-100 P0 0.0 0.0 P0 -98 5 1 1 Si-28 P0 0.0 0.0 P0 -99 5 1 1 Si-29 P0 0.0 0.0 P0 -100 5 1 1 Si-30 P0 0.0 0.0 P0 -101 5 1 1 Cr-50 P0 0.0 0.0 P0 -102 5 1 1 Cr-52 P0 0.0 0.0 P0 -103 5 1 1 Cr-53 P0 0.0 0.0 P0 -104 5 1 1 Cr-54 P0 0.0 0.0 P0 -105 5 1 1 C-Nat P0 0.0 0.0 P0 -106 5 1 1 Cu-63 P0 0.0 0.0 P0 -107 5 1 1 Cu-65 P0 0.0 0.0 P0 -54 5 1 2 Fe-54 P0 0.0 0.0 P0 -55 5 1 2 Fe-56 P0 0.0 0.0 P0 -56 5 1 2 Fe-57 P0 0.0 0.0 P0 -57 5 1 2 Fe-58 P0 0.0 0.0 P0 -58 5 1 2 Ni-58 P0 0.0 0.0 P0 -59 5 1 2 Ni-60 P0 0.0 0.0 P0 -60 5 1 2 Ni-61 P0 0.0 0.0 P0 -61 5 1 2 Ni-62 P0 0.0 0.0 P0 -62 5 1 2 Ni-64 P0 0.0 0.0 P0 -63 5 1 2 Mn-55 P0 0.0 0.0 P0 -64 5 1 2 Mo-92 P0 0.0 0.0 P0 -65 5 1 2 Mo-94 P0 0.0 0.0 P0 -66 5 1 2 Mo-95 P0 0.0 0.0 P0 -67 5 1 2 Mo-96 P0 0.0 0.0 P0 -68 5 1 2 Mo-97 P0 0.0 0.0 P0 -69 5 1 2 Mo-98 P0 0.0 0.0 P0 -70 5 1 2 Mo-100 P0 0.0 0.0 P0 -71 5 1 2 Si-28 P0 0.0 0.0 P0 -72 5 1 2 Si-29 P0 0.0 0.0 P0 -73 5 1 2 Si-30 P0 0.0 0.0 P0 -74 5 1 2 Cr-50 P0 0.0 0.0 P0 -75 5 1 2 Cr-52 P0 0.0 0.0 P0 -76 5 1 2 Cr-53 P0 0.0 0.0 P0 -77 5 1 2 Cr-54 P0 0.0 0.0 P0 -78 5 1 2 C-Nat P0 0.0 0.0 P0 -79 5 1 2 Cu-63 P0 0.0 0.0 P0 -80 5 1 2 Cu-65 P0 0.0 0.0 P0 -27 5 2 1 Fe-54 P0 0.0 0.0 P0 -28 5 2 1 Fe-56 P0 0.0 0.0 P0 -29 5 2 1 Fe-57 P0 0.0 0.0 P0 -30 5 2 1 Fe-58 P0 0.0 0.0 P0 -31 5 2 1 Ni-58 P0 0.0 0.0 P0 -32 5 2 1 Ni-60 P0 0.0 0.0 P0 -33 5 2 1 Ni-61 P0 0.0 0.0 P0 -34 5 2 1 Ni-62 P0 0.0 0.0 P0 -35 5 2 1 Ni-64 P0 0.0 0.0 P0 -36 5 2 1 Mn-55 P0 0.0 0.0 P0 -37 5 2 1 Mo-92 P0 0.0 0.0 P0 -38 5 2 1 Mo-94 P0 0.0 0.0 P0 -39 5 2 1 Mo-95 P0 0.0 0.0 P0 -40 5 2 1 Mo-96 P0 0.0 0.0 P0 -41 5 2 1 Mo-97 P0 0.0 0.0 P0 -42 5 2 1 Mo-98 P0 0.0 0.0 P0 -43 5 2 1 Mo-100 P0 0.0 0.0 P0 -44 5 2 1 Si-28 P0 0.0 0.0 P0 -45 5 2 1 Si-29 P0 0.0 0.0 P0 -46 5 2 1 Si-30 P0 0.0 0.0 P0 -47 5 2 1 Cr-50 P0 0.0 0.0 P0 -48 5 2 1 Cr-52 P0 0.0 0.0 P0 -49 5 2 1 Cr-53 P0 0.0 0.0 P0 -50 5 2 1 Cr-54 P0 0.0 0.0 P0 -51 5 2 1 C-Nat P0 0.0 0.0 P0 -52 5 2 1 Cu-63 P0 0.0 0.0 P0 -53 5 2 1 Cu-65 P0 0.0 0.0 P0 -0 5 2 2 Fe-54 P0 0.0 0.0 P0 -1 5 2 2 Fe-56 P0 0.0 0.0 P0 -2 5 2 2 Fe-57 P0 0.0 0.0 P0 -3 5 2 2 Fe-58 P0 0.0 0.0 P0 -4 5 2 2 Ni-58 P0 0.0 0.0 P0 -5 5 2 2 Ni-60 P0 0.0 0.0 P0 -6 5 2 2 Ni-61 P0 0.0 0.0 P0 -7 5 2 2 Ni-62 P0 0.0 0.0 P0 -8 5 2 2 Ni-64 P0 0.0 0.0 P0 -9 5 2 2 Mn-55 P0 0.0 0.0 P0 -10 5 2 2 Mo-92 P0 0.0 0.0 P0 -11 5 2 2 Mo-94 P0 0.0 0.0 P0 -12 5 2 2 Mo-95 P0 0.0 0.0 P0 -13 5 2 2 Mo-96 P0 0.0 0.0 P0 -14 5 2 2 Mo-97 P0 0.0 0.0 P0 -15 5 2 2 Mo-98 P0 0.0 0.0 P0 -16 5 2 2 Mo-100 P0 0.0 0.0 P0 -17 5 2 2 Si-28 P0 0.0 0.0 P0 -18 5 2 2 Si-29 P0 0.0 0.0 P0 -19 5 2 2 Si-30 P0 0.0 0.0 P0 -20 5 2 2 Cr-50 P0 0.0 0.0 P0 -21 5 2 2 Cr-52 P0 0.0 0.0 P0 -22 5 2 2 Cr-53 P0 0.0 0.0 P0 -23 5 2 2 Cr-54 P0 0.0 0.0 P0 -24 5 2 2 C-Nat P0 0.0 0.0 P0 -25 5 2 2 Cu-63 P0 0.0 0.0 P0 -26 5 2 2 Cu-65 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +26 5 2 Cu-65 0.0 0.0 material group in group out nuclide mean std. dev. +81 5 1 1 Fe-54 0.0 0.0 +82 5 1 1 Fe-56 0.0 0.0 +83 5 1 1 Fe-57 0.0 0.0 +84 5 1 1 Fe-58 0.0 0.0 +85 5 1 1 Ni-58 0.0 0.0 +86 5 1 1 Ni-60 0.0 0.0 +87 5 1 1 Ni-61 0.0 0.0 +88 5 1 1 Ni-62 0.0 0.0 +89 5 1 1 Ni-64 0.0 0.0 +90 5 1 1 Mn-55 0.0 0.0 +91 5 1 1 Mo-92 0.0 0.0 +92 5 1 1 Mo-94 0.0 0.0 +93 5 1 1 Mo-95 0.0 0.0 +94 5 1 1 Mo-96 0.0 0.0 +95 5 1 1 Mo-97 0.0 0.0 +96 5 1 1 Mo-98 0.0 0.0 +97 5 1 1 Mo-100 0.0 0.0 +98 5 1 1 Si-28 0.0 0.0 +99 5 1 1 Si-29 0.0 0.0 +100 5 1 1 Si-30 0.0 0.0 +101 5 1 1 Cr-50 0.0 0.0 +102 5 1 1 Cr-52 0.0 0.0 +103 5 1 1 Cr-53 0.0 0.0 +104 5 1 1 Cr-54 0.0 0.0 +105 5 1 1 C-Nat 0.0 0.0 +106 5 1 1 Cu-63 0.0 0.0 +107 5 1 1 Cu-65 0.0 0.0 +54 5 1 2 Fe-54 0.0 0.0 +55 5 1 2 Fe-56 0.0 0.0 +56 5 1 2 Fe-57 0.0 0.0 +57 5 1 2 Fe-58 0.0 0.0 +58 5 1 2 Ni-58 0.0 0.0 +59 5 1 2 Ni-60 0.0 0.0 +60 5 1 2 Ni-61 0.0 0.0 +61 5 1 2 Ni-62 0.0 0.0 +62 5 1 2 Ni-64 0.0 0.0 +63 5 1 2 Mn-55 0.0 0.0 +64 5 1 2 Mo-92 0.0 0.0 +65 5 1 2 Mo-94 0.0 0.0 +66 5 1 2 Mo-95 0.0 0.0 +67 5 1 2 Mo-96 0.0 0.0 +68 5 1 2 Mo-97 0.0 0.0 +69 5 1 2 Mo-98 0.0 0.0 +70 5 1 2 Mo-100 0.0 0.0 +71 5 1 2 Si-28 0.0 0.0 +72 5 1 2 Si-29 0.0 0.0 +73 5 1 2 Si-30 0.0 0.0 +74 5 1 2 Cr-50 0.0 0.0 +75 5 1 2 Cr-52 0.0 0.0 +76 5 1 2 Cr-53 0.0 0.0 +77 5 1 2 Cr-54 0.0 0.0 +78 5 1 2 C-Nat 0.0 0.0 +79 5 1 2 Cu-63 0.0 0.0 +80 5 1 2 Cu-65 0.0 0.0 +27 5 2 1 Fe-54 0.0 0.0 +28 5 2 1 Fe-56 0.0 0.0 +29 5 2 1 Fe-57 0.0 0.0 +30 5 2 1 Fe-58 0.0 0.0 +31 5 2 1 Ni-58 0.0 0.0 +32 5 2 1 Ni-60 0.0 0.0 +33 5 2 1 Ni-61 0.0 0.0 +34 5 2 1 Ni-62 0.0 0.0 +35 5 2 1 Ni-64 0.0 0.0 +36 5 2 1 Mn-55 0.0 0.0 +37 5 2 1 Mo-92 0.0 0.0 +38 5 2 1 Mo-94 0.0 0.0 +39 5 2 1 Mo-95 0.0 0.0 +40 5 2 1 Mo-96 0.0 0.0 +41 5 2 1 Mo-97 0.0 0.0 +42 5 2 1 Mo-98 0.0 0.0 +43 5 2 1 Mo-100 0.0 0.0 +44 5 2 1 Si-28 0.0 0.0 +45 5 2 1 Si-29 0.0 0.0 +46 5 2 1 Si-30 0.0 0.0 +47 5 2 1 Cr-50 0.0 0.0 +48 5 2 1 Cr-52 0.0 0.0 +49 5 2 1 Cr-53 0.0 0.0 +50 5 2 1 Cr-54 0.0 0.0 +51 5 2 1 C-Nat 0.0 0.0 +52 5 2 1 Cu-63 0.0 0.0 +53 5 2 1 Cu-65 0.0 0.0 +0 5 2 2 Fe-54 0.0 0.0 +1 5 2 2 Fe-56 0.0 0.0 +2 5 2 2 Fe-57 0.0 0.0 +3 5 2 2 Fe-58 0.0 0.0 +4 5 2 2 Ni-58 0.0 0.0 +5 5 2 2 Ni-60 0.0 0.0 +6 5 2 2 Ni-61 0.0 0.0 +7 5 2 2 Ni-62 0.0 0.0 +8 5 2 2 Ni-64 0.0 0.0 +9 5 2 2 Mn-55 0.0 0.0 +10 5 2 2 Mo-92 0.0 0.0 +11 5 2 2 Mo-94 0.0 0.0 +12 5 2 2 Mo-95 0.0 0.0 +13 5 2 2 Mo-96 0.0 0.0 +14 5 2 2 Mo-97 0.0 0.0 +15 5 2 2 Mo-98 0.0 0.0 +16 5 2 2 Mo-100 0.0 0.0 +17 5 2 2 Si-28 0.0 0.0 +18 5 2 2 Si-29 0.0 0.0 +19 5 2 2 Si-30 0.0 0.0 +20 5 2 2 Cr-50 0.0 0.0 +21 5 2 2 Cr-52 0.0 0.0 +22 5 2 2 Cr-53 0.0 0.0 +23 5 2 2 Cr-54 0.0 0.0 +24 5 2 2 C-Nat 0.0 0.0 +25 5 2 2 Cu-63 0.0 0.0 +26 5 2 2 Cu-65 0.0 0.0 material group out nuclide mean std. dev. 27 5 1 Fe-54 0.0 0.0 28 5 1 Fe-56 0.0 0.0 29 5 1 Fe-57 0.0 0.0 @@ -822,91 +822,91 @@ 17 6 2 Cr-50 0.0 0.0 18 6 2 Cr-52 0.0 0.0 19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -63 6 1 1 H-1 P0 0.0 0.0 P0 -64 6 1 1 O-16 P0 0.0 0.0 P0 -65 6 1 1 B-10 P0 0.0 0.0 P0 -66 6 1 1 B-11 P0 0.0 0.0 P0 -67 6 1 1 Fe-54 P0 0.0 0.0 P0 -68 6 1 1 Fe-56 P0 0.0 0.0 P0 -69 6 1 1 Fe-57 P0 0.0 0.0 P0 -70 6 1 1 Fe-58 P0 0.0 0.0 P0 -71 6 1 1 Ni-58 P0 0.0 0.0 P0 -72 6 1 1 Ni-60 P0 0.0 0.0 P0 -73 6 1 1 Ni-61 P0 0.0 0.0 P0 -74 6 1 1 Ni-62 P0 0.0 0.0 P0 -75 6 1 1 Ni-64 P0 0.0 0.0 P0 -76 6 1 1 Mn-55 P0 0.0 0.0 P0 -77 6 1 1 Si-28 P0 0.0 0.0 P0 -78 6 1 1 Si-29 P0 0.0 0.0 P0 -79 6 1 1 Si-30 P0 0.0 0.0 P0 -80 6 1 1 Cr-50 P0 0.0 0.0 P0 -81 6 1 1 Cr-52 P0 0.0 0.0 P0 -82 6 1 1 Cr-53 P0 0.0 0.0 P0 -83 6 1 1 Cr-54 P0 0.0 0.0 P0 -42 6 1 2 H-1 P0 0.0 0.0 P0 -43 6 1 2 O-16 P0 0.0 0.0 P0 -44 6 1 2 B-10 P0 0.0 0.0 P0 -45 6 1 2 B-11 P0 0.0 0.0 P0 -46 6 1 2 Fe-54 P0 0.0 0.0 P0 -47 6 1 2 Fe-56 P0 0.0 0.0 P0 -48 6 1 2 Fe-57 P0 0.0 0.0 P0 -49 6 1 2 Fe-58 P0 0.0 0.0 P0 -50 6 1 2 Ni-58 P0 0.0 0.0 P0 -51 6 1 2 Ni-60 P0 0.0 0.0 P0 -52 6 1 2 Ni-61 P0 0.0 0.0 P0 -53 6 1 2 Ni-62 P0 0.0 0.0 P0 -54 6 1 2 Ni-64 P0 0.0 0.0 P0 -55 6 1 2 Mn-55 P0 0.0 0.0 P0 -56 6 1 2 Si-28 P0 0.0 0.0 P0 -57 6 1 2 Si-29 P0 0.0 0.0 P0 -58 6 1 2 Si-30 P0 0.0 0.0 P0 -59 6 1 2 Cr-50 P0 0.0 0.0 P0 -60 6 1 2 Cr-52 P0 0.0 0.0 P0 -61 6 1 2 Cr-53 P0 0.0 0.0 P0 -62 6 1 2 Cr-54 P0 0.0 0.0 P0 -21 6 2 1 H-1 P0 0.0 0.0 P0 -22 6 2 1 O-16 P0 0.0 0.0 P0 -23 6 2 1 B-10 P0 0.0 0.0 P0 -24 6 2 1 B-11 P0 0.0 0.0 P0 -25 6 2 1 Fe-54 P0 0.0 0.0 P0 -26 6 2 1 Fe-56 P0 0.0 0.0 P0 -27 6 2 1 Fe-57 P0 0.0 0.0 P0 -28 6 2 1 Fe-58 P0 0.0 0.0 P0 -29 6 2 1 Ni-58 P0 0.0 0.0 P0 -30 6 2 1 Ni-60 P0 0.0 0.0 P0 -31 6 2 1 Ni-61 P0 0.0 0.0 P0 -32 6 2 1 Ni-62 P0 0.0 0.0 P0 -33 6 2 1 Ni-64 P0 0.0 0.0 P0 -34 6 2 1 Mn-55 P0 0.0 0.0 P0 -35 6 2 1 Si-28 P0 0.0 0.0 P0 -36 6 2 1 Si-29 P0 0.0 0.0 P0 -37 6 2 1 Si-30 P0 0.0 0.0 P0 -38 6 2 1 Cr-50 P0 0.0 0.0 P0 -39 6 2 1 Cr-52 P0 0.0 0.0 P0 -40 6 2 1 Cr-53 P0 0.0 0.0 P0 -41 6 2 1 Cr-54 P0 0.0 0.0 P0 -0 6 2 2 H-1 P0 0.0 0.0 P0 -1 6 2 2 O-16 P0 0.0 0.0 P0 -2 6 2 2 B-10 P0 0.0 0.0 P0 -3 6 2 2 B-11 P0 0.0 0.0 P0 -4 6 2 2 Fe-54 P0 0.0 0.0 P0 -5 6 2 2 Fe-56 P0 0.0 0.0 P0 -6 6 2 2 Fe-57 P0 0.0 0.0 P0 -7 6 2 2 Fe-58 P0 0.0 0.0 P0 -8 6 2 2 Ni-58 P0 0.0 0.0 P0 -9 6 2 2 Ni-60 P0 0.0 0.0 P0 -10 6 2 2 Ni-61 P0 0.0 0.0 P0 -11 6 2 2 Ni-62 P0 0.0 0.0 P0 -12 6 2 2 Ni-64 P0 0.0 0.0 P0 -13 6 2 2 Mn-55 P0 0.0 0.0 P0 -14 6 2 2 Si-28 P0 0.0 0.0 P0 -15 6 2 2 Si-29 P0 0.0 0.0 P0 -16 6 2 2 Si-30 P0 0.0 0.0 P0 -17 6 2 2 Cr-50 P0 0.0 0.0 P0 -18 6 2 2 Cr-52 P0 0.0 0.0 P0 -19 6 2 2 Cr-53 P0 0.0 0.0 P0 -20 6 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +20 6 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. +63 6 1 1 H-1 0.0 0.0 +64 6 1 1 O-16 0.0 0.0 +65 6 1 1 B-10 0.0 0.0 +66 6 1 1 B-11 0.0 0.0 +67 6 1 1 Fe-54 0.0 0.0 +68 6 1 1 Fe-56 0.0 0.0 +69 6 1 1 Fe-57 0.0 0.0 +70 6 1 1 Fe-58 0.0 0.0 +71 6 1 1 Ni-58 0.0 0.0 +72 6 1 1 Ni-60 0.0 0.0 +73 6 1 1 Ni-61 0.0 0.0 +74 6 1 1 Ni-62 0.0 0.0 +75 6 1 1 Ni-64 0.0 0.0 +76 6 1 1 Mn-55 0.0 0.0 +77 6 1 1 Si-28 0.0 0.0 +78 6 1 1 Si-29 0.0 0.0 +79 6 1 1 Si-30 0.0 0.0 +80 6 1 1 Cr-50 0.0 0.0 +81 6 1 1 Cr-52 0.0 0.0 +82 6 1 1 Cr-53 0.0 0.0 +83 6 1 1 Cr-54 0.0 0.0 +42 6 1 2 H-1 0.0 0.0 +43 6 1 2 O-16 0.0 0.0 +44 6 1 2 B-10 0.0 0.0 +45 6 1 2 B-11 0.0 0.0 +46 6 1 2 Fe-54 0.0 0.0 +47 6 1 2 Fe-56 0.0 0.0 +48 6 1 2 Fe-57 0.0 0.0 +49 6 1 2 Fe-58 0.0 0.0 +50 6 1 2 Ni-58 0.0 0.0 +51 6 1 2 Ni-60 0.0 0.0 +52 6 1 2 Ni-61 0.0 0.0 +53 6 1 2 Ni-62 0.0 0.0 +54 6 1 2 Ni-64 0.0 0.0 +55 6 1 2 Mn-55 0.0 0.0 +56 6 1 2 Si-28 0.0 0.0 +57 6 1 2 Si-29 0.0 0.0 +58 6 1 2 Si-30 0.0 0.0 +59 6 1 2 Cr-50 0.0 0.0 +60 6 1 2 Cr-52 0.0 0.0 +61 6 1 2 Cr-53 0.0 0.0 +62 6 1 2 Cr-54 0.0 0.0 +21 6 2 1 H-1 0.0 0.0 +22 6 2 1 O-16 0.0 0.0 +23 6 2 1 B-10 0.0 0.0 +24 6 2 1 B-11 0.0 0.0 +25 6 2 1 Fe-54 0.0 0.0 +26 6 2 1 Fe-56 0.0 0.0 +27 6 2 1 Fe-57 0.0 0.0 +28 6 2 1 Fe-58 0.0 0.0 +29 6 2 1 Ni-58 0.0 0.0 +30 6 2 1 Ni-60 0.0 0.0 +31 6 2 1 Ni-61 0.0 0.0 +32 6 2 1 Ni-62 0.0 0.0 +33 6 2 1 Ni-64 0.0 0.0 +34 6 2 1 Mn-55 0.0 0.0 +35 6 2 1 Si-28 0.0 0.0 +36 6 2 1 Si-29 0.0 0.0 +37 6 2 1 Si-30 0.0 0.0 +38 6 2 1 Cr-50 0.0 0.0 +39 6 2 1 Cr-52 0.0 0.0 +40 6 2 1 Cr-53 0.0 0.0 +41 6 2 1 Cr-54 0.0 0.0 +0 6 2 2 H-1 0.0 0.0 +1 6 2 2 O-16 0.0 0.0 +2 6 2 2 B-10 0.0 0.0 +3 6 2 2 B-11 0.0 0.0 +4 6 2 2 Fe-54 0.0 0.0 +5 6 2 2 Fe-56 0.0 0.0 +6 6 2 2 Fe-57 0.0 0.0 +7 6 2 2 Fe-58 0.0 0.0 +8 6 2 2 Ni-58 0.0 0.0 +9 6 2 2 Ni-60 0.0 0.0 +10 6 2 2 Ni-61 0.0 0.0 +11 6 2 2 Ni-62 0.0 0.0 +12 6 2 2 Ni-64 0.0 0.0 +13 6 2 2 Mn-55 0.0 0.0 +14 6 2 2 Si-28 0.0 0.0 +15 6 2 2 Si-29 0.0 0.0 +16 6 2 2 Si-30 0.0 0.0 +17 6 2 2 Cr-50 0.0 0.0 +18 6 2 2 Cr-52 0.0 0.0 +19 6 2 2 Cr-53 0.0 0.0 +20 6 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. 21 6 1 H-1 0.0 0.0 22 6 1 O-16 0.0 0.0 23 6 1 B-10 0.0 0.0 @@ -1032,91 +1032,91 @@ 17 7 2 Cr-50 0.0 0.0 18 7 2 Cr-52 0.0 0.0 19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -63 7 1 1 H-1 P0 0.0 0.0 P0 -64 7 1 1 O-16 P0 0.0 0.0 P0 -65 7 1 1 B-10 P0 0.0 0.0 P0 -66 7 1 1 B-11 P0 0.0 0.0 P0 -67 7 1 1 Fe-54 P0 0.0 0.0 P0 -68 7 1 1 Fe-56 P0 0.0 0.0 P0 -69 7 1 1 Fe-57 P0 0.0 0.0 P0 -70 7 1 1 Fe-58 P0 0.0 0.0 P0 -71 7 1 1 Ni-58 P0 0.0 0.0 P0 -72 7 1 1 Ni-60 P0 0.0 0.0 P0 -73 7 1 1 Ni-61 P0 0.0 0.0 P0 -74 7 1 1 Ni-62 P0 0.0 0.0 P0 -75 7 1 1 Ni-64 P0 0.0 0.0 P0 -76 7 1 1 Mn-55 P0 0.0 0.0 P0 -77 7 1 1 Si-28 P0 0.0 0.0 P0 -78 7 1 1 Si-29 P0 0.0 0.0 P0 -79 7 1 1 Si-30 P0 0.0 0.0 P0 -80 7 1 1 Cr-50 P0 0.0 0.0 P0 -81 7 1 1 Cr-52 P0 0.0 0.0 P0 -82 7 1 1 Cr-53 P0 0.0 0.0 P0 -83 7 1 1 Cr-54 P0 0.0 0.0 P0 -42 7 1 2 H-1 P0 0.0 0.0 P0 -43 7 1 2 O-16 P0 0.0 0.0 P0 -44 7 1 2 B-10 P0 0.0 0.0 P0 -45 7 1 2 B-11 P0 0.0 0.0 P0 -46 7 1 2 Fe-54 P0 0.0 0.0 P0 -47 7 1 2 Fe-56 P0 0.0 0.0 P0 -48 7 1 2 Fe-57 P0 0.0 0.0 P0 -49 7 1 2 Fe-58 P0 0.0 0.0 P0 -50 7 1 2 Ni-58 P0 0.0 0.0 P0 -51 7 1 2 Ni-60 P0 0.0 0.0 P0 -52 7 1 2 Ni-61 P0 0.0 0.0 P0 -53 7 1 2 Ni-62 P0 0.0 0.0 P0 -54 7 1 2 Ni-64 P0 0.0 0.0 P0 -55 7 1 2 Mn-55 P0 0.0 0.0 P0 -56 7 1 2 Si-28 P0 0.0 0.0 P0 -57 7 1 2 Si-29 P0 0.0 0.0 P0 -58 7 1 2 Si-30 P0 0.0 0.0 P0 -59 7 1 2 Cr-50 P0 0.0 0.0 P0 -60 7 1 2 Cr-52 P0 0.0 0.0 P0 -61 7 1 2 Cr-53 P0 0.0 0.0 P0 -62 7 1 2 Cr-54 P0 0.0 0.0 P0 -21 7 2 1 H-1 P0 0.0 0.0 P0 -22 7 2 1 O-16 P0 0.0 0.0 P0 -23 7 2 1 B-10 P0 0.0 0.0 P0 -24 7 2 1 B-11 P0 0.0 0.0 P0 -25 7 2 1 Fe-54 P0 0.0 0.0 P0 -26 7 2 1 Fe-56 P0 0.0 0.0 P0 -27 7 2 1 Fe-57 P0 0.0 0.0 P0 -28 7 2 1 Fe-58 P0 0.0 0.0 P0 -29 7 2 1 Ni-58 P0 0.0 0.0 P0 -30 7 2 1 Ni-60 P0 0.0 0.0 P0 -31 7 2 1 Ni-61 P0 0.0 0.0 P0 -32 7 2 1 Ni-62 P0 0.0 0.0 P0 -33 7 2 1 Ni-64 P0 0.0 0.0 P0 -34 7 2 1 Mn-55 P0 0.0 0.0 P0 -35 7 2 1 Si-28 P0 0.0 0.0 P0 -36 7 2 1 Si-29 P0 0.0 0.0 P0 -37 7 2 1 Si-30 P0 0.0 0.0 P0 -38 7 2 1 Cr-50 P0 0.0 0.0 P0 -39 7 2 1 Cr-52 P0 0.0 0.0 P0 -40 7 2 1 Cr-53 P0 0.0 0.0 P0 -41 7 2 1 Cr-54 P0 0.0 0.0 P0 -0 7 2 2 H-1 P0 0.0 0.0 P0 -1 7 2 2 O-16 P0 0.0 0.0 P0 -2 7 2 2 B-10 P0 0.0 0.0 P0 -3 7 2 2 B-11 P0 0.0 0.0 P0 -4 7 2 2 Fe-54 P0 0.0 0.0 P0 -5 7 2 2 Fe-56 P0 0.0 0.0 P0 -6 7 2 2 Fe-57 P0 0.0 0.0 P0 -7 7 2 2 Fe-58 P0 0.0 0.0 P0 -8 7 2 2 Ni-58 P0 0.0 0.0 P0 -9 7 2 2 Ni-60 P0 0.0 0.0 P0 -10 7 2 2 Ni-61 P0 0.0 0.0 P0 -11 7 2 2 Ni-62 P0 0.0 0.0 P0 -12 7 2 2 Ni-64 P0 0.0 0.0 P0 -13 7 2 2 Mn-55 P0 0.0 0.0 P0 -14 7 2 2 Si-28 P0 0.0 0.0 P0 -15 7 2 2 Si-29 P0 0.0 0.0 P0 -16 7 2 2 Si-30 P0 0.0 0.0 P0 -17 7 2 2 Cr-50 P0 0.0 0.0 P0 -18 7 2 2 Cr-52 P0 0.0 0.0 P0 -19 7 2 2 Cr-53 P0 0.0 0.0 P0 -20 7 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +20 7 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. +63 7 1 1 H-1 0.0 0.0 +64 7 1 1 O-16 0.0 0.0 +65 7 1 1 B-10 0.0 0.0 +66 7 1 1 B-11 0.0 0.0 +67 7 1 1 Fe-54 0.0 0.0 +68 7 1 1 Fe-56 0.0 0.0 +69 7 1 1 Fe-57 0.0 0.0 +70 7 1 1 Fe-58 0.0 0.0 +71 7 1 1 Ni-58 0.0 0.0 +72 7 1 1 Ni-60 0.0 0.0 +73 7 1 1 Ni-61 0.0 0.0 +74 7 1 1 Ni-62 0.0 0.0 +75 7 1 1 Ni-64 0.0 0.0 +76 7 1 1 Mn-55 0.0 0.0 +77 7 1 1 Si-28 0.0 0.0 +78 7 1 1 Si-29 0.0 0.0 +79 7 1 1 Si-30 0.0 0.0 +80 7 1 1 Cr-50 0.0 0.0 +81 7 1 1 Cr-52 0.0 0.0 +82 7 1 1 Cr-53 0.0 0.0 +83 7 1 1 Cr-54 0.0 0.0 +42 7 1 2 H-1 0.0 0.0 +43 7 1 2 O-16 0.0 0.0 +44 7 1 2 B-10 0.0 0.0 +45 7 1 2 B-11 0.0 0.0 +46 7 1 2 Fe-54 0.0 0.0 +47 7 1 2 Fe-56 0.0 0.0 +48 7 1 2 Fe-57 0.0 0.0 +49 7 1 2 Fe-58 0.0 0.0 +50 7 1 2 Ni-58 0.0 0.0 +51 7 1 2 Ni-60 0.0 0.0 +52 7 1 2 Ni-61 0.0 0.0 +53 7 1 2 Ni-62 0.0 0.0 +54 7 1 2 Ni-64 0.0 0.0 +55 7 1 2 Mn-55 0.0 0.0 +56 7 1 2 Si-28 0.0 0.0 +57 7 1 2 Si-29 0.0 0.0 +58 7 1 2 Si-30 0.0 0.0 +59 7 1 2 Cr-50 0.0 0.0 +60 7 1 2 Cr-52 0.0 0.0 +61 7 1 2 Cr-53 0.0 0.0 +62 7 1 2 Cr-54 0.0 0.0 +21 7 2 1 H-1 0.0 0.0 +22 7 2 1 O-16 0.0 0.0 +23 7 2 1 B-10 0.0 0.0 +24 7 2 1 B-11 0.0 0.0 +25 7 2 1 Fe-54 0.0 0.0 +26 7 2 1 Fe-56 0.0 0.0 +27 7 2 1 Fe-57 0.0 0.0 +28 7 2 1 Fe-58 0.0 0.0 +29 7 2 1 Ni-58 0.0 0.0 +30 7 2 1 Ni-60 0.0 0.0 +31 7 2 1 Ni-61 0.0 0.0 +32 7 2 1 Ni-62 0.0 0.0 +33 7 2 1 Ni-64 0.0 0.0 +34 7 2 1 Mn-55 0.0 0.0 +35 7 2 1 Si-28 0.0 0.0 +36 7 2 1 Si-29 0.0 0.0 +37 7 2 1 Si-30 0.0 0.0 +38 7 2 1 Cr-50 0.0 0.0 +39 7 2 1 Cr-52 0.0 0.0 +40 7 2 1 Cr-53 0.0 0.0 +41 7 2 1 Cr-54 0.0 0.0 +0 7 2 2 H-1 0.0 0.0 +1 7 2 2 O-16 0.0 0.0 +2 7 2 2 B-10 0.0 0.0 +3 7 2 2 B-11 0.0 0.0 +4 7 2 2 Fe-54 0.0 0.0 +5 7 2 2 Fe-56 0.0 0.0 +6 7 2 2 Fe-57 0.0 0.0 +7 7 2 2 Fe-58 0.0 0.0 +8 7 2 2 Ni-58 0.0 0.0 +9 7 2 2 Ni-60 0.0 0.0 +10 7 2 2 Ni-61 0.0 0.0 +11 7 2 2 Ni-62 0.0 0.0 +12 7 2 2 Ni-64 0.0 0.0 +13 7 2 2 Mn-55 0.0 0.0 +14 7 2 2 Si-28 0.0 0.0 +15 7 2 2 Si-29 0.0 0.0 +16 7 2 2 Si-30 0.0 0.0 +17 7 2 2 Cr-50 0.0 0.0 +18 7 2 2 Cr-52 0.0 0.0 +19 7 2 2 Cr-53 0.0 0.0 +20 7 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. 21 7 1 H-1 0.0 0.0 22 7 1 O-16 0.0 0.0 23 7 1 B-10 0.0 0.0 @@ -1242,91 +1242,91 @@ 17 8 2 Cr-50 0.0 0.0 18 8 2 Cr-52 0.0 0.0 19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -63 8 1 1 H-1 P0 0.0 0.0 P0 -64 8 1 1 O-16 P0 0.0 0.0 P0 -65 8 1 1 B-10 P0 0.0 0.0 P0 -66 8 1 1 B-11 P0 0.0 0.0 P0 -67 8 1 1 Fe-54 P0 0.0 0.0 P0 -68 8 1 1 Fe-56 P0 0.0 0.0 P0 -69 8 1 1 Fe-57 P0 0.0 0.0 P0 -70 8 1 1 Fe-58 P0 0.0 0.0 P0 -71 8 1 1 Ni-58 P0 0.0 0.0 P0 -72 8 1 1 Ni-60 P0 0.0 0.0 P0 -73 8 1 1 Ni-61 P0 0.0 0.0 P0 -74 8 1 1 Ni-62 P0 0.0 0.0 P0 -75 8 1 1 Ni-64 P0 0.0 0.0 P0 -76 8 1 1 Mn-55 P0 0.0 0.0 P0 -77 8 1 1 Si-28 P0 0.0 0.0 P0 -78 8 1 1 Si-29 P0 0.0 0.0 P0 -79 8 1 1 Si-30 P0 0.0 0.0 P0 -80 8 1 1 Cr-50 P0 0.0 0.0 P0 -81 8 1 1 Cr-52 P0 0.0 0.0 P0 -82 8 1 1 Cr-53 P0 0.0 0.0 P0 -83 8 1 1 Cr-54 P0 0.0 0.0 P0 -42 8 1 2 H-1 P0 0.0 0.0 P0 -43 8 1 2 O-16 P0 0.0 0.0 P0 -44 8 1 2 B-10 P0 0.0 0.0 P0 -45 8 1 2 B-11 P0 0.0 0.0 P0 -46 8 1 2 Fe-54 P0 0.0 0.0 P0 -47 8 1 2 Fe-56 P0 0.0 0.0 P0 -48 8 1 2 Fe-57 P0 0.0 0.0 P0 -49 8 1 2 Fe-58 P0 0.0 0.0 P0 -50 8 1 2 Ni-58 P0 0.0 0.0 P0 -51 8 1 2 Ni-60 P0 0.0 0.0 P0 -52 8 1 2 Ni-61 P0 0.0 0.0 P0 -53 8 1 2 Ni-62 P0 0.0 0.0 P0 -54 8 1 2 Ni-64 P0 0.0 0.0 P0 -55 8 1 2 Mn-55 P0 0.0 0.0 P0 -56 8 1 2 Si-28 P0 0.0 0.0 P0 -57 8 1 2 Si-29 P0 0.0 0.0 P0 -58 8 1 2 Si-30 P0 0.0 0.0 P0 -59 8 1 2 Cr-50 P0 0.0 0.0 P0 -60 8 1 2 Cr-52 P0 0.0 0.0 P0 -61 8 1 2 Cr-53 P0 0.0 0.0 P0 -62 8 1 2 Cr-54 P0 0.0 0.0 P0 -21 8 2 1 H-1 P0 0.0 0.0 P0 -22 8 2 1 O-16 P0 0.0 0.0 P0 -23 8 2 1 B-10 P0 0.0 0.0 P0 -24 8 2 1 B-11 P0 0.0 0.0 P0 -25 8 2 1 Fe-54 P0 0.0 0.0 P0 -26 8 2 1 Fe-56 P0 0.0 0.0 P0 -27 8 2 1 Fe-57 P0 0.0 0.0 P0 -28 8 2 1 Fe-58 P0 0.0 0.0 P0 -29 8 2 1 Ni-58 P0 0.0 0.0 P0 -30 8 2 1 Ni-60 P0 0.0 0.0 P0 -31 8 2 1 Ni-61 P0 0.0 0.0 P0 -32 8 2 1 Ni-62 P0 0.0 0.0 P0 -33 8 2 1 Ni-64 P0 0.0 0.0 P0 -34 8 2 1 Mn-55 P0 0.0 0.0 P0 -35 8 2 1 Si-28 P0 0.0 0.0 P0 -36 8 2 1 Si-29 P0 0.0 0.0 P0 -37 8 2 1 Si-30 P0 0.0 0.0 P0 -38 8 2 1 Cr-50 P0 0.0 0.0 P0 -39 8 2 1 Cr-52 P0 0.0 0.0 P0 -40 8 2 1 Cr-53 P0 0.0 0.0 P0 -41 8 2 1 Cr-54 P0 0.0 0.0 P0 -0 8 2 2 H-1 P0 0.0 0.0 P0 -1 8 2 2 O-16 P0 0.0 0.0 P0 -2 8 2 2 B-10 P0 0.0 0.0 P0 -3 8 2 2 B-11 P0 0.0 0.0 P0 -4 8 2 2 Fe-54 P0 0.0 0.0 P0 -5 8 2 2 Fe-56 P0 0.0 0.0 P0 -6 8 2 2 Fe-57 P0 0.0 0.0 P0 -7 8 2 2 Fe-58 P0 0.0 0.0 P0 -8 8 2 2 Ni-58 P0 0.0 0.0 P0 -9 8 2 2 Ni-60 P0 0.0 0.0 P0 -10 8 2 2 Ni-61 P0 0.0 0.0 P0 -11 8 2 2 Ni-62 P0 0.0 0.0 P0 -12 8 2 2 Ni-64 P0 0.0 0.0 P0 -13 8 2 2 Mn-55 P0 0.0 0.0 P0 -14 8 2 2 Si-28 P0 0.0 0.0 P0 -15 8 2 2 Si-29 P0 0.0 0.0 P0 -16 8 2 2 Si-30 P0 0.0 0.0 P0 -17 8 2 2 Cr-50 P0 0.0 0.0 P0 -18 8 2 2 Cr-52 P0 0.0 0.0 P0 -19 8 2 2 Cr-53 P0 0.0 0.0 P0 -20 8 2 2 Cr-54 P0 0.0 0.0 P0 material group out nuclide mean std. dev. +20 8 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. +63 8 1 1 H-1 0.0 0.0 +64 8 1 1 O-16 0.0 0.0 +65 8 1 1 B-10 0.0 0.0 +66 8 1 1 B-11 0.0 0.0 +67 8 1 1 Fe-54 0.0 0.0 +68 8 1 1 Fe-56 0.0 0.0 +69 8 1 1 Fe-57 0.0 0.0 +70 8 1 1 Fe-58 0.0 0.0 +71 8 1 1 Ni-58 0.0 0.0 +72 8 1 1 Ni-60 0.0 0.0 +73 8 1 1 Ni-61 0.0 0.0 +74 8 1 1 Ni-62 0.0 0.0 +75 8 1 1 Ni-64 0.0 0.0 +76 8 1 1 Mn-55 0.0 0.0 +77 8 1 1 Si-28 0.0 0.0 +78 8 1 1 Si-29 0.0 0.0 +79 8 1 1 Si-30 0.0 0.0 +80 8 1 1 Cr-50 0.0 0.0 +81 8 1 1 Cr-52 0.0 0.0 +82 8 1 1 Cr-53 0.0 0.0 +83 8 1 1 Cr-54 0.0 0.0 +42 8 1 2 H-1 0.0 0.0 +43 8 1 2 O-16 0.0 0.0 +44 8 1 2 B-10 0.0 0.0 +45 8 1 2 B-11 0.0 0.0 +46 8 1 2 Fe-54 0.0 0.0 +47 8 1 2 Fe-56 0.0 0.0 +48 8 1 2 Fe-57 0.0 0.0 +49 8 1 2 Fe-58 0.0 0.0 +50 8 1 2 Ni-58 0.0 0.0 +51 8 1 2 Ni-60 0.0 0.0 +52 8 1 2 Ni-61 0.0 0.0 +53 8 1 2 Ni-62 0.0 0.0 +54 8 1 2 Ni-64 0.0 0.0 +55 8 1 2 Mn-55 0.0 0.0 +56 8 1 2 Si-28 0.0 0.0 +57 8 1 2 Si-29 0.0 0.0 +58 8 1 2 Si-30 0.0 0.0 +59 8 1 2 Cr-50 0.0 0.0 +60 8 1 2 Cr-52 0.0 0.0 +61 8 1 2 Cr-53 0.0 0.0 +62 8 1 2 Cr-54 0.0 0.0 +21 8 2 1 H-1 0.0 0.0 +22 8 2 1 O-16 0.0 0.0 +23 8 2 1 B-10 0.0 0.0 +24 8 2 1 B-11 0.0 0.0 +25 8 2 1 Fe-54 0.0 0.0 +26 8 2 1 Fe-56 0.0 0.0 +27 8 2 1 Fe-57 0.0 0.0 +28 8 2 1 Fe-58 0.0 0.0 +29 8 2 1 Ni-58 0.0 0.0 +30 8 2 1 Ni-60 0.0 0.0 +31 8 2 1 Ni-61 0.0 0.0 +32 8 2 1 Ni-62 0.0 0.0 +33 8 2 1 Ni-64 0.0 0.0 +34 8 2 1 Mn-55 0.0 0.0 +35 8 2 1 Si-28 0.0 0.0 +36 8 2 1 Si-29 0.0 0.0 +37 8 2 1 Si-30 0.0 0.0 +38 8 2 1 Cr-50 0.0 0.0 +39 8 2 1 Cr-52 0.0 0.0 +40 8 2 1 Cr-53 0.0 0.0 +41 8 2 1 Cr-54 0.0 0.0 +0 8 2 2 H-1 0.0 0.0 +1 8 2 2 O-16 0.0 0.0 +2 8 2 2 B-10 0.0 0.0 +3 8 2 2 B-11 0.0 0.0 +4 8 2 2 Fe-54 0.0 0.0 +5 8 2 2 Fe-56 0.0 0.0 +6 8 2 2 Fe-57 0.0 0.0 +7 8 2 2 Fe-58 0.0 0.0 +8 8 2 2 Ni-58 0.0 0.0 +9 8 2 2 Ni-60 0.0 0.0 +10 8 2 2 Ni-61 0.0 0.0 +11 8 2 2 Ni-62 0.0 0.0 +12 8 2 2 Ni-64 0.0 0.0 +13 8 2 2 Mn-55 0.0 0.0 +14 8 2 2 Si-28 0.0 0.0 +15 8 2 2 Si-29 0.0 0.0 +16 8 2 2 Si-30 0.0 0.0 +17 8 2 2 Cr-50 0.0 0.0 +18 8 2 2 Cr-52 0.0 0.0 +19 8 2 2 Cr-53 0.0 0.0 +20 8 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. 21 8 1 H-1 0.0 0.0 22 8 1 O-16 0.0 0.0 23 8 1 B-10 0.0 0.0 @@ -1452,91 +1452,91 @@ 17 9 2 Cr-50 0.0 0.0 18 9 2 Cr-52 0.0 0.0 19 9 2 Cr-53 0.0 0.0 -20 9 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -63 9 1 1 H-1 P0 0.150655 0.480993 P0 -64 9 1 1 O-16 P0 0.116221 0.114089 P0 -65 9 1 1 B-10 P0 0.000000 0.000000 P0 -66 9 1 1 B-11 P0 0.000000 0.000000 P0 -67 9 1 1 Fe-54 P0 0.000000 0.000000 P0 -68 9 1 1 Fe-56 P0 0.186217 0.199795 P0 -69 9 1 1 Fe-57 P0 0.000000 0.000000 P0 -70 9 1 1 Fe-58 P0 0.000000 0.000000 P0 -71 9 1 1 Ni-58 P0 0.000000 0.000000 P0 -72 9 1 1 Ni-60 P0 0.000000 0.000000 P0 -73 9 1 1 Ni-61 P0 0.000000 0.000000 P0 -74 9 1 1 Ni-62 P0 0.000000 0.000000 P0 -75 9 1 1 Ni-64 P0 0.000000 0.000000 P0 -76 9 1 1 Mn-55 P0 0.000000 0.000000 P0 -77 9 1 1 Si-28 P0 0.000000 0.000000 P0 -78 9 1 1 Si-29 P0 0.000000 0.000000 P0 -79 9 1 1 Si-30 P0 0.000000 0.000000 P0 -80 9 1 1 Cr-50 P0 0.000000 0.000000 P0 -81 9 1 1 Cr-52 P0 0.000000 0.000000 P0 -82 9 1 1 Cr-53 P0 0.147443 0.139574 P0 -83 9 1 1 Cr-54 P0 0.000000 0.000000 P0 -42 9 1 2 H-1 P0 0.000000 0.000000 P0 -43 9 1 2 O-16 P0 0.000000 0.000000 P0 -44 9 1 2 B-10 P0 0.000000 0.000000 P0 -45 9 1 2 B-11 P0 0.000000 0.000000 P0 -46 9 1 2 Fe-54 P0 0.000000 0.000000 P0 -47 9 1 2 Fe-56 P0 0.000000 0.000000 P0 -48 9 1 2 Fe-57 P0 0.000000 0.000000 P0 -49 9 1 2 Fe-58 P0 0.000000 0.000000 P0 -50 9 1 2 Ni-58 P0 0.000000 0.000000 P0 -51 9 1 2 Ni-60 P0 0.000000 0.000000 P0 -52 9 1 2 Ni-61 P0 0.000000 0.000000 P0 -53 9 1 2 Ni-62 P0 0.000000 0.000000 P0 -54 9 1 2 Ni-64 P0 0.000000 0.000000 P0 -55 9 1 2 Mn-55 P0 0.000000 0.000000 P0 -56 9 1 2 Si-28 P0 0.000000 0.000000 P0 -57 9 1 2 Si-29 P0 0.000000 0.000000 P0 -58 9 1 2 Si-30 P0 0.000000 0.000000 P0 -59 9 1 2 Cr-50 P0 0.000000 0.000000 P0 -60 9 1 2 Cr-52 P0 0.000000 0.000000 P0 -61 9 1 2 Cr-53 P0 0.000000 0.000000 P0 -62 9 1 2 Cr-54 P0 0.000000 0.000000 P0 -21 9 2 1 H-1 P0 0.000000 0.000000 P0 -22 9 2 1 O-16 P0 0.000000 0.000000 P0 -23 9 2 1 B-10 P0 0.000000 0.000000 P0 -24 9 2 1 B-11 P0 0.000000 0.000000 P0 -25 9 2 1 Fe-54 P0 0.000000 0.000000 P0 -26 9 2 1 Fe-56 P0 0.000000 0.000000 P0 -27 9 2 1 Fe-57 P0 0.000000 0.000000 P0 -28 9 2 1 Fe-58 P0 0.000000 0.000000 P0 -29 9 2 1 Ni-58 P0 0.000000 0.000000 P0 -30 9 2 1 Ni-60 P0 0.000000 0.000000 P0 -31 9 2 1 Ni-61 P0 0.000000 0.000000 P0 -32 9 2 1 Ni-62 P0 0.000000 0.000000 P0 -33 9 2 1 Ni-64 P0 0.000000 0.000000 P0 -34 9 2 1 Mn-55 P0 0.000000 0.000000 P0 -35 9 2 1 Si-28 P0 0.000000 0.000000 P0 -36 9 2 1 Si-29 P0 0.000000 0.000000 P0 -37 9 2 1 Si-30 P0 0.000000 0.000000 P0 -38 9 2 1 Cr-50 P0 0.000000 0.000000 P0 -39 9 2 1 Cr-52 P0 0.000000 0.000000 P0 -40 9 2 1 Cr-53 P0 0.000000 0.000000 P0 -41 9 2 1 Cr-54 P0 0.000000 0.000000 P0 -0 9 2 2 H-1 P0 0.000000 0.000000 P0 -1 9 2 2 O-16 P0 0.000000 0.000000 P0 -2 9 2 2 B-10 P0 0.000000 0.000000 P0 -3 9 2 2 B-11 P0 0.000000 0.000000 P0 -4 9 2 2 Fe-54 P0 0.000000 0.000000 P0 -5 9 2 2 Fe-56 P0 0.000000 0.000000 P0 -6 9 2 2 Fe-57 P0 0.000000 0.000000 P0 -7 9 2 2 Fe-58 P0 0.000000 0.000000 P0 -8 9 2 2 Ni-58 P0 0.000000 0.000000 P0 -9 9 2 2 Ni-60 P0 0.000000 0.000000 P0 -10 9 2 2 Ni-61 P0 0.000000 0.000000 P0 -11 9 2 2 Ni-62 P0 0.000000 0.000000 P0 -12 9 2 2 Ni-64 P0 0.000000 0.000000 P0 -13 9 2 2 Mn-55 P0 0.000000 0.000000 P0 -14 9 2 2 Si-28 P0 0.000000 0.000000 P0 -15 9 2 2 Si-29 P0 0.000000 0.000000 P0 -16 9 2 2 Si-30 P0 0.000000 0.000000 P0 -17 9 2 2 Cr-50 P0 0.000000 0.000000 P0 -18 9 2 2 Cr-52 P0 0.000000 0.000000 P0 -19 9 2 2 Cr-53 P0 0.000000 0.000000 P0 -20 9 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +20 9 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. +63 9 1 1 H-1 0.150655 0.480993 +64 9 1 1 O-16 0.116221 0.114089 +65 9 1 1 B-10 0.000000 0.000000 +66 9 1 1 B-11 0.000000 0.000000 +67 9 1 1 Fe-54 0.000000 0.000000 +68 9 1 1 Fe-56 0.186217 0.199795 +69 9 1 1 Fe-57 0.000000 0.000000 +70 9 1 1 Fe-58 0.000000 0.000000 +71 9 1 1 Ni-58 0.000000 0.000000 +72 9 1 1 Ni-60 0.000000 0.000000 +73 9 1 1 Ni-61 0.000000 0.000000 +74 9 1 1 Ni-62 0.000000 0.000000 +75 9 1 1 Ni-64 0.000000 0.000000 +76 9 1 1 Mn-55 0.000000 0.000000 +77 9 1 1 Si-28 0.000000 0.000000 +78 9 1 1 Si-29 0.000000 0.000000 +79 9 1 1 Si-30 0.000000 0.000000 +80 9 1 1 Cr-50 0.000000 0.000000 +81 9 1 1 Cr-52 0.000000 0.000000 +82 9 1 1 Cr-53 0.147443 0.139574 +83 9 1 1 Cr-54 0.000000 0.000000 +42 9 1 2 H-1 0.000000 0.000000 +43 9 1 2 O-16 0.000000 0.000000 +44 9 1 2 B-10 0.000000 0.000000 +45 9 1 2 B-11 0.000000 0.000000 +46 9 1 2 Fe-54 0.000000 0.000000 +47 9 1 2 Fe-56 0.000000 0.000000 +48 9 1 2 Fe-57 0.000000 0.000000 +49 9 1 2 Fe-58 0.000000 0.000000 +50 9 1 2 Ni-58 0.000000 0.000000 +51 9 1 2 Ni-60 0.000000 0.000000 +52 9 1 2 Ni-61 0.000000 0.000000 +53 9 1 2 Ni-62 0.000000 0.000000 +54 9 1 2 Ni-64 0.000000 0.000000 +55 9 1 2 Mn-55 0.000000 0.000000 +56 9 1 2 Si-28 0.000000 0.000000 +57 9 1 2 Si-29 0.000000 0.000000 +58 9 1 2 Si-30 0.000000 0.000000 +59 9 1 2 Cr-50 0.000000 0.000000 +60 9 1 2 Cr-52 0.000000 0.000000 +61 9 1 2 Cr-53 0.000000 0.000000 +62 9 1 2 Cr-54 0.000000 0.000000 +21 9 2 1 H-1 0.000000 0.000000 +22 9 2 1 O-16 0.000000 0.000000 +23 9 2 1 B-10 0.000000 0.000000 +24 9 2 1 B-11 0.000000 0.000000 +25 9 2 1 Fe-54 0.000000 0.000000 +26 9 2 1 Fe-56 0.000000 0.000000 +27 9 2 1 Fe-57 0.000000 0.000000 +28 9 2 1 Fe-58 0.000000 0.000000 +29 9 2 1 Ni-58 0.000000 0.000000 +30 9 2 1 Ni-60 0.000000 0.000000 +31 9 2 1 Ni-61 0.000000 0.000000 +32 9 2 1 Ni-62 0.000000 0.000000 +33 9 2 1 Ni-64 0.000000 0.000000 +34 9 2 1 Mn-55 0.000000 0.000000 +35 9 2 1 Si-28 0.000000 0.000000 +36 9 2 1 Si-29 0.000000 0.000000 +37 9 2 1 Si-30 0.000000 0.000000 +38 9 2 1 Cr-50 0.000000 0.000000 +39 9 2 1 Cr-52 0.000000 0.000000 +40 9 2 1 Cr-53 0.000000 0.000000 +41 9 2 1 Cr-54 0.000000 0.000000 +0 9 2 2 H-1 0.000000 0.000000 +1 9 2 2 O-16 0.000000 0.000000 +2 9 2 2 B-10 0.000000 0.000000 +3 9 2 2 B-11 0.000000 0.000000 +4 9 2 2 Fe-54 0.000000 0.000000 +5 9 2 2 Fe-56 0.000000 0.000000 +6 9 2 2 Fe-57 0.000000 0.000000 +7 9 2 2 Fe-58 0.000000 0.000000 +8 9 2 2 Ni-58 0.000000 0.000000 +9 9 2 2 Ni-60 0.000000 0.000000 +10 9 2 2 Ni-61 0.000000 0.000000 +11 9 2 2 Ni-62 0.000000 0.000000 +12 9 2 2 Ni-64 0.000000 0.000000 +13 9 2 2 Mn-55 0.000000 0.000000 +14 9 2 2 Si-28 0.000000 0.000000 +15 9 2 2 Si-29 0.000000 0.000000 +16 9 2 2 Si-30 0.000000 0.000000 +17 9 2 2 Cr-50 0.000000 0.000000 +18 9 2 2 Cr-52 0.000000 0.000000 +19 9 2 2 Cr-53 0.000000 0.000000 +20 9 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. 21 9 1 H-1 0.0 0.0 22 9 1 O-16 0.0 0.0 23 9 1 B-10 0.0 0.0 @@ -1662,91 +1662,91 @@ 17 10 2 Cr-50 0.0 0.0 18 10 2 Cr-52 0.0 0.0 19 10 2 Cr-53 0.0 0.0 -20 10 2 Cr-54 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -63 10 1 1 H-1 P0 0.123944 0.541390 P0 -64 10 1 1 O-16 P0 0.000000 0.000000 P0 -65 10 1 1 B-10 P0 0.000000 0.000000 P0 -66 10 1 1 B-11 P0 0.000000 0.000000 P0 -67 10 1 1 Fe-54 P0 0.000000 0.000000 P0 -68 10 1 1 Fe-56 P0 0.000000 0.000000 P0 -69 10 1 1 Fe-57 P0 0.000000 0.000000 P0 -70 10 1 1 Fe-58 P0 0.000000 0.000000 P0 -71 10 1 1 Ni-58 P0 0.000000 0.000000 P0 -72 10 1 1 Ni-60 P0 0.000000 0.000000 P0 -73 10 1 1 Ni-61 P0 0.000000 0.000000 P0 -74 10 1 1 Ni-62 P0 0.000000 0.000000 P0 -75 10 1 1 Ni-64 P0 0.000000 0.000000 P0 -76 10 1 1 Mn-55 P0 0.000000 0.000000 P0 -77 10 1 1 Si-28 P0 0.000000 0.000000 P0 -78 10 1 1 Si-29 P0 0.000000 0.000000 P0 -79 10 1 1 Si-30 P0 0.000000 0.000000 P0 -80 10 1 1 Cr-50 P0 0.111571 0.138458 P0 -81 10 1 1 Cr-52 P0 0.000000 0.000000 P0 -82 10 1 1 Cr-53 P0 0.000000 0.000000 P0 -83 10 1 1 Cr-54 P0 0.000000 0.000000 P0 -42 10 1 2 H-1 P0 0.000000 0.000000 P0 -43 10 1 2 O-16 P0 0.000000 0.000000 P0 -44 10 1 2 B-10 P0 0.000000 0.000000 P0 -45 10 1 2 B-11 P0 0.000000 0.000000 P0 -46 10 1 2 Fe-54 P0 0.000000 0.000000 P0 -47 10 1 2 Fe-56 P0 0.000000 0.000000 P0 -48 10 1 2 Fe-57 P0 0.000000 0.000000 P0 -49 10 1 2 Fe-58 P0 0.000000 0.000000 P0 -50 10 1 2 Ni-58 P0 0.000000 0.000000 P0 -51 10 1 2 Ni-60 P0 0.000000 0.000000 P0 -52 10 1 2 Ni-61 P0 0.000000 0.000000 P0 -53 10 1 2 Ni-62 P0 0.000000 0.000000 P0 -54 10 1 2 Ni-64 P0 0.000000 0.000000 P0 -55 10 1 2 Mn-55 P0 0.000000 0.000000 P0 -56 10 1 2 Si-28 P0 0.000000 0.000000 P0 -57 10 1 2 Si-29 P0 0.000000 0.000000 P0 -58 10 1 2 Si-30 P0 0.000000 0.000000 P0 -59 10 1 2 Cr-50 P0 0.000000 0.000000 P0 -60 10 1 2 Cr-52 P0 0.000000 0.000000 P0 -61 10 1 2 Cr-53 P0 0.000000 0.000000 P0 -62 10 1 2 Cr-54 P0 0.000000 0.000000 P0 -21 10 2 1 H-1 P0 0.000000 0.000000 P0 -22 10 2 1 O-16 P0 0.000000 0.000000 P0 -23 10 2 1 B-10 P0 0.000000 0.000000 P0 -24 10 2 1 B-11 P0 0.000000 0.000000 P0 -25 10 2 1 Fe-54 P0 0.000000 0.000000 P0 -26 10 2 1 Fe-56 P0 0.000000 0.000000 P0 -27 10 2 1 Fe-57 P0 0.000000 0.000000 P0 -28 10 2 1 Fe-58 P0 0.000000 0.000000 P0 -29 10 2 1 Ni-58 P0 0.000000 0.000000 P0 -30 10 2 1 Ni-60 P0 0.000000 0.000000 P0 -31 10 2 1 Ni-61 P0 0.000000 0.000000 P0 -32 10 2 1 Ni-62 P0 0.000000 0.000000 P0 -33 10 2 1 Ni-64 P0 0.000000 0.000000 P0 -34 10 2 1 Mn-55 P0 0.000000 0.000000 P0 -35 10 2 1 Si-28 P0 0.000000 0.000000 P0 -36 10 2 1 Si-29 P0 0.000000 0.000000 P0 -37 10 2 1 Si-30 P0 0.000000 0.000000 P0 -38 10 2 1 Cr-50 P0 0.000000 0.000000 P0 -39 10 2 1 Cr-52 P0 0.000000 0.000000 P0 -40 10 2 1 Cr-53 P0 0.000000 0.000000 P0 -41 10 2 1 Cr-54 P0 0.000000 0.000000 P0 -0 10 2 2 H-1 P0 0.000000 0.000000 P0 -1 10 2 2 O-16 P0 0.000000 0.000000 P0 -2 10 2 2 B-10 P0 0.000000 0.000000 P0 -3 10 2 2 B-11 P0 0.000000 0.000000 P0 -4 10 2 2 Fe-54 P0 0.000000 0.000000 P0 -5 10 2 2 Fe-56 P0 0.000000 0.000000 P0 -6 10 2 2 Fe-57 P0 0.000000 0.000000 P0 -7 10 2 2 Fe-58 P0 0.000000 0.000000 P0 -8 10 2 2 Ni-58 P0 0.000000 0.000000 P0 -9 10 2 2 Ni-60 P0 0.000000 0.000000 P0 -10 10 2 2 Ni-61 P0 0.000000 0.000000 P0 -11 10 2 2 Ni-62 P0 0.000000 0.000000 P0 -12 10 2 2 Ni-64 P0 0.000000 0.000000 P0 -13 10 2 2 Mn-55 P0 0.000000 0.000000 P0 -14 10 2 2 Si-28 P0 0.000000 0.000000 P0 -15 10 2 2 Si-29 P0 0.000000 0.000000 P0 -16 10 2 2 Si-30 P0 0.000000 0.000000 P0 -17 10 2 2 Cr-50 P0 0.000000 0.000000 P0 -18 10 2 2 Cr-52 P0 0.000000 0.000000 P0 -19 10 2 2 Cr-53 P0 0.000000 0.000000 P0 -20 10 2 2 Cr-54 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +20 10 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. +63 10 1 1 H-1 0.123944 0.541390 +64 10 1 1 O-16 0.000000 0.000000 +65 10 1 1 B-10 0.000000 0.000000 +66 10 1 1 B-11 0.000000 0.000000 +67 10 1 1 Fe-54 0.000000 0.000000 +68 10 1 1 Fe-56 0.000000 0.000000 +69 10 1 1 Fe-57 0.000000 0.000000 +70 10 1 1 Fe-58 0.000000 0.000000 +71 10 1 1 Ni-58 0.000000 0.000000 +72 10 1 1 Ni-60 0.000000 0.000000 +73 10 1 1 Ni-61 0.000000 0.000000 +74 10 1 1 Ni-62 0.000000 0.000000 +75 10 1 1 Ni-64 0.000000 0.000000 +76 10 1 1 Mn-55 0.000000 0.000000 +77 10 1 1 Si-28 0.000000 0.000000 +78 10 1 1 Si-29 0.000000 0.000000 +79 10 1 1 Si-30 0.000000 0.000000 +80 10 1 1 Cr-50 0.111571 0.138458 +81 10 1 1 Cr-52 0.000000 0.000000 +82 10 1 1 Cr-53 0.000000 0.000000 +83 10 1 1 Cr-54 0.000000 0.000000 +42 10 1 2 H-1 0.000000 0.000000 +43 10 1 2 O-16 0.000000 0.000000 +44 10 1 2 B-10 0.000000 0.000000 +45 10 1 2 B-11 0.000000 0.000000 +46 10 1 2 Fe-54 0.000000 0.000000 +47 10 1 2 Fe-56 0.000000 0.000000 +48 10 1 2 Fe-57 0.000000 0.000000 +49 10 1 2 Fe-58 0.000000 0.000000 +50 10 1 2 Ni-58 0.000000 0.000000 +51 10 1 2 Ni-60 0.000000 0.000000 +52 10 1 2 Ni-61 0.000000 0.000000 +53 10 1 2 Ni-62 0.000000 0.000000 +54 10 1 2 Ni-64 0.000000 0.000000 +55 10 1 2 Mn-55 0.000000 0.000000 +56 10 1 2 Si-28 0.000000 0.000000 +57 10 1 2 Si-29 0.000000 0.000000 +58 10 1 2 Si-30 0.000000 0.000000 +59 10 1 2 Cr-50 0.000000 0.000000 +60 10 1 2 Cr-52 0.000000 0.000000 +61 10 1 2 Cr-53 0.000000 0.000000 +62 10 1 2 Cr-54 0.000000 0.000000 +21 10 2 1 H-1 0.000000 0.000000 +22 10 2 1 O-16 0.000000 0.000000 +23 10 2 1 B-10 0.000000 0.000000 +24 10 2 1 B-11 0.000000 0.000000 +25 10 2 1 Fe-54 0.000000 0.000000 +26 10 2 1 Fe-56 0.000000 0.000000 +27 10 2 1 Fe-57 0.000000 0.000000 +28 10 2 1 Fe-58 0.000000 0.000000 +29 10 2 1 Ni-58 0.000000 0.000000 +30 10 2 1 Ni-60 0.000000 0.000000 +31 10 2 1 Ni-61 0.000000 0.000000 +32 10 2 1 Ni-62 0.000000 0.000000 +33 10 2 1 Ni-64 0.000000 0.000000 +34 10 2 1 Mn-55 0.000000 0.000000 +35 10 2 1 Si-28 0.000000 0.000000 +36 10 2 1 Si-29 0.000000 0.000000 +37 10 2 1 Si-30 0.000000 0.000000 +38 10 2 1 Cr-50 0.000000 0.000000 +39 10 2 1 Cr-52 0.000000 0.000000 +40 10 2 1 Cr-53 0.000000 0.000000 +41 10 2 1 Cr-54 0.000000 0.000000 +0 10 2 2 H-1 0.000000 0.000000 +1 10 2 2 O-16 0.000000 0.000000 +2 10 2 2 B-10 0.000000 0.000000 +3 10 2 2 B-11 0.000000 0.000000 +4 10 2 2 Fe-54 0.000000 0.000000 +5 10 2 2 Fe-56 0.000000 0.000000 +6 10 2 2 Fe-57 0.000000 0.000000 +7 10 2 2 Fe-58 0.000000 0.000000 +8 10 2 2 Ni-58 0.000000 0.000000 +9 10 2 2 Ni-60 0.000000 0.000000 +10 10 2 2 Ni-61 0.000000 0.000000 +11 10 2 2 Ni-62 0.000000 0.000000 +12 10 2 2 Ni-64 0.000000 0.000000 +13 10 2 2 Mn-55 0.000000 0.000000 +14 10 2 2 Si-28 0.000000 0.000000 +15 10 2 2 Si-29 0.000000 0.000000 +16 10 2 2 Si-30 0.000000 0.000000 +17 10 2 2 Cr-50 0.000000 0.000000 +18 10 2 2 Cr-52 0.000000 0.000000 +19 10 2 2 Cr-53 0.000000 0.000000 +20 10 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. 21 10 1 H-1 0.0 0.0 22 10 1 O-16 0.0 0.0 23 10 1 B-10 0.0 0.0 @@ -1824,43 +1824,43 @@ 5 11 2 Zr-91 0.0 0.0 6 11 2 Zr-92 0.0 0.0 7 11 2 Zr-94 0.0 0.0 -8 11 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -27 11 1 1 H-1 P0 0.099594 0.442578 P0 -28 11 1 1 O-16 P0 0.028684 0.043000 P0 -29 11 1 1 B-10 P0 0.000000 0.000000 P0 -30 11 1 1 B-11 P0 0.000000 0.000000 P0 -31 11 1 1 Zr-90 P0 0.021980 0.039963 P0 -32 11 1 1 Zr-91 P0 0.000000 0.000000 P0 -33 11 1 1 Zr-92 P0 0.000000 0.000000 P0 -34 11 1 1 Zr-94 P0 0.004191 0.087344 P0 -35 11 1 1 Zr-96 P0 0.000000 0.000000 P0 -18 11 1 2 H-1 P0 0.031875 0.045078 P0 -19 11 1 2 O-16 P0 0.000000 0.000000 P0 -20 11 1 2 B-10 P0 0.000000 0.000000 P0 -21 11 1 2 B-11 P0 0.000000 0.000000 P0 -22 11 1 2 Zr-90 P0 0.000000 0.000000 P0 -23 11 1 2 Zr-91 P0 0.000000 0.000000 P0 -24 11 1 2 Zr-92 P0 0.000000 0.000000 P0 -25 11 1 2 Zr-94 P0 0.000000 0.000000 P0 -26 11 1 2 Zr-96 P0 0.000000 0.000000 P0 -9 11 2 1 H-1 P0 0.000000 0.000000 P0 -10 11 2 1 O-16 P0 0.000000 0.000000 P0 -11 11 2 1 B-10 P0 0.000000 0.000000 P0 -12 11 2 1 B-11 P0 0.000000 0.000000 P0 -13 11 2 1 Zr-90 P0 0.000000 0.000000 P0 -14 11 2 1 Zr-91 P0 0.000000 0.000000 P0 -15 11 2 1 Zr-92 P0 0.000000 0.000000 P0 -16 11 2 1 Zr-94 P0 0.000000 0.000000 P0 -17 11 2 1 Zr-96 P0 0.000000 0.000000 P0 -0 11 2 2 H-1 P0 0.687243 1.239217 P0 -1 11 2 2 O-16 P0 0.000000 0.000000 P0 -2 11 2 2 B-10 P0 0.000000 0.000000 P0 -3 11 2 2 B-11 P0 0.000000 0.000000 P0 -4 11 2 2 Zr-90 P0 0.039576 0.105193 P0 -5 11 2 2 Zr-91 P0 0.000000 0.000000 P0 -6 11 2 2 Zr-92 P0 0.084226 0.103161 P0 -7 11 2 2 Zr-94 P0 0.092039 0.125985 P0 -8 11 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +8 11 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. +27 11 1 1 H-1 0.099594 0.442578 +28 11 1 1 O-16 0.028684 0.043000 +29 11 1 1 B-10 0.000000 0.000000 +30 11 1 1 B-11 0.000000 0.000000 +31 11 1 1 Zr-90 0.021980 0.039963 +32 11 1 1 Zr-91 0.000000 0.000000 +33 11 1 1 Zr-92 0.000000 0.000000 +34 11 1 1 Zr-94 0.004191 0.087344 +35 11 1 1 Zr-96 0.000000 0.000000 +18 11 1 2 H-1 0.031875 0.045078 +19 11 1 2 O-16 0.000000 0.000000 +20 11 1 2 B-10 0.000000 0.000000 +21 11 1 2 B-11 0.000000 0.000000 +22 11 1 2 Zr-90 0.000000 0.000000 +23 11 1 2 Zr-91 0.000000 0.000000 +24 11 1 2 Zr-92 0.000000 0.000000 +25 11 1 2 Zr-94 0.000000 0.000000 +26 11 1 2 Zr-96 0.000000 0.000000 +9 11 2 1 H-1 0.000000 0.000000 +10 11 2 1 O-16 0.000000 0.000000 +11 11 2 1 B-10 0.000000 0.000000 +12 11 2 1 B-11 0.000000 0.000000 +13 11 2 1 Zr-90 0.000000 0.000000 +14 11 2 1 Zr-91 0.000000 0.000000 +15 11 2 1 Zr-92 0.000000 0.000000 +16 11 2 1 Zr-94 0.000000 0.000000 +17 11 2 1 Zr-96 0.000000 0.000000 +0 11 2 2 H-1 0.687243 1.239217 +1 11 2 2 O-16 0.000000 0.000000 +2 11 2 2 B-10 0.000000 0.000000 +3 11 2 2 B-11 0.000000 0.000000 +4 11 2 2 Zr-90 0.039576 0.105193 +5 11 2 2 Zr-91 0.000000 0.000000 +6 11 2 2 Zr-92 0.084226 0.103161 +7 11 2 2 Zr-94 0.092039 0.125985 +8 11 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. 9 11 1 H-1 0.0 0.0 10 11 1 O-16 0.0 0.0 11 11 1 B-10 0.0 0.0 @@ -1914,43 +1914,43 @@ 5 12 2 Zr-91 0.0 0.0 6 12 2 Zr-92 0.0 0.0 7 12 2 Zr-94 0.0 0.0 -8 12 2 Zr-96 0.0 0.0 material group in group out nuclide moment mean std. dev. moment -27 12 1 1 H-1 P0 0.071704 0.167588 P0 -28 12 1 1 O-16 P0 0.013270 0.020403 P0 -29 12 1 1 B-10 P0 0.000000 0.000000 P0 -30 12 1 1 B-11 P0 0.000000 0.000000 P0 -31 12 1 1 Zr-90 P0 0.089997 0.075538 P0 -32 12 1 1 Zr-91 P0 0.000000 0.000000 P0 -33 12 1 1 Zr-92 P0 0.003501 0.017031 P0 -34 12 1 1 Zr-94 P0 0.004850 0.016327 P0 -35 12 1 1 Zr-96 P0 0.002730 0.017476 P0 -18 12 1 2 H-1 P0 0.027240 0.029555 P0 -19 12 1 2 O-16 P0 0.000000 0.000000 P0 -20 12 1 2 B-10 P0 0.000000 0.000000 P0 -21 12 1 2 B-11 P0 0.000000 0.000000 P0 -22 12 1 2 Zr-90 P0 0.000000 0.000000 P0 -23 12 1 2 Zr-91 P0 0.000000 0.000000 P0 -24 12 1 2 Zr-92 P0 0.000000 0.000000 P0 -25 12 1 2 Zr-94 P0 0.000000 0.000000 P0 -26 12 1 2 Zr-96 P0 0.000000 0.000000 P0 -9 12 2 1 H-1 P0 0.000000 0.000000 P0 -10 12 2 1 O-16 P0 0.000000 0.000000 P0 -11 12 2 1 B-10 P0 0.000000 0.000000 P0 -12 12 2 1 B-11 P0 0.000000 0.000000 P0 -13 12 2 1 Zr-90 P0 0.000000 0.000000 P0 -14 12 2 1 Zr-91 P0 0.000000 0.000000 P0 -15 12 2 1 Zr-92 P0 0.000000 0.000000 P0 -16 12 2 1 Zr-94 P0 0.000000 0.000000 P0 -17 12 2 1 Zr-96 P0 0.000000 0.000000 P0 -0 12 2 2 H-1 P0 1.244758 1.956675 P0 -1 12 2 2 O-16 P0 0.079159 0.104796 P0 -2 12 2 2 B-10 P0 0.000000 0.000000 P0 -3 12 2 2 B-11 P0 0.000000 0.000000 P0 -4 12 2 2 Zr-90 P0 0.000000 0.000000 P0 -5 12 2 2 Zr-91 P0 0.033201 0.040665 P0 -6 12 2 2 Zr-92 P0 0.000000 0.000000 P0 -7 12 2 2 Zr-94 P0 0.000000 0.000000 P0 -8 12 2 2 Zr-96 P0 0.000000 0.000000 P0 material group out nuclide mean std. dev. +8 12 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. +27 12 1 1 H-1 0.071704 0.167588 +28 12 1 1 O-16 0.013270 0.020403 +29 12 1 1 B-10 0.000000 0.000000 +30 12 1 1 B-11 0.000000 0.000000 +31 12 1 1 Zr-90 0.089997 0.075538 +32 12 1 1 Zr-91 0.000000 0.000000 +33 12 1 1 Zr-92 0.003501 0.017031 +34 12 1 1 Zr-94 0.004850 0.016327 +35 12 1 1 Zr-96 0.002730 0.017476 +18 12 1 2 H-1 0.027240 0.029555 +19 12 1 2 O-16 0.000000 0.000000 +20 12 1 2 B-10 0.000000 0.000000 +21 12 1 2 B-11 0.000000 0.000000 +22 12 1 2 Zr-90 0.000000 0.000000 +23 12 1 2 Zr-91 0.000000 0.000000 +24 12 1 2 Zr-92 0.000000 0.000000 +25 12 1 2 Zr-94 0.000000 0.000000 +26 12 1 2 Zr-96 0.000000 0.000000 +9 12 2 1 H-1 0.000000 0.000000 +10 12 2 1 O-16 0.000000 0.000000 +11 12 2 1 B-10 0.000000 0.000000 +12 12 2 1 B-11 0.000000 0.000000 +13 12 2 1 Zr-90 0.000000 0.000000 +14 12 2 1 Zr-91 0.000000 0.000000 +15 12 2 1 Zr-92 0.000000 0.000000 +16 12 2 1 Zr-94 0.000000 0.000000 +17 12 2 1 Zr-96 0.000000 0.000000 +0 12 2 2 H-1 1.244758 1.956675 +1 12 2 2 O-16 0.079159 0.104796 +2 12 2 2 B-10 0.000000 0.000000 +3 12 2 2 B-11 0.000000 0.000000 +4 12 2 2 Zr-90 0.000000 0.000000 +5 12 2 2 Zr-91 0.033201 0.040665 +6 12 2 2 Zr-92 0.000000 0.000000 +7 12 2 2 Zr-94 0.000000 0.000000 +8 12 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. 9 12 1 H-1 0.0 0.0 10 12 1 O-16 0.0 0.0 11 12 1 B-10 0.0 0.0 From 47ef320ad517612376e181ec6a6bc42ca0db98ce Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 10:20:16 -0400 Subject: [PATCH 124/147] Made MGXS.domain set MGXS.domain_type to reduce burden on user --- .../pythonapi/examples/mgxs-part-i.ipynb | 34 +- .../pythonapi/examples/mgxs-part-ii.ipynb | 37 +- .../pythonapi/examples/mgxs-part-iii.ipynb | 506 ++++-------------- openmc/mgxs/mgxs.py | 9 + 4 files changed, 135 insertions(+), 451 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index 2d44d95cd..ea75bec72 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -396,9 +396,9 @@ "outputs": [], "source": [ "# Instantiate a few different sections\n", - "total = mgxs.TotalXS(domain=cell, domain_type='cell', groups=groups)\n", - "absorption = mgxs.AbsorptionXS(domain=cell, domain_type='cell', groups=groups)\n", - "scattering = mgxs.ScatterXS(domain=cell, domain_type='cell', groups=groups)" + "total = mgxs.TotalXS(domain=cell, groups=groups)\n", + "absorption = mgxs.AbsorptionXS(domain=cell, groups=groups)\n", + "scattering = mgxs.ScatterXS(domain=cell, groups=groups)" ] }, { @@ -514,7 +514,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", - " Date/Time: 2016-05-13 09:02:04\n", + " Date/Time: 2016-05-13 10:19:16\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -600,20 +600,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.2500E-01 seconds\n", - " Reading cross sections = 8.5000E-02 seconds\n", - " Total time in simulation = 1.6642E+01 seconds\n", - " Time in transport only = 1.6628E+01 seconds\n", - " Time in inactive batches = 1.9160E+00 seconds\n", - " Time in active batches = 1.4726E+01 seconds\n", - " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 2.0000E-03 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for initialization = 4.2300E-01 seconds\n", + " Reading cross sections = 9.3000E-02 seconds\n", + " Total time in simulation = 1.6549E+01 seconds\n", + " Time in transport only = 1.6535E+01 seconds\n", + " Time in inactive batches = 2.3650E+00 seconds\n", + " Time in active batches = 1.4184E+01 seconds\n", + " Time synchronizing fission bank = 5.0000E-03 seconds\n", + " Sampling source sites = 3.0000E-03 seconds\n", + " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.7076E+01 seconds\n", - " Calculation Rate (inactive) = 13048.0 neutrons/second\n", - " Calculation Rate (active) = 6790.71 neutrons/second\n", + " Total time elapsed = 1.6981E+01 seconds\n", + " Calculation Rate (inactive) = 10570.8 neutrons/second\n", + " Calculation Rate (active) = 7050.20 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", diff --git a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb index d57f2a1f3..b882e949c 100644 --- a/docs/source/pythonapi/examples/mgxs-part-ii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-ii.ipynb @@ -396,9 +396,8 @@ "for cell in openmc_cells:\n", " for rxn_type in xs_library[cell.id]:\n", "\n", - " # Set the cross sections domain type to the cell\n", + " # Set the cross sections domain to the cell\n", " xs_library[cell.id][rxn_type].domain = cell\n", - " xs_library[cell.id][rxn_type].domain_type = 'cell'\n", " \n", " # Tally cross sections by nuclide\n", " xs_library[cell.id][rxn_type].by_nuclide = True\n", @@ -446,7 +445,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", - " Date/Time: 2016-05-13 10:04:37\n", + " Date/Time: 2016-05-13 10:13:48\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -562,20 +561,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.9300E-01 seconds\n", - " Reading cross sections = 1.0800E-01 seconds\n", - " Total time in simulation = 2.2830E+02 seconds\n", - " Time in transport only = 2.2826E+02 seconds\n", - " Time in inactive batches = 1.5534E+01 seconds\n", - " Time in active batches = 2.1277E+02 seconds\n", - " Time synchronizing fission bank = 1.8000E-02 seconds\n", - " Sampling source sites = 1.3000E-02 seconds\n", - " SEND/RECV source sites = 4.0000E-03 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", - " Total time for finalization = 1.1000E-02 seconds\n", - " Total time elapsed = 2.2887E+02 seconds\n", - " Calculation Rate (inactive) = 6437.49 neutrons/second\n", - " Calculation Rate (active) = 1879.96 neutrons/second\n", + " Total time for initialization = 5.7400E-01 seconds\n", + " Reading cross sections = 1.2600E-01 seconds\n", + " Total time in simulation = 2.6256E+02 seconds\n", + " Time in transport only = 2.6250E+02 seconds\n", + " Time in inactive batches = 2.2890E+01 seconds\n", + " Time in active batches = 2.3967E+02 seconds\n", + " Time synchronizing fission bank = 3.4000E-02 seconds\n", + " Sampling source sites = 2.1000E-02 seconds\n", + " SEND/RECV source sites = 1.3000E-02 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", + " Total time for finalization = 1.3000E-02 seconds\n", + " Total time elapsed = 2.6320E+02 seconds\n", + " Calculation Rate (inactive) = 4368.72 neutrons/second\n", + " Calculation Rate (active) = 1668.93 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1783,7 +1782,7 @@ "data": { "image/png": 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QJiJHAEOBeSJSCOyS3GKpXGezwaRJzc+lXLvWxpIlmb+bbaKXz6irs7XoeUol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\n+KP1PP8hsU6nNWku3KqsyVy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GugNni0h3YC/ge+9p2bHgi1I7oVMnz05tMxruRl5S4uHw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\nCqHJQSmlVAhNDkoppUL8Pzlt5uQccjZkAAAAAElFTkSuQmCC\n", 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 15bf06b24..152a68aff 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -23,24 +23,11 @@ }, { "cell_type": "code", - "execution_count": 1, + "execution_count": 71, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stderr", - "output_type": "stream", - "text": [ - "/usr/local/lib/python2.7/dist-packages/matplotlib-1.5.1+1178.ga40c9ec-py2.7-linux-x86_64.egg/matplotlib/__init__.py:1362: UserWarning: This call to matplotlib.use() has no effect\n", - "because the backend has already been chosen;\n", - "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", - "or matplotlib.backends is imported for the first time.\n", - "\n", - " warnings.warn(_use_error_msg)\n" - ] - } - ], + "outputs": [], "source": [ "import math\n", "import pickle\n", @@ -68,7 +55,7 @@ }, { "cell_type": "code", - "execution_count": 2, + "execution_count": 72, "metadata": { "collapsed": false }, @@ -92,7 +79,7 @@ }, { "cell_type": "code", - "execution_count": 3, + "execution_count": 73, "metadata": { "collapsed": true }, @@ -127,7 +114,7 @@ }, { "cell_type": "code", - "execution_count": 4, + "execution_count": 74, "metadata": { "collapsed": true }, @@ -150,7 +137,7 @@ }, { "cell_type": "code", - "execution_count": 5, + "execution_count": 75, "metadata": { "collapsed": true }, @@ -178,7 +165,7 @@ }, { "cell_type": "code", - "execution_count": 6, + "execution_count": 76, "metadata": { "collapsed": true }, @@ -215,7 +202,7 @@ }, { "cell_type": "code", - "execution_count": 7, + "execution_count": 77, "metadata": { "collapsed": true }, @@ -252,7 +239,7 @@ }, { "cell_type": "code", - "execution_count": 8, + "execution_count": 78, "metadata": { "collapsed": true }, @@ -274,7 +261,7 @@ }, { "cell_type": "code", - "execution_count": 9, + "execution_count": 79, "metadata": { "collapsed": true }, @@ -306,7 +293,7 @@ }, { "cell_type": "code", - "execution_count": 10, + "execution_count": 80, "metadata": { "collapsed": true }, @@ -333,7 +320,7 @@ }, { "cell_type": "code", - "execution_count": 11, + "execution_count": 81, "metadata": { "collapsed": true }, @@ -346,7 +333,7 @@ }, { "cell_type": "code", - "execution_count": 12, + "execution_count": 82, "metadata": { "collapsed": true }, @@ -365,7 +352,7 @@ }, { "cell_type": "code", - "execution_count": 13, + "execution_count": 83, "metadata": { "collapsed": false }, @@ -401,7 +388,7 @@ }, { "cell_type": "code", - "execution_count": 14, + "execution_count": 57, "metadata": { "collapsed": true }, @@ -429,7 +416,7 @@ }, { "cell_type": "code", - "execution_count": 15, + "execution_count": 58, "metadata": { "collapsed": false }, @@ -440,7 +427,7 @@ "0" ] }, - "execution_count": 15, + "execution_count": 58, "metadata": {}, "output_type": "execute_result" } @@ -452,19 +439,19 @@ }, { "cell_type": "code", - "execution_count": 16, + "execution_count": 59, "metadata": { "collapsed": false }, "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] }, - "execution_count": 16, + "execution_count": 59, "metadata": {}, "output_type": "execute_result" } @@ -500,7 +487,7 @@ }, { "cell_type": "code", - "execution_count": 17, + "execution_count": 60, "metadata": { "collapsed": false }, @@ -520,7 +507,7 @@ }, { "cell_type": "code", - "execution_count": 18, + "execution_count": 61, "metadata": { "collapsed": false }, @@ -558,7 +545,7 @@ }, { "cell_type": "code", - "execution_count": 19, + "execution_count": 62, "metadata": { "collapsed": false }, @@ -579,14 +566,14 @@ }, { "cell_type": "code", - "execution_count": 20, + "execution_count": 63, "metadata": { "collapsed": true }, "outputs": [], "source": [ "# Specify a \"cell\" domain type for the cross section tally filters\n", - "mgxs_lib.domain_type = \"cell\"\n", + "mgxs_lib.domain_type = 'cell'\n", "\n", "# Specify the cell domains over which to compute multi-group cross sections\n", "mgxs_lib.domains = geometry.get_all_material_cells()" @@ -601,7 +588,7 @@ }, { "cell_type": "code", - "execution_count": 21, + "execution_count": 64, "metadata": { "collapsed": true }, @@ -620,7 +607,7 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 65, "metadata": { "collapsed": true }, @@ -641,7 +628,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 66, "metadata": { "collapsed": true }, @@ -661,7 +648,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 67, "metadata": { "collapsed": false }, @@ -689,7 +676,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 68, "metadata": { "collapsed": true }, @@ -701,7 +688,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 69, "metadata": { "collapsed": false }, @@ -727,7 +714,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", - " Date/Time: 2016-05-13 09:04:22\n", + " Date/Time: 2016-05-13 10:12:20\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -814,20 +801,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.4100E-01 seconds\n", - " Reading cross sections = 1.0500E-01 seconds\n", - " Total time in simulation = 5.1887E+01 seconds\n", - " Time in transport only = 5.1864E+01 seconds\n", - " Time in inactive batches = 3.9000E+00 seconds\n", - " Time in active batches = 4.7987E+01 seconds\n", - " Time synchronizing fission bank = 5.0000E-03 seconds\n", - " Sampling source sites = 1.0000E-03 seconds\n", - " SEND/RECV source sites = 4.0000E-03 seconds\n", - " Time accumulating tallies = 2.0000E-03 seconds\n", + " Total time for initialization = 5.0700E-01 seconds\n", + " Reading cross sections = 1.0600E-01 seconds\n", + " Total time in simulation = 6.4501E+01 seconds\n", + " Time in transport only = 6.4461E+01 seconds\n", + " Time in inactive batches = 5.2590E+00 seconds\n", + " Time in active batches = 5.9242E+01 seconds\n", + " Time synchronizing fission bank = 4.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 3.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 5.2448E+01 seconds\n", - " Calculation Rate (inactive) = 6410.26 neutrons/second\n", - " Calculation Rate (active) = 2083.90 neutrons/second\n", + " Total time elapsed = 6.5026E+01 seconds\n", + " Calculation Rate (inactive) = 4753.76 neutrons/second\n", + " Calculation Rate (active) = 1687.99 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -845,7 +832,7 @@ "0" ] }, - "execution_count": 26, + "execution_count": 69, "metadata": {}, "output_type": "execute_result" } @@ -871,11 +858,32 @@ }, { "cell_type": "code", - "execution_count": 27, + "execution_count": 70, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "ename": "KeyError", + "evalue": "'Unable to open object (Component not found)'", + "output_type": "error", + "traceback": [ + "\u001b[1;31m---------------------------------------------------------------------------\u001b[0m", + "\u001b[1;31mKeyError\u001b[0m Traceback (most recent call last)", + "\u001b[1;32m\u001b[0m in \u001b[0;36m\u001b[1;34m()\u001b[0m\n\u001b[0;32m 1\u001b[0m \u001b[1;31m# Load the last statepoint file\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m----> 2\u001b[1;33m \u001b[0msp\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mopenmc\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mStatePoint\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;34m'statepoint.50.h5'\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m", + "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36m__init__\u001b[1;34m(self, filename, autolink)\u001b[0m\n\u001b[0;32m 135\u001b[0m \u001b[1;32mif\u001b[0m \u001b[0mos\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mpath\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mexists\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mpath_summary\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 136\u001b[0m \u001b[0msu\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mopenmc\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mSummary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mpath_summary\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 137\u001b[1;33m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mlink_with_summary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0msu\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 138\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 139\u001b[0m \u001b[1;32mdef\u001b[0m \u001b[0mclose\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mself\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", + "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36mlink_with_summary\u001b[1;34m(self, summary)\u001b[0m\n\u001b[0;32m 639\u001b[0m \u001b[1;32mraise\u001b[0m \u001b[0mValueError\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mmsg\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 640\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 641\u001b[1;33m \u001b[1;32mfor\u001b[0m \u001b[0mtally_id\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mtally\u001b[0m \u001b[1;32min\u001b[0m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mtallies\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mitems\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 642\u001b[0m \u001b[0msummary_tally\u001b[0m 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\u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0m_f\u001b[0m\u001b[1;33m[\u001b[0m\u001b[1;34m'{0}{1}/n_realizations'\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mformat\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mbase\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mtally_key\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m]\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mvalue\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 379\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 380\u001b[0m \u001b[1;31m# Create Tally object and assign basic properties\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", + "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2453)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 52\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mneeded\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mit\u001b[0m \u001b[0macquires\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mand\u001b[0m \u001b[0mnotifies\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mfirst\u001b[0m \u001b[0mthread\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 54\u001b[1;33m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 55\u001b[0m \"\"\"\n\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", + "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2410)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 54\u001b[0m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 55\u001b[1;33m \"\"\"\n\u001b[0m\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 57\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mlong\u001b[0m \u001b[0m_owner\u001b[0m \u001b[1;31m# ID of thread owning the lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", + "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/h5py-2.5.0-py2.7-linux-x86_64.egg/h5py/_hl/group.pyc\u001b[0m in \u001b[0;36m__getitem__\u001b[1;34m(self, name)\u001b[0m\n\u001b[0;32m 162\u001b[0m \u001b[1;32mraise\u001b[0m \u001b[0mValueError\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;34m\"Invalid HDF5 object reference\"\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 163\u001b[0m \u001b[1;32melse\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 164\u001b[1;33m \u001b[0moid\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mh5o\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mopen\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mid\u001b[0m\u001b[1;33m,\u001b[0m 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"\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2410)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 54\u001b[0m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 55\u001b[1;33m \"\"\"\n\u001b[0m\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 57\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mlong\u001b[0m \u001b[0m_owner\u001b[0m \u001b[1;31m# ID of thread owning the lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", + "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/h5o.pyx\u001b[0m in \u001b[0;36mh5py.h5o.open (/home/wboyd/Downloads/h5py-2.5.0/h5py/h5o.c:3363)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 188\u001b[0m char* dst_name, PropID copypl=None, PropID lcpl=None):\n\u001b[0;32m 189\u001b[0m \"\"\"(ObjectID src_loc, STRING src_name, GroupID dst_loc, STRING dst_name,\n\u001b[1;32m--> 190\u001b[1;33m PropID copypl=None, PropID lcpl=None)\n\u001b[0m\u001b[0;32m 191\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 192\u001b[0m \u001b[0mCopy\u001b[0m \u001b[0ma\u001b[0m \u001b[0mgroup\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mdataset\u001b[0m \u001b[1;32mor\u001b[0m \u001b[0mnamed\u001b[0m \u001b[0mdatatype\u001b[0m \u001b[1;32mfrom\u001b[0m \u001b[0mone\u001b[0m \u001b[0mlocation\u001b[0m \u001b[0mto\u001b[0m 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cellgroup innuclidemeanstd. dev.
3100001U-2358.055246e-032.857567e-05
4100001U-2387.339215e-034.349466e-05
5100001O-160.000000e+000.000000e+00
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1100002U-2386.742638e-073.795256e-09
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\n", - "
" - ], - "text/plain": [ - " cell group in nuclide mean std. dev.\n", - "3 10000 1 U-235 8.055246e-03 2.857567e-05\n", - "4 10000 1 U-238 7.339215e-03 4.349466e-05\n", - "5 10000 1 O-16 0.000000e+00 0.000000e+00\n", - "0 10000 2 U-235 3.615565e-01 2.050486e-03\n", - "1 10000 2 U-238 6.742638e-07 3.795256e-09\n", - "2 10000 2 O-16 0.000000e+00 0.000000e+00" - ] - }, - "execution_count": 30, - "metadata": {}, - "output_type": "execute_result" - } - ], + "outputs": [], "source": [ "df = fuel_mgxs.get_pandas_dataframe()\n", "df" @@ -1053,39 +971,11 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "Multi-Group XS\n", - "\tReaction Type =\tnu-fission\n", - "\tDomain Type =\tcell\n", - "\tDomain ID =\t10000\n", - "\tNuclide =\tU-235\n", - "\tCross Sections [cm^-1]:\n", - " Group 1 [6.25e-07 - 20.0 MeV]:\t8.06e-03 +/- 3.55e-01%\n", - " Group 2 [0.0 - 6.25e-07 MeV]:\t3.62e-01 +/- 5.67e-01%\n", - "\n", - "\tNuclide =\tU-238\n", - "\tCross Sections [cm^-1]:\n", - " Group 1 [6.25e-07 - 20.0 MeV]:\t7.34e-03 +/- 5.93e-01%\n", - " Group 2 [0.0 - 6.25e-07 MeV]:\t6.74e-07 +/- 5.63e-01%\n", - "\n", - "\tNuclide =\tO-16\n", - "\tCross Sections [cm^-1]:\n", - " Group 1 [6.25e-07 - 20.0 MeV]:\t0.00e+00 +/- nan%\n", - " Group 2 [0.0 - 6.25e-07 MeV]:\t0.00e+00 +/- nan%\n", - "\n", - "\n", - "\n" - ] - } - ], + "outputs": [], "source": [ "fuel_mgxs.print_xs()" ] @@ -1099,7 +989,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": null, "metadata": { "collapsed": false }, @@ -1118,7 +1008,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": null, "metadata": { "collapsed": true }, @@ -1130,7 +1020,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": null, "metadata": { "collapsed": true }, @@ -1149,7 +1039,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": null, "metadata": { "collapsed": true }, @@ -1164,67 +1054,11 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "data": { - "text/html": [ - "
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cellgroup innuclidemeanstd. dev.
0100001U-2350.0748600.000303
1100001U-2380.0059520.000035
2100001O-160.0000000.000000
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" - ], - "text/plain": [ - " cell group in nuclide mean std. dev.\n", - "0 10000 1 U-235 0.074860 0.000303\n", - "1 10000 1 U-238 0.005952 0.000035\n", - "2 10000 1 O-16 0.000000 0.000000" - ] - }, - "execution_count": 36, - "metadata": {}, - "output_type": "execute_result" - } - ], + "outputs": [], "source": [ "# Retrieve the NuFissionXS object for the fuel cell from the 1-group library\n", "coarse_fuel_mgxs = coarse_mgxs_lib.get_mgxs(fuel_cell, 'nu-fission')\n", @@ -1249,7 +1083,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": null, "metadata": { "collapsed": false }, @@ -1268,7 +1102,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": null, "metadata": { "collapsed": false }, @@ -1287,139 +1121,12 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": null, "metadata": { "collapsed": false, "scrolled": true }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "[ NORMAL ] Importing ray tracing data from file...\n", - "[ NORMAL ] Computing the eigenvalue...\n", - "[ NORMAL ] Iteration 0:\tk_eff = 0.854370\tres = 0.000E+00\n", - "[ NORMAL ] Iteration 1:\tk_eff = 0.801922\tres = 1.521E-01\n", - "[ NORMAL ] Iteration 2:\tk_eff = 0.761745\tres = 6.349E-02\n", - "[ NORMAL ] Iteration 3:\tk_eff = 0.732366\tres = 5.029E-02\n", - "[ NORMAL ] Iteration 4:\tk_eff = 0.711073\tres = 3.869E-02\n", - "[ NORMAL ] Iteration 5:\tk_eff = 0.696554\tres = 2.912E-02\n", - "[ NORMAL ] Iteration 6:\tk_eff = 0.687670\tres = 2.044E-02\n", - "[ NORMAL ] Iteration 7:\tk_eff = 0.683465\tres = 1.277E-02\n", - "[ NORMAL ] Iteration 8:\tk_eff = 0.683124\tres = 6.142E-03\n", - "[ NORMAL ] Iteration 9:\tk_eff = 0.685943\tres = 7.897E-04\n", - "[ NORMAL ] Iteration 10:\tk_eff = 0.691322\tres = 4.180E-03\n", - "[ NORMAL ] Iteration 11:\tk_eff = 0.698747\tres = 7.873E-03\n", - "[ NORMAL ] Iteration 12:\tk_eff = 0.707777\tres = 1.076E-02\n", - "[ NORMAL ] Iteration 13:\tk_eff = 0.718040\tres = 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0.889870\tres = 1.125E-02\n", - "[ NORMAL ] Iteration 29:\tk_eff = 0.898748\tres = 1.061E-02\n", - "[ NORMAL ] Iteration 30:\tk_eff = 0.907172\tres = 9.985E-03\n", - "[ NORMAL ] Iteration 31:\tk_eff = 0.915151\tres = 9.382E-03\n", - "[ NORMAL ] Iteration 32:\tk_eff = 0.922693\tres = 8.802E-03\n", - "[ NORMAL ] Iteration 33:\tk_eff = 0.929811\tres = 8.248E-03\n", - "[ NORMAL ] Iteration 34:\tk_eff = 0.936517\tres = 7.720E-03\n", - "[ NORMAL ] Iteration 35:\tk_eff = 0.942827\tres = 7.219E-03\n", - "[ NORMAL ] Iteration 36:\tk_eff = 0.948757\tres = 6.744E-03\n", - "[ NORMAL ] Iteration 37:\tk_eff = 0.954322\tres = 6.295E-03\n", - "[ NORMAL ] Iteration 38:\tk_eff = 0.959539\tres = 5.871E-03\n", - "[ NORMAL ] Iteration 39:\tk_eff = 0.964425\tres = 5.472E-03\n", - "[ NORMAL ] Iteration 40:\tk_eff = 0.968996\tres = 5.096E-03\n", - "[ NORMAL ] Iteration 41:\tk_eff = 0.973268\tres = 4.744E-03\n", - "[ NORMAL ] Iteration 42:\tk_eff = 0.977259\tres = 4.413E-03\n", - "[ NORMAL ] Iteration 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- "[ NORMAL ] Iteration 88:\tk_eff = 1.027347\tres = 1.160E-04\n", - "[ NORMAL ] Iteration 89:\tk_eff = 1.027447\tres = 1.067E-04\n", - "[ NORMAL ] Iteration 90:\tk_eff = 1.027540\tres = 9.823E-05\n", - "[ NORMAL ] Iteration 91:\tk_eff = 1.027625\tres = 9.039E-05\n", - "[ NORMAL ] Iteration 92:\tk_eff = 1.027704\tres = 8.317E-05\n", - "[ NORMAL ] Iteration 93:\tk_eff = 1.027776\tres = 7.652E-05\n", - "[ NORMAL ] Iteration 94:\tk_eff = 1.027843\tres = 7.040E-05\n", - "[ NORMAL ] Iteration 95:\tk_eff = 1.027904\tres = 6.476E-05\n", - "[ NORMAL ] Iteration 96:\tk_eff = 1.027960\tres = 5.957E-05\n", - "[ NORMAL ] Iteration 97:\tk_eff = 1.028012\tres = 5.479E-05\n", - "[ NORMAL ] Iteration 98:\tk_eff = 1.028059\tres = 5.039E-05\n", - "[ NORMAL ] Iteration 99:\tk_eff = 1.028103\tres = 4.635E-05\n", - "[ NORMAL ] Iteration 100:\tk_eff = 1.028143\tres = 4.262E-05\n", - "[ NORMAL ] Iteration 101:\tk_eff = 1.028180\tres = 3.919E-05\n", - "[ NORMAL ] Iteration 102:\tk_eff = 1.028214\tres = 3.603E-05\n", - "[ NORMAL ] Iteration 103:\tk_eff = 1.028245\tres = 3.313E-05\n", - "[ NORMAL ] Iteration 104:\tk_eff = 1.028274\tres = 3.046E-05\n", - "[ NORMAL ] Iteration 105:\tk_eff = 1.028300\tres = 2.800E-05\n", - "[ NORMAL ] Iteration 106:\tk_eff = 1.028324\tres = 2.574E-05\n", - "[ NORMAL ] Iteration 107:\tk_eff = 1.028347\tres = 2.366E-05\n", - "[ NORMAL ] Iteration 108:\tk_eff = 1.028367\tres = 2.175E-05\n", - "[ NORMAL ] Iteration 109:\tk_eff = 1.028386\tres = 1.999E-05\n", - "[ NORMAL ] Iteration 110:\tk_eff = 1.028403\tres = 1.837E-05\n", - "[ NORMAL ] Iteration 111:\tk_eff = 1.028419\tres = 1.688E-05\n", - "[ NORMAL ] Iteration 112:\tk_eff = 1.028434\tres = 1.551E-05\n", - "[ NORMAL ] Iteration 113:\tk_eff = 1.028447\tres = 1.426E-05\n", - "[ NORMAL ] Iteration 114:\tk_eff = 1.028460\tres = 1.310E-05\n", - "[ NORMAL ] Iteration 115:\tk_eff = 1.028471\tres = 1.204E-05\n", - "[ NORMAL ] Iteration 116:\tk_eff = 1.028481\tres = 1.106E-05\n", - "[ NORMAL ] Iteration 117:\tk_eff = 1.028491\tres = 1.016E-05\n" - ] - } - ], + "outputs": [], "source": [ "# Generate tracks for OpenMOC\n", "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=32, azim_spacing=0.1)\n", @@ -1439,21 +1146,11 @@ }, { "cell_type": "code", - "execution_count": 40, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "name": "stdout", - "output_type": "stream", - "text": [ - "openmc keff = 1.028263\n", - "openmoc keff = 1.028491\n", - "bias [pcm]: 22.8\n" - ] - } - ], + "outputs": [], "source": [ "# Print report of keff and bias with OpenMC\n", "openmoc_keff = solver.getKeff()\n", @@ -1492,7 +1189,7 @@ }, { "cell_type": "code", - "execution_count": 41, + "execution_count": null, "metadata": { "collapsed": false }, @@ -1518,7 +1215,7 @@ }, { "cell_type": "code", - "execution_count": 42, + "execution_count": null, "metadata": { "collapsed": false }, @@ -1550,32 +1247,11 @@ }, { "cell_type": "code", - "execution_count": 43, + "execution_count": null, "metadata": { "collapsed": false }, - "outputs": [ - { - "data": { - "text/plain": [ - "" - ] - }, - "execution_count": 43, - "metadata": {}, - "output_type": "execute_result" - }, - { - "data": { - "image/png": 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- "text/plain": [ - "" - ] - }, - "metadata": {}, - "output_type": "display_data" - } - ], + "outputs": [], "source": [ "# Ignore zero fission rates in guide tubes with Matplotlib color scheme\n", "openmc_fission_rates[openmc_fission_rates == 0] = np.nan\n", diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index eff0bde0a..182691283 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -368,6 +368,15 @@ class MGXS(object): cv.check_type('domain', domain, tuple(_DOMAINS)) self._domain = domain + # Assign a domain type + if self.domain_type is None: + if isinstance(domain, openmc.Material): + self._domain_type = 'material' + elif isinstance(domain, openmc.Cell): + self._domain_type = 'cell' + elif isinstance(domain, openmc.Universe): + self._domain_type = 'universe' + @domain_type.setter def domain_type(self, domain_type): cv.check_value('domain type', domain_type, tuple(DOMAIN_TYPES)) From c31d6232267dd5811c88e2feb05e3806b83bdd11 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 13 May 2016 08:44:21 -0500 Subject: [PATCH 125/147] Ability to read from attributes on HDF5 groups/datasets --- src/hdf5_interface.F90 | 918 ++++++++++++++++++++++++++++----------- src/initialize.F90 | 4 +- src/particle_restart.F90 | 30 +- src/source.F90 | 2 +- src/state_point.F90 | 72 +-- 5 files changed, 712 insertions(+), 314 deletions(-) diff --git a/src/hdf5_interface.F90 b/src/hdf5_interface.F90 index 01e50d983..ce934baa4 100644 --- a/src/hdf5_interface.F90 +++ b/src/hdf5_interface.F90 @@ -64,14 +64,28 @@ module hdf5_interface module procedure read_tally_result_2D end interface read_dataset + interface read_attribute + module procedure read_attribute_double + module procedure read_attribute_double_1D + module procedure read_attribute_double_2D + module procedure read_attribute_integer + module procedure read_attribute_integer_1D + module procedure read_attribute_integer_2D + module procedure read_attribute_string + end interface read_attribute + public :: write_dataset public :: read_dataset + public :: read_attribute public :: file_create public :: file_open public :: file_close public :: create_group public :: open_group public :: close_group + public :: open_dataset + public :: close_dataset + public :: get_shape public :: write_attribute_string contains @@ -243,6 +257,44 @@ contains end if end subroutine close_group +!=============================================================================== +! OPEN_DATASET opens an existing HDF5 dataset +!=============================================================================== + + function open_dataset(group_id, name) result(dataset_id) + integer(HID_T), intent(in) :: group_id + character(*), intent(in) :: name ! name of dataset + integer(HID_T) :: dataset_id + + logical :: exists ! does the dataset exist + integer :: hdf5_err ! HDF5 error code + + ! Check if group exists + call h5ltpath_valid_f(group_id, trim(name), .true., exists, hdf5_err) + + ! open group if it exists + if (exists) then + call h5dopen_f(group_id, trim(name), dataset_id, hdf5_err) + else + call fatal_error("The dataset '" // trim(name) // "' does not exist.") + end if + end function open_dataset + +!=============================================================================== +! CLOSE_GROUP closes HDF5 temp_group +!=============================================================================== + + subroutine close_dataset(dataset_id) + integer(HID_T), intent(inout) :: dataset_id + + integer :: hdf5_err ! HDF5 error code + + call h5dclose_f(dataset_id, hdf5_err) + if (hdf5_err < 0) then + call fatal_error("Unable to close HDF5 dataset.") + end if + end subroutine close_dataset + !=============================================================================== ! WRITE_DOUBLE writes double precision scalar data !=============================================================================== @@ -293,19 +345,27 @@ contains ! READ_DOUBLE reads double precision scalar data !=============================================================================== - subroutine read_double(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name for data - real(8), intent(inout), target :: buffer ! read data to here - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double(buffer, obj_id, name, indep) + real(8), target, intent(inout) :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O - integer :: hdf5_err - integer :: data_xfer_mode + integer :: hdf5_err + integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle - type(c_ptr) :: f_ptr + integer(HID_T) :: dset_id + type(c_ptr) :: f_ptr + + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) + else + dset_id = obj_id + end if ! Set up collective vs. independent I/O data_xfer_mode = H5FD_MPIO_COLLECTIVE_F @@ -313,21 +373,20 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) end if - call h5dclose_f(dset, hdf5_err) + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_double !=============================================================================== @@ -396,35 +455,46 @@ contains ! READ_DOUBLE_1D reads double precision 1-D array data !=============================================================================== - subroutine read_double_1D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_1D(buffer, obj_id, name, indep) + real(8), target, intent(inout) :: buffer(:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(1) - dims(:) = shape(buffer) - if (present(indep)) then - call read_double_1D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_double_1D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_double_1D_explicit(dset_id, dims, buffer, indep) + else + call read_double_1D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_double_1D - subroutine read_double_1D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(1) - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(dims(1)) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_1D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(1) + real(8), target, intent(inout) :: buffer(dims(1)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -433,21 +503,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_double_1D_explicit !=============================================================================== @@ -516,35 +583,46 @@ contains ! READ_DOUBLE_2D reads double precision 2-D array data !=============================================================================== - subroutine read_double_2D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_2D(buffer, obj_id, name, indep) + real(8), target, intent(inout) :: buffer(:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(2) - dims(:) = shape(buffer) - if (present(indep)) then - call read_double_2D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_double_2D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_double_2D_explicit(dset_id, dims, buffer, indep) + else + call read_double_2D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_double_2D - subroutine read_double_2D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(2) - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(dims(1),dims(2)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_2D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(2) + real(8), target, intent(inout) :: buffer(dims(1),dims(2)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -553,21 +631,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_double_2D_explicit !=============================================================================== @@ -636,35 +711,46 @@ contains ! READ_DOUBLE_3D reads double precision 3-D array data !=============================================================================== - subroutine read_double_3D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(:,:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_3D(buffer, obj_id, name, indep) + real(8), target, intent(inout) :: buffer(:,:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(3) - dims(:) = shape(buffer) - if (present(indep)) then - call read_double_3D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_double_3D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_double_3D_explicit(dset_id, dims, buffer, indep) + else + call read_double_3D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_double_3D - subroutine read_double_3D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(3) - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(dims(1),dims(2),dims(3)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_3D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(3) + real(8), target, intent(inout) :: buffer(dims(1),dims(2),dims(3)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -673,21 +759,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_double_3D_explicit !=============================================================================== @@ -756,35 +839,46 @@ contains ! READ_DOUBLE_4D reads double precision 4-D array data !=============================================================================== - subroutine read_double_4D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(:,:,:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_4D(buffer, obj_id, name, indep) + real(8), target, intent(inout) :: buffer(:,:,:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(4) - dims(:) = shape(buffer) - if (present(indep)) then - call read_double_4D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_double_4D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_double_4D_explicit(dset_id, dims, buffer, indep) + else + call read_double_4D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_double_4D - subroutine read_double_4D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(4) - character(*), intent(in) :: name ! name of data - real(8), intent(inout), target :: buffer(dims(1),dims(2),dims(3),dims(4)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_double_4D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(4) + real(8), target, intent(inout) :: buffer(dims(1),dims(2),dims(3),dims(4)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -793,21 +887,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_double_4D_explicit !=============================================================================== @@ -860,19 +951,27 @@ contains ! READ_INTEGER reads integer precision scalar data !=============================================================================== - subroutine read_integer(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name for data - integer, intent(inout), target :: buffer ! read data to here - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer(buffer, obj_id, name, indep) + integer, target, intent(inout) :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O - integer :: hdf5_err - integer :: data_xfer_mode + integer :: hdf5_err + integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle - type(c_ptr) :: f_ptr + integer(HID_T) :: dset_id + type(c_ptr) :: f_ptr + + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) + else + dset_id = obj_id + end if ! Set up collective vs. independent I/O data_xfer_mode = H5FD_MPIO_COLLECTIVE_F @@ -880,21 +979,20 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) end if - call h5dclose_f(dset, hdf5_err) + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_integer !=============================================================================== @@ -963,35 +1061,46 @@ contains ! READ_INTEGER_1D reads integer precision 1-D array data !=============================================================================== - subroutine read_integer_1D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_1D(buffer, obj_id, name, indep) + integer, target, intent(inout) :: buffer(:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(1) - dims(:) = shape(buffer) - if (present(indep)) then - call read_integer_1D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_integer_1D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_integer_1D_explicit(dset_id, dims, buffer, indep) + else + call read_integer_1D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_integer_1D - subroutine read_integer_1D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(1) - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(dims(1)) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_1D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(1) + integer, target, intent(inout) :: buffer(dims(1)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -1000,21 +1109,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_integer_1D_explicit !=============================================================================== @@ -1083,35 +1189,46 @@ contains ! READ_INTEGER_2D reads integer precision 2-D array data !=============================================================================== - subroutine read_integer_2D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_2D(buffer, obj_id, name, indep) + integer, target, intent(inout) :: buffer(:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(2) - dims(:) = shape(buffer) - if (present(indep)) then - call read_integer_2D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_integer_2D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_integer_2D_explicit(dset_id, dims, buffer, indep) + else + call read_integer_2D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_integer_2D - subroutine read_integer_2D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(2) - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(dims(1),dims(2)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_2D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(2) + integer, target, intent(inout) :: buffer(dims(1),dims(2)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -1120,21 +1237,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_integer_2D_explicit !=============================================================================== @@ -1203,35 +1317,46 @@ contains ! READ_INTEGER_3D reads integer precision 3-D array data !=============================================================================== - subroutine read_integer_3D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(:,:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_3D(buffer, obj_id, name, indep) + integer, target, intent(inout) :: buffer(:,:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(3) - dims(:) = shape(buffer) - if (present(indep)) then - call read_integer_3D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_integer_3D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_integer_3D_explicit(dset_id, dims, buffer, indep) + else + call read_integer_3D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_integer_3D - subroutine read_integer_3D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(3) - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(dims(1),dims(2),dims(3)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_3D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(3) + integer, target, intent(inout) :: buffer(dims(1),dims(2),dims(3)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -1240,21 +1365,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_integer_3D_explicit !=============================================================================== @@ -1323,35 +1445,46 @@ contains ! READ_INTEGER_4D reads integer precision 4-D array data !=============================================================================== - subroutine read_integer_4D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(:,:,:,:) ! data to write - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_4D(buffer, obj_id, name, indep) + integer, target, intent(inout) :: buffer(:,:,:,:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(4) - dims(:) = shape(buffer) - if (present(indep)) then - call read_integer_4D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_integer_4D_explicit(group_id, dims, name, buffer) + dset_id = obj_id end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_integer_4D_explicit(dset_id, dims, buffer, indep) + else + call read_integer_4D_explicit(dset_id, dims, buffer) + end if + + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_integer_4D - subroutine read_integer_4D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(4) - character(*), intent(in) :: name ! name of data - integer, intent(inout), target :: buffer(dims(1),dims(2),dims(3),dims(4)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_integer_4D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(4) + integer, target, intent(inout) :: buffer(dims(1),dims(2),dims(3),dims(4)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle type(c_ptr) :: f_ptr ! Set up collective vs. independent I/O @@ -1360,21 +1493,18 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5dread_f(dset_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) end if - - call h5dclose_f(dset, hdf5_err) end subroutine read_integer_4D_explicit !=============================================================================== @@ -1427,19 +1557,27 @@ contains ! READ_LONG reads long integer scalar data !=============================================================================== - subroutine read_long(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name for data - integer(8), intent(inout), target :: buffer ! read data to here - logical, intent(in), optional :: indep ! independent I/O + subroutine read_long(buffer, obj_id, name, indep) + integer(8), target, intent(inout) :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O - integer :: hdf5_err - integer :: data_xfer_mode + integer :: hdf5_err + integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle - type(c_ptr) :: f_ptr + integer(HID_T) :: dset_id + type(c_ptr) :: f_ptr + + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) + else + dset_id = obj_id + end if ! Set up collective vs. independent I/O data_xfer_mode = H5FD_MPIO_COLLECTIVE_F @@ -1447,21 +1585,20 @@ contains if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - call h5dopen_f(group_id, trim(name), dset, hdf5_err) f_ptr = c_loc(buffer) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, hdf5_integer8_t, f_ptr, hdf5_err, xfer_prp=plist) + call h5dread_f(dset_id, hdf5_integer8_t, f_ptr, hdf5_err, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, hdf5_integer8_t, f_ptr, hdf5_err) + call h5dread_f(dset_id, hdf5_integer8_t, f_ptr, hdf5_err) end if - call h5dclose_f(dset, hdf5_err) + if (present(name)) call h5dclose_f(dset_id, hdf5_err) end subroutine read_long !=============================================================================== @@ -1529,37 +1666,42 @@ contains ! READ_STRING reads string data !=============================================================================== - subroutine read_string(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name ! name for data - character(*), intent(inout), target :: buffer ! read data to here - logical, intent(in), optional :: indep ! independent I/O + subroutine read_string(buffer, obj_id, name, indep) + character(*), target, intent(inout) :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle - integer(HID_T) :: dspace ! data or file space handle + integer(HID_T) :: dset_id + integer(HID_T) :: space_id integer(HID_T) :: filetype integer(HID_T) :: memtype integer(SIZE_T) :: size integer(SIZE_T) :: n type(c_ptr) :: f_ptr + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) + else + dset_id = obj_id + end if + ! Set up collective vs. independent I/O data_xfer_mode = H5FD_MPIO_COLLECTIVE_F if (present(indep)) then if (indep) data_xfer_mode = H5FD_MPIO_INDEPENDENT_F end if - ! Get dataset and dataspace - call h5dopen_f(group_id, trim(name), dset, hdf5_err) - call h5dget_space_f(dset, dspace, hdf5_err) + ! Get dataspace + call h5dget_space_f(dset_id, space_id, hdf5_err) ! Make sure buffer is large enough - call h5dget_type_f(dset, filetype, hdf5_err) + call h5dget_type_f(dset_id, filetype, hdf5_err) call h5tget_size_f(filetype, size, hdf5_err) if (size > len(buffer) + 1) then call fatal_error("Character buffer is not long enough to & @@ -1574,20 +1716,21 @@ contains ! Get pointer to start of string f_ptr = c_loc(buffer(1:1)) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, memtype, f_ptr, hdf5_err, mem_space_id=dspace, & - xfer_prp=plist) + call h5dread_f(dset_id, memtype, f_ptr, hdf5_err, & + mem_space_id=space_id, xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, memtype, f_ptr, hdf5_err, mem_space_id=dspace) + call h5dread_f(dset_id, memtype, f_ptr, hdf5_err, mem_space_id=space_id) end if - call h5dclose_f(dset, hdf5_err) - call h5sclose_f(dspace, hdf5_err) + if (present(name)) call h5dclose_f(dset_id, hdf5_err) + + call h5sclose_f(space_id, hdf5_err) call h5tclose_f(filetype, hdf5_err) call h5tclose_f(memtype, hdf5_err) end subroutine read_string @@ -1674,36 +1817,45 @@ contains ! READ_STRING_1D reads string 1-D array data !=============================================================================== - subroutine read_string_1D(group_id, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - character(*), intent(in) :: name - character(*), intent(inout), target :: buffer(:) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_string_1D(buffer, obj_id, name, indep) + character(*), target, intent(inout) :: buffer(:) + integer(HID_T), intent(in) :: obj_id + character(*), optional, intent(in) :: name + logical, optional, intent(in) :: indep ! independent I/O + integer :: hdf5_err + integer(HID_T) :: dset_id integer(HSIZE_T) :: dims(1) - dims(:) = shape(buffer) - if (present(indep)) then - call read_string_1D_explicit(group_id, dims, name, buffer, indep) + ! If 'name' argument is passed, obj_id is interpreted to be a group and + ! 'name' is the name of the dataset we should read from + if (present(name)) then + call h5dopen_f(obj_id, trim(name), dset_id, hdf5_err) else - call read_string_1D_explicit(group_id, dims, name, buffer) + dset_id = obj_id + end if + + dims(:) = shape(buffer) + + if (present(indep)) then + call read_string_1D_explicit(dset_id, dims, buffer, indep) + else + call read_string_1D_explicit(dset_id, dims, buffer) end if end subroutine read_string_1D - subroutine read_string_1D_explicit(group_id, dims, name, buffer, indep) - integer(HID_T), intent(in) :: group_id - integer(HSIZE_T), intent(in) :: dims(1) - character(*), intent(in) :: name - character(*), intent(inout), target :: buffer(dims(1)) - logical, intent(in), optional :: indep ! independent I/O + subroutine read_string_1D_explicit(dset_id, dims, buffer, indep) + integer(HID_T), intent(in) :: dset_id + integer(HSIZE_T), intent(in) :: dims(1) + character(*), target, intent(inout) :: buffer(dims(1)) + logical, optional, intent(in) :: indep ! independent I/O integer :: hdf5_err integer :: data_xfer_mode #ifdef PHDF5 integer(HID_T) :: plist ! property list #endif - integer(HID_T) :: dset ! data set handle - integer(HID_T) :: dspace ! data or file space handle + integer(HID_T) :: space_id integer(HID_T) :: filetype integer(HID_T) :: memtype integer(SIZE_T) :: size @@ -1717,11 +1869,10 @@ contains end if ! Get dataset and dataspace - call h5dopen_f(group_id, trim(name), dset, hdf5_err) - call h5dget_space_f(dset, dspace, hdf5_err) + call h5dget_space_f(dset_id, space_id, hdf5_err) ! Make sure buffer is large enough - call h5dget_type_f(dset, filetype, hdf5_err) + call h5dget_type_f(dset_id, filetype, hdf5_err) call h5tget_size_f(filetype, size, hdf5_err) if (size > len(buffer(1)) + 1) then call fatal_error("Character buffer is not long enough to & @@ -1736,20 +1887,19 @@ contains ! Get pointer to start of string f_ptr = c_loc(buffer(1)(1:1)) - if (using_mpio_device(group_id)) then + if (using_mpio_device(dset_id)) then #ifdef PHDF5 call h5pcreate_f(H5P_DATASET_XFER_F, plist, hdf5_err) call h5pset_dxpl_mpio_f(plist, data_xfer_mode, hdf5_err) - call h5dread_f(dset, memtype, f_ptr, hdf5_err, mem_space_id=dspace, & + call h5dread_f(dset_id, memtype, f_ptr, hdf5_err, mem_space_id=space_id, & xfer_prp=plist) call h5pclose_f(plist, hdf5_err) #endif else - call h5dread_f(dset, memtype, f_ptr, hdf5_err, mem_space_id=dspace) + call h5dread_f(dset_id, memtype, f_ptr, hdf5_err, mem_space_id=space_id) end if - call h5dclose_f(dset, hdf5_err) - call h5sclose_f(dspace, hdf5_err) + call h5sclose_f(space_id, hdf5_err) call h5tclose_f(filetype, hdf5_err) call h5tclose_f(memtype, hdf5_err) end subroutine read_string_1D_explicit @@ -1893,6 +2043,254 @@ contains call h5dclose_f(dset, hdf5_err) end subroutine read_tally_result_2D_explicit + subroutine read_attribute_double(buffer, obj_id, name) + real(8), intent(inout), target :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: attr_id + type(c_ptr) :: f_ptr + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_double + + subroutine read_attribute_double_1D(buffer, obj_id, name) + real(8), target, allocatable, intent(inout) :: buffer(:) + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: space_id + integer(HID_T) :: attr_id + integer(HSIZE_T) :: dims(1) + integer(HSIZE_T) :: maxdims(1) + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + + if (allocated(buffer)) then + dims(:) = shape(buffer) + else + call h5aget_space_f(attr_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + allocate(buffer(dims(1))) + call h5sclose_f(space_id, hdf5_err) + end if + + call read_attribute_double_1D_explicit(attr_id, dims, buffer) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_double_1D + + subroutine read_attribute_double_1D_explicit(attr_id, dims, buffer) + integer(HID_T), intent(in) :: attr_id + integer(HSIZE_T), intent(in) :: dims(1) + real(8), target, intent(inout) :: buffer(dims(1)) + + integer :: hdf5_err + type(c_ptr) :: f_ptr + + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + end subroutine read_attribute_double_1D_explicit + + subroutine read_attribute_double_2D(buffer, obj_id, name) + real(8), target, allocatable, intent(inout) :: buffer(:,:) + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: space_id + integer(HID_T) :: attr_id + integer(HSIZE_T) :: dims(2) + integer(HSIZE_T) :: maxdims(2) + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + + if (allocated(buffer)) then + dims(:) = shape(buffer) + else + call h5aget_space_f(attr_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + allocate(buffer(dims(1), dims(2))) + call h5sclose_f(space_id, hdf5_err) + end if + + call read_attribute_double_2D_explicit(attr_id, dims, buffer) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_double_2D + + subroutine read_attribute_double_2D_explicit(attr_id, dims, buffer) + integer(HID_T), intent(in) :: attr_id + integer(HSIZE_T), intent(in) :: dims(2) + real(8), target, intent(inout) :: buffer(dims(1),dims(2)) + + integer :: hdf5_err + type(c_ptr) :: f_ptr + + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_DOUBLE, f_ptr, hdf5_err) + end subroutine read_attribute_double_2D_explicit + + subroutine read_attribute_integer(buffer, obj_id, name) + integer, intent(inout), target :: buffer + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: attr_id + type(c_ptr) :: f_ptr + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_integer + + subroutine read_attribute_integer_1D(buffer, obj_id, name) + integer, target, allocatable, intent(inout) :: buffer(:) + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: space_id + integer(HID_T) :: attr_id + integer(HSIZE_T) :: dims(1) + integer(HSIZE_T) :: maxdims(1) + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + + if (allocated(buffer)) then + dims(:) = shape(buffer) + else + call h5aget_space_f(attr_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + allocate(buffer(dims(1))) + call h5sclose_f(space_id, hdf5_err) + end if + + call read_attribute_integer_1D_explicit(attr_id, dims, buffer) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_integer_1D + + subroutine read_attribute_integer_1D_explicit(attr_id, dims, buffer) + integer(HID_T), intent(in) :: attr_id + integer(HSIZE_T), intent(in) :: dims(1) + integer, target, intent(inout) :: buffer(dims(1)) + + integer :: hdf5_err + type(c_ptr) :: f_ptr + + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + end subroutine read_attribute_integer_1D_explicit + + subroutine read_attribute_integer_2D(buffer, obj_id, name) + integer, target, allocatable, intent(inout) :: buffer(:,:) + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name + + integer :: hdf5_err + integer(HID_T) :: space_id + integer(HID_T) :: attr_id + integer(HSIZE_T) :: dims(2) + integer(HSIZE_T) :: maxdims(2) + + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + + if (allocated(buffer)) then + dims(:) = shape(buffer) + else + call h5aget_space_f(attr_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + allocate(buffer(dims(1), dims(2))) + call h5sclose_f(space_id, hdf5_err) + end if + + call read_attribute_integer_2D_explicit(attr_id, dims, buffer) + call h5aclose_f(attr_id, hdf5_err) + end subroutine read_attribute_integer_2D + + subroutine read_attribute_integer_2D_explicit(attr_id, dims, buffer) + integer(HID_T), intent(in) :: attr_id + integer(HSIZE_T), intent(in) :: dims(2) + integer, target, intent(inout) :: buffer(dims(1),dims(2)) + + integer :: hdf5_err + type(c_ptr) :: f_ptr + + f_ptr = c_loc(buffer) + call h5aread_f(attr_id, H5T_NATIVE_INTEGER, f_ptr, hdf5_err) + end subroutine read_attribute_integer_2D_explicit + + subroutine read_attribute_string(buffer, obj_id, name) + character(*), intent(inout), target :: buffer ! read data to here + integer(HID_T), intent(in) :: obj_id + character(*), intent(in) :: name ! name for data + + integer :: hdf5_err + integer(HID_T) :: attr_id ! data set handle + integer(HID_T) :: filetype + integer(HID_T) :: memtype + integer(SIZE_T) :: i + integer(SIZE_T) :: size + character(kind=C_CHAR), allocatable, target :: temp_buffer(:) + type(c_ptr) :: f_ptr + + ! Get dataset and dataspace + call h5aopen_f(obj_id, trim(name), attr_id, hdf5_err) + + ! Make sure buffer is large enough + call h5aget_type_f(attr_id, filetype, hdf5_err) + call h5tget_size_f(filetype, size, hdf5_err) + allocate(temp_buffer(size)) + if (size > len(buffer)) then + call fatal_error("Character buffer is not long enough to & + &read HDF5 string.") + end if + + ! Get datatype in memory based on Fortran character + call h5tcopy_f(H5T_C_S1, memtype, hdf5_err) + call h5tset_size_f(memtype, size + 1, hdf5_err) + + ! Get pointer to start of string + f_ptr = c_loc(temp_buffer(1)) + + call h5aread_f(attr_id, memtype, f_ptr, hdf5_err) + buffer = '' + do i = 1, size + buffer(i:i) = temp_buffer(i) + end do + deallocate(temp_buffer) + + call h5aclose_f(attr_id, hdf5_err) + call h5tclose_f(filetype, hdf5_err) + call h5tclose_f(memtype, hdf5_err) + end subroutine read_attribute_string + + subroutine get_shape(obj_id, dims) + integer(HID_T), intent(in) :: obj_id + integer(HSIZE_T), intent(out) :: dims(:) + + integer :: hdf5_err + integer :: type + integer(HID_T) :: space_id + integer(HSIZE_T) :: maxdims(size(dims)) + + call h5iget_type_f(obj_id, type, hdf5_err) + if (type == H5I_DATASET_F) then + call h5dget_space_f(obj_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + call h5sclose_f(space_id, hdf5_err) + elseif (type == H5I_ATTR_F) then + call h5aget_space_f(obj_id, space_id, hdf5_err) + call h5sget_simple_extent_dims_f(space_id, dims, maxdims, hdf5_err) + call h5sclose_f(space_id, hdf5_err) + end if + end subroutine get_shape + function using_mpio_device(obj_id) result(mpio) integer(HID_T), intent(in) :: obj_id logical :: mpio diff --git a/src/initialize.F90 b/src/initialize.F90 index 09bedb138..8c4eabbc1 100644 --- a/src/initialize.F90 +++ b/src/initialize.F90 @@ -375,7 +375,7 @@ contains ! Check what type of file this is file_id = file_open(argv(i), 'r', parallel=.true.) - call read_dataset(file_id, 'filetype', filetype) + call read_dataset(filetype, file_id, 'filetype') call file_close(file_id) ! Set path and flag for type of run @@ -401,7 +401,7 @@ contains ! Check file type is a source file file_id = file_open(argv(i), 'r', parallel=.true.) - call read_dataset(file_id, 'filetype', filetype) + call read_dataset(filetype, file_id, 'filetype') call file_close(file_id) if (filetype /= 'source') then call fatal_error("Second file after restart flag must be a & diff --git a/src/particle_restart.F90 b/src/particle_restart.F90 index 9d49a4f97..4040a471a 100644 --- a/src/particle_restart.F90 +++ b/src/particle_restart.F90 @@ -71,7 +71,7 @@ contains integer :: int_scalar integer(HID_T) :: file_id - character(MAX_WORD_LEN) :: mode + character(MAX_WORD_LEN) :: tempstr ! Write meessage call write_message("Loading particle restart file " & @@ -81,25 +81,25 @@ contains file_id = file_open(path_particle_restart, 'r') ! Read data from file - call read_dataset(file_id, 'filetype', int_scalar) - call read_dataset(file_id, 'revision', int_scalar) - call read_dataset(file_id, 'current_batch', current_batch) - call read_dataset(file_id, 'gen_per_batch', gen_per_batch) - call read_dataset(file_id, 'current_gen', current_gen) - call read_dataset(file_id, 'n_particles', n_particles) - call read_dataset(file_id, 'run_mode', mode) - select case (mode) + call read_dataset(tempstr, file_id, 'filetype') + call read_dataset(int_scalar, file_id, 'revision') + call read_dataset(current_batch, file_id, 'current_batch') + call read_dataset(gen_per_batch, file_id, 'gen_per_batch') + call read_dataset(current_gen, file_id, 'current_gen') + call read_dataset(n_particles, file_id, 'n_particles') + call read_dataset(tempstr, file_id, 'run_mode') + select case (tempstr) case ('k-eigenvalue') previous_run_mode = MODE_EIGENVALUE case ('fixed source') previous_run_mode = MODE_FIXEDSOURCE end select - call read_dataset(file_id, 'id', p%id) - call read_dataset(file_id, 'weight', p%wgt) - call read_dataset(file_id, 'energy', p%E) - call read_dataset(file_id, 'energy_group', p%g) - call read_dataset(file_id, 'xyz', p%coord(1)%xyz) - call read_dataset(file_id, 'uvw', p%coord(1)%uvw) + call read_dataset(p%id, file_id, 'id') + call read_dataset(p%wgt, file_id, 'weight') + call read_dataset(p%E, file_id, 'energy') + call read_dataset(p%g, file_id, 'energy_group') + call read_dataset(p%coord(1)%xyz, file_id, 'xyz') + call read_dataset(p%coord(1)%uvw, file_id, 'uvw') ! Set particle last attributes p%last_wgt = p%wgt diff --git a/src/source.F90 b/src/source.F90 index ad565c95c..194c8c6ad 100644 --- a/src/source.F90 +++ b/src/source.F90 @@ -53,7 +53,7 @@ contains file_id = file_open(path_source, 'r', parallel=.true.) ! Read the file type - call read_dataset(file_id, "filetype", filetype) + call read_dataset(filetype, file_id, "filetype") ! Check to make sure this is a source file if (filetype /= 'source') then diff --git a/src/state_point.F90 b/src/state_point.F90 index cbd6c017a..81abf0c1b 100644 --- a/src/state_point.F90 +++ b/src/state_point.F90 @@ -703,25 +703,25 @@ contains file_id = file_open(path_state_point, 'r', parallel=.true.) ! Read filetype - call read_dataset(file_id, "filetype", word) + call read_dataset(word, file_id, "filetype") if (word /= 'statepoint') then call fatal_error("OpenMC tried to restart from a non-statepoint file.") end if ! Read revision number for state point file and make sure it matches with ! current version - call read_dataset(file_id, "revision", int_array(1)) + call read_dataset(int_array(1), file_id, "revision") if (int_array(1) /= REVISION_STATEPOINT) then call fatal_error("State point version does not match current version & &in OpenMC.") end if ! Read and overwrite random number seed - call read_dataset(file_id, "seed", seed) + call read_dataset(seed, file_id, "seed") ! It is not impossible for a state point to be generated from a CE run but ! to be loaded in to an MG run (or vice versa), check to prevent that. - call read_dataset(file_id, "run_CE", sp_run_CE) + call read_dataset(sp_run_CE, file_id, "run_CE") if (sp_run_CE == 0 .and. run_CE) then call fatal_error("State point file is from multi-group run but & & current run is continous-energy!") @@ -731,24 +731,24 @@ contains end if ! Read and overwrite run information except number of batches - call read_dataset(file_id, "run_mode", word) + call read_dataset(word, file_id, "run_mode") select case(word) case ('fixed source') run_mode = MODE_FIXEDSOURCE case ('k-eigenvalue') run_mode = MODE_EIGENVALUE end select - call read_dataset(file_id, "n_particles", n_particles) - call read_dataset(file_id, "n_batches", int_array(1)) + call read_dataset(n_particles, file_id, "n_particles") + call read_dataset(int_array(1), file_id, "n_batches") ! Take maximum of statepoint n_batches and input n_batches n_batches = max(n_batches, int_array(1)) ! Read batch number to restart at - call read_dataset(file_id, "current_batch", restart_batch) + call read_dataset(restart_batch, file_id, "current_batch") ! Check for source in statepoint if needed - call read_dataset(file_id, "source_present", int_array(1)) + call read_dataset(int_array(1), file_id, "source_present") if (int_array(1) == 1) then source_present = .true. else @@ -762,37 +762,37 @@ contains ! Read information specific to eigenvalue run if (run_mode == MODE_EIGENVALUE) then - call read_dataset(file_id, "n_inactive", int_array(1)) - call read_dataset(file_id, "gen_per_batch", gen_per_batch) - call read_dataset(file_id, "k_generation", & - k_generation(1:restart_batch*gen_per_batch)) - call read_dataset(file_id, "entropy", & - entropy(1:restart_batch*gen_per_batch)) - call read_dataset(file_id, "k_col_abs", k_col_abs) - call read_dataset(file_id, "k_col_tra", k_col_tra) - call read_dataset(file_id, "k_abs_tra", k_abs_tra) - call read_dataset(file_id, "k_combined", real_array(1:2)) + call read_dataset(int_array(1), file_id, "n_inactive") + call read_dataset(gen_per_batch, file_id, "gen_per_batch") + call read_dataset(k_generation(1:restart_batch*gen_per_batch), & + file_id, "k_generation") + call read_dataset(entropy(1:restart_batch*gen_per_batch), & + file_id, "entropy") + call read_dataset(k_col_abs, file_id, "k_col_abs") + call read_dataset(k_col_tra, file_id, "k_col_tra") + call read_dataset(k_abs_tra, file_id, "k_abs_tra") + call read_dataset(real_array(1:2), file_id, "k_combined") ! Take maximum of statepoint n_inactive and input n_inactive n_inactive = max(n_inactive, int_array(1)) ! Read in to see if CMFD was on - call read_dataset(file_id, "cmfd_on", int_array(1)) + call read_dataset(int_array(1), file_id, "cmfd_on") ! Read in CMFD info if (int_array(1) == 1) then cmfd_group = open_group(file_id, "cmfd") - call read_dataset(cmfd_group, "indices", cmfd%indices) - call read_dataset(cmfd_group, "k_cmfd", cmfd%k_cmfd(1:restart_batch)) - call read_dataset(cmfd_group, "cmfd_src", cmfd%cmfd_src) - call read_dataset(cmfd_group, "cmfd_entropy", & - cmfd%entropy(1:restart_batch)) - call read_dataset(cmfd_group, "cmfd_balance", & - cmfd%balance(1:restart_batch)) - call read_dataset(cmfd_group, "cmfd_dominance", & - cmfd%dom(1:restart_batch)) - call read_dataset(cmfd_group, "cmfd_srccmp", & - cmfd%src_cmp(1:restart_batch)) + call read_dataset(cmfd%indices, cmfd_group, "indices") + call read_dataset(cmfd%k_cmfd(1:restart_batch), cmfd_group, "k_cmfd") + call read_dataset(cmfd%cmfd_src, cmfd_group, "cmfd_src") + call read_dataset(cmfd%entropy(1:restart_batch), cmfd_group, & + "cmfd_entropy") + call read_dataset(cmfd%balance(1:restart_batch), cmfd_group, & + "cmfd_balance") + call read_dataset(cmfd%dom(1:restart_batch), cmfd_group, & + "cmfd_dominance") + call read_dataset(cmfd%src_cmp(1:restart_batch), cmfd_group, & + "cmfd_srccmp") call close_group(cmfd_group) end if end if @@ -812,14 +812,14 @@ contains #endif ! Read number of realizations for global tallies - call read_dataset(file_id, "n_realizations", n_realizations, indep=.true.) + call read_dataset(n_realizations, file_id, "n_realizations", indep=.true.) ! Read global tally data call read_dataset(file_id, "global_tallies", global_tallies) ! Check if tally results are present tallies_group = open_group(file_id, "tallies") - call read_dataset(tallies_group, "tallies_present", int_array(1), & + call read_dataset(int_array(1), tallies_group, "tallies_present", & indep=.true.) ! Read in sum and sum squared @@ -832,8 +832,8 @@ contains tally_group = open_group(tallies_group, "tally " // & trim(to_str(tally % id))) call read_dataset(tally_group, "results", tally % results) - call read_dataset(tally_group, "n_realizations", & - tally % n_realizations) + call read_dataset(tally % n_realizations, tally_group, & + "n_realizations") call close_group(tally_group) end do TALLY_RESULTS end if @@ -859,7 +859,7 @@ contains file_id = file_open(path_source_point, 'r', parallel=.true.) ! Read file type - call read_dataset(file_id, "filetype", int_array(1)) + call read_dataset(int_array(1), file_id, "filetype") end if From 68d2e5b047d20964b866ce4fa555008f0ab3edb2 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 13:18:18 -0400 Subject: [PATCH 126/147] Fixed hosed mgxs-part-iii notebook --- .../pythonapi/examples/mgxs-part-iii.ipynb | 509 ++++++++++++++---- 1 file changed, 417 insertions(+), 92 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index 152a68aff..ece33e3f5 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -23,11 +23,24 @@ }, { "cell_type": "code", - "execution_count": 71, + "execution_count": 1, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stderr", + "output_type": "stream", + "text": [ + "/home/wboyd/anaconda2/lib/python2.7/site-packages/matplotlib/__init__.py:1350: UserWarning: This call to matplotlib.use() has no effect\n", + "because the backend has already been chosen;\n", + "matplotlib.use() must be called *before* pylab, matplotlib.pyplot,\n", + "or matplotlib.backends is imported for the first time.\n", + "\n", + " warnings.warn(_use_error_msg)\n" + ] + } + ], "source": [ "import math\n", "import pickle\n", @@ -55,7 +68,7 @@ }, { "cell_type": "code", - "execution_count": 72, + "execution_count": 2, "metadata": { "collapsed": false }, @@ -79,7 +92,7 @@ }, { "cell_type": "code", - "execution_count": 73, + "execution_count": 3, "metadata": { "collapsed": true }, @@ -114,7 +127,7 @@ }, { "cell_type": "code", - "execution_count": 74, + "execution_count": 4, "metadata": { "collapsed": true }, @@ -137,7 +150,7 @@ }, { "cell_type": "code", - "execution_count": 75, + "execution_count": 5, "metadata": { "collapsed": true }, @@ -165,7 +178,7 @@ }, { "cell_type": "code", - "execution_count": 76, + "execution_count": 6, "metadata": { "collapsed": true }, @@ -202,7 +215,7 @@ }, { "cell_type": "code", - "execution_count": 77, + "execution_count": 7, "metadata": { "collapsed": true }, @@ -239,7 +252,7 @@ }, { "cell_type": "code", - "execution_count": 78, + "execution_count": 8, "metadata": { "collapsed": true }, @@ -261,7 +274,7 @@ }, { "cell_type": "code", - "execution_count": 79, + "execution_count": 9, "metadata": { "collapsed": true }, @@ -293,7 +306,7 @@ }, { "cell_type": "code", - "execution_count": 80, + "execution_count": 10, "metadata": { "collapsed": true }, @@ -320,7 +333,7 @@ }, { "cell_type": "code", - "execution_count": 81, + "execution_count": 11, "metadata": { "collapsed": true }, @@ -333,7 +346,7 @@ }, { "cell_type": "code", - "execution_count": 82, + "execution_count": 12, "metadata": { "collapsed": true }, @@ -352,7 +365,7 @@ }, { "cell_type": "code", - "execution_count": 83, + "execution_count": 13, "metadata": { "collapsed": false }, @@ -388,7 +401,7 @@ }, { "cell_type": "code", - "execution_count": 57, + "execution_count": 14, "metadata": { "collapsed": true }, @@ -416,7 +429,7 @@ }, { "cell_type": "code", - "execution_count": 58, + "execution_count": 15, "metadata": { "collapsed": false }, @@ -427,7 +440,7 @@ "0" ] }, - "execution_count": 58, + "execution_count": 15, "metadata": {}, "output_type": "execute_result" } @@ -439,19 +452,19 @@ }, { "cell_type": "code", - "execution_count": 59, + "execution_count": 16, "metadata": { "collapsed": false }, "outputs": [ { "data": { - 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"execution_count": 59, + "execution_count": 16, "metadata": {}, "output_type": "execute_result" } @@ -487,7 +500,7 @@ }, { "cell_type": "code", - "execution_count": 60, + "execution_count": 17, "metadata": { "collapsed": false }, @@ -507,7 +520,7 @@ }, { "cell_type": "code", - "execution_count": 61, + "execution_count": 18, "metadata": { "collapsed": false }, @@ -545,7 +558,7 @@ }, { "cell_type": "code", - "execution_count": 62, + "execution_count": 19, "metadata": { "collapsed": false }, @@ -566,7 +579,7 @@ }, { "cell_type": "code", - "execution_count": 63, + "execution_count": 20, "metadata": { "collapsed": true }, @@ -588,7 +601,7 @@ }, { "cell_type": "code", - "execution_count": 64, + "execution_count": 21, "metadata": { "collapsed": true }, @@ -607,7 +620,7 @@ }, { "cell_type": "code", - "execution_count": 65, + "execution_count": 22, "metadata": { "collapsed": true }, @@ -628,7 +641,7 @@ }, { "cell_type": "code", - "execution_count": 66, + "execution_count": 23, "metadata": { "collapsed": true }, @@ -648,7 +661,7 @@ }, { "cell_type": "code", - "execution_count": 67, + "execution_count": 24, "metadata": { "collapsed": false }, @@ -676,7 +689,7 @@ }, { "cell_type": "code", - "execution_count": 68, + "execution_count": 25, "metadata": { "collapsed": true }, @@ -688,7 +701,7 @@ }, { "cell_type": "code", - "execution_count": 69, + "execution_count": 26, "metadata": { "collapsed": false }, @@ -713,8 +726,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n", - " Date/Time: 2016-05-13 10:12:20\n", + " Git SHA1: 47ef320ad517612376e181ec6a6bc42ca0db98ce\n", + " Date/Time: 2016-05-13 13:14:08\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -801,20 +814,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.0700E-01 seconds\n", - " Reading cross sections = 1.0600E-01 seconds\n", - " Total time in simulation = 6.4501E+01 seconds\n", - " Time in transport only = 6.4461E+01 seconds\n", - " Time in inactive batches = 5.2590E+00 seconds\n", - " Time in active batches = 5.9242E+01 seconds\n", - " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 2.0000E-03 seconds\n", - " Time accumulating tallies = 3.0000E-03 seconds\n", + " Total time for initialization = 7.4900E-01 seconds\n", + " Reading cross sections = 2.6400E-01 seconds\n", + " Total time in simulation = 8.0114E+01 seconds\n", + " Time in transport only = 8.0033E+01 seconds\n", + " Time in inactive batches = 6.5120E+00 seconds\n", + " Time in active batches = 7.3602E+01 seconds\n", + " Time synchronizing fission bank = 3.2000E-02 seconds\n", + " Sampling source sites = 3.0000E-03 seconds\n", + " SEND/RECV source sites = 2.8000E-02 seconds\n", + " Time accumulating tallies = 2.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 6.5026E+01 seconds\n", - " Calculation Rate (inactive) = 4753.76 neutrons/second\n", - " Calculation Rate (active) = 1687.99 neutrons/second\n", + " Total time elapsed = 8.0892E+01 seconds\n", + " Calculation Rate (inactive) = 3839.07 neutrons/second\n", + " Calculation Rate (active) = 1358.66 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -832,7 +845,7 @@ "0" ] }, - "execution_count": 69, + "execution_count": 26, "metadata": {}, "output_type": "execute_result" } @@ -858,32 +871,11 @@ }, { "cell_type": "code", - "execution_count": 70, + "execution_count": 27, "metadata": { "collapsed": false }, - "outputs": [ - { - "ename": "KeyError", - "evalue": "'Unable to open object (Component not found)'", - "output_type": "error", - "traceback": [ - "\u001b[1;31m---------------------------------------------------------------------------\u001b[0m", - "\u001b[1;31mKeyError\u001b[0m Traceback (most recent call last)", - "\u001b[1;32m\u001b[0m in \u001b[0;36m\u001b[1;34m()\u001b[0m\n\u001b[0;32m 1\u001b[0m \u001b[1;31m# Load the last statepoint file\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m----> 2\u001b[1;33m \u001b[0msp\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mopenmc\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mStatePoint\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;34m'statepoint.50.h5'\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m", - "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36m__init__\u001b[1;34m(self, filename, autolink)\u001b[0m\n\u001b[0;32m 135\u001b[0m \u001b[1;32mif\u001b[0m \u001b[0mos\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mpath\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mexists\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mpath_summary\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 136\u001b[0m \u001b[0msu\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mopenmc\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mSummary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mpath_summary\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 137\u001b[1;33m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mlink_with_summary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0msu\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 138\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 139\u001b[0m \u001b[1;32mdef\u001b[0m \u001b[0mclose\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mself\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36mlink_with_summary\u001b[1;34m(self, summary)\u001b[0m\n\u001b[0;32m 639\u001b[0m \u001b[1;32mraise\u001b[0m \u001b[0mValueError\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mmsg\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 640\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 641\u001b[1;33m \u001b[1;32mfor\u001b[0m \u001b[0mtally_id\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mtally\u001b[0m \u001b[1;32min\u001b[0m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mtallies\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mitems\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 642\u001b[0m \u001b[0msummary_tally\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0msummary\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mtallies\u001b[0m\u001b[1;33m[\u001b[0m\u001b[0mtally_id\u001b[0m\u001b[1;33m]\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 643\u001b[0m \u001b[0mtally\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mname\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0msummary_tally\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mname\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.1-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36mtallies\u001b[1;34m(self)\u001b[0m\n\u001b[0;32m 376\u001b[0m \u001b[1;31m# Read the Tally size specifications\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 377\u001b[0m \u001b[0mn_realizations\u001b[0m \u001b[1;33m=\u001b[0m\u001b[0;31m \u001b[0m\u001b[0;31m\\\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 378\u001b[1;33m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0m_f\u001b[0m\u001b[1;33m[\u001b[0m\u001b[1;34m'{0}{1}/n_realizations'\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mformat\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mbase\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mtally_key\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m]\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mvalue\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 379\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 380\u001b[0m \u001b[1;31m# Create Tally object and assign basic properties\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2453)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 52\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mneeded\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mit\u001b[0m \u001b[0macquires\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mand\u001b[0m \u001b[0mnotifies\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mfirst\u001b[0m \u001b[0mthread\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 54\u001b[1;33m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 55\u001b[0m \"\"\"\n\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2410)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 54\u001b[0m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 55\u001b[1;33m \"\"\"\n\u001b[0m\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 57\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mlong\u001b[0m \u001b[0m_owner\u001b[0m \u001b[1;31m# ID of thread owning the lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/local/lib/python2.7/dist-packages/h5py-2.5.0-py2.7-linux-x86_64.egg/h5py/_hl/group.pyc\u001b[0m in \u001b[0;36m__getitem__\u001b[1;34m(self, name)\u001b[0m\n\u001b[0;32m 162\u001b[0m \u001b[1;32mraise\u001b[0m \u001b[0mValueError\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;34m\"Invalid HDF5 object reference\"\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 163\u001b[0m \u001b[1;32melse\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 164\u001b[1;33m \u001b[0moid\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mh5o\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mopen\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mid\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0m_e\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0mname\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mlapl\u001b[0m\u001b[1;33m=\u001b[0m\u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0m_lapl\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 165\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 166\u001b[0m \u001b[0motype\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mh5i\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mget_type\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0moid\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2453)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 52\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mneeded\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mit\u001b[0m \u001b[0macquires\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mlock\u001b[0m \u001b[1;32mand\u001b[0m \u001b[0mnotifies\u001b[0m \u001b[0mthe\u001b[0m \u001b[0mfirst\u001b[0m \u001b[0mthread\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 54\u001b[1;33m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 55\u001b[0m \"\"\"\n\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/_objects.pyx\u001b[0m in \u001b[0;36mh5py._objects.with_phil.wrapper (/home/wboyd/Downloads/h5py-2.5.0/h5py/_objects.c:2410)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 53\u001b[0m \u001b[0mto\u001b[0m \u001b[0mrelease\u001b[0m \u001b[0mit\u001b[0m \u001b[0mwhen\u001b[0m \u001b[0mit\u001b[0m\u001b[0;31m'\u001b[0m\u001b[0ms\u001b[0m \u001b[0mdone\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThis\u001b[0m \u001b[1;32mis\u001b[0m \u001b[0mall\u001b[0m \u001b[0mmade\u001b[0m \u001b[0mpossible\u001b[0m \u001b[0mby\u001b[0m \u001b[0mthe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 54\u001b[0m \u001b[0mwonderful\u001b[0m \u001b[0mGIL\u001b[0m\u001b[1;33m.\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m---> 55\u001b[1;33m \"\"\"\n\u001b[0m\u001b[0;32m 56\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mpythread\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mPyThread_type_lock\u001b[0m \u001b[0m_real_lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 57\u001b[0m \u001b[0mcdef\u001b[0m \u001b[0mlong\u001b[0m \u001b[0m_owner\u001b[0m \u001b[1;31m# ID of thread owning the lock\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;32m/usr/lib/python2.7/dist-packages/h5py/h5o.pyx\u001b[0m in \u001b[0;36mh5py.h5o.open (/home/wboyd/Downloads/h5py-2.5.0/h5py/h5o.c:3363)\u001b[1;34m()\u001b[0m\n\u001b[0;32m 188\u001b[0m char* dst_name, PropID copypl=None, PropID lcpl=None):\n\u001b[0;32m 189\u001b[0m \"\"\"(ObjectID src_loc, STRING src_name, GroupID dst_loc, STRING dst_name,\n\u001b[1;32m--> 190\u001b[1;33m PropID copypl=None, PropID lcpl=None)\n\u001b[0m\u001b[0;32m 191\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 192\u001b[0m \u001b[0mCopy\u001b[0m \u001b[0ma\u001b[0m \u001b[0mgroup\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mdataset\u001b[0m \u001b[1;32mor\u001b[0m \u001b[0mnamed\u001b[0m \u001b[0mdatatype\u001b[0m \u001b[1;32mfrom\u001b[0m \u001b[0mone\u001b[0m \u001b[0mlocation\u001b[0m \u001b[0mto\u001b[0m \u001b[0manother\u001b[0m\u001b[1;33m.\u001b[0m \u001b[0mThe\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n", - "\u001b[1;31mKeyError\u001b[0m: 'Unable to open object (Component not found)'" - ] - } - ], + "outputs": [], "source": [ "# Load the last statepoint file\n", "sp = openmc.StatePoint('statepoint.50.h5')" @@ -898,7 +890,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -933,7 +925,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -952,11 +944,102 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 30, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stderr", + "output_type": "stream", + "text": [ + "/home/wboyd/Documents/NSE-CRPG-Codes/openmc/openmc/tallies.py:1988: RuntimeWarning: invalid value encountered in true_divide\n", + " self_rel_err = data['self']['std. dev.'] / data['self']['mean']\n" + ] + }, + { + "data": { + "text/html": [ + "
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cellgroup innuclidemeanstd. dev.
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5100001O-160.000000e+000.000000e+00
0100002U-2353.615565e-012.050486e-03
1100002U-2386.742638e-073.795256e-09
2100002O-160.000000e+000.000000e+00
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" + ], + "text/plain": [ + " cell group in nuclide mean std. dev.\n", + "3 10000 1 U-235 8.055246e-03 2.857567e-05\n", + "4 10000 1 U-238 7.339215e-03 4.349466e-05\n", + "5 10000 1 O-16 0.000000e+00 0.000000e+00\n", + "0 10000 2 U-235 3.615565e-01 2.050486e-03\n", + "1 10000 2 U-238 6.742638e-07 3.795256e-09\n", + "2 10000 2 O-16 0.000000e+00 0.000000e+00" + ] + }, + "execution_count": 30, + "metadata": {}, + "output_type": "execute_result" + } + ], "source": [ "df = fuel_mgxs.get_pandas_dataframe()\n", "df" @@ -971,11 +1054,39 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 31, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "Multi-Group XS\n", + "\tReaction Type =\tnu-fission\n", + "\tDomain Type =\tcell\n", + "\tDomain ID =\t10000\n", + "\tNuclide =\tU-235\n", + "\tCross Sections [cm^-1]:\n", + " Group 1 [6.25e-07 - 20.0 MeV]:\t8.06e-03 +/- 3.55e-01%\n", + " Group 2 [0.0 - 6.25e-07 MeV]:\t3.62e-01 +/- 5.67e-01%\n", + "\n", + "\tNuclide =\tU-238\n", + "\tCross Sections [cm^-1]:\n", + " Group 1 [6.25e-07 - 20.0 MeV]:\t7.34e-03 +/- 5.93e-01%\n", + " Group 2 [0.0 - 6.25e-07 MeV]:\t6.74e-07 +/- 5.63e-01%\n", + "\n", + "\tNuclide =\tO-16\n", + "\tCross Sections [cm^-1]:\n", + " Group 1 [6.25e-07 - 20.0 MeV]:\t0.00e+00 +/- nan%\n", + " Group 2 [0.0 - 6.25e-07 MeV]:\t0.00e+00 +/- nan%\n", + "\n", + "\n", + "\n" + ] + } + ], "source": [ "fuel_mgxs.print_xs()" ] @@ -989,7 +1100,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 32, "metadata": { "collapsed": false }, @@ -1008,7 +1119,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 33, "metadata": { "collapsed": true }, @@ -1020,7 +1131,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 34, "metadata": { "collapsed": true }, @@ -1039,7 +1150,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 35, "metadata": { "collapsed": true }, @@ -1054,11 +1165,67 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 36, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "data": { + "text/html": [ + "
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cellgroup innuclidemeanstd. dev.
0100001U-2350.0748600.000303
1100001U-2380.0059520.000035
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" + ], + "text/plain": [ + " cell group in nuclide mean std. dev.\n", + "0 10000 1 U-235 0.074860 0.000303\n", + "1 10000 1 U-238 0.005952 0.000035\n", + "2 10000 1 O-16 0.000000 0.000000" + ] + }, + "execution_count": 36, + "metadata": {}, + "output_type": "execute_result" + } + ], "source": [ "# Retrieve the NuFissionXS object for the fuel cell from the 1-group library\n", "coarse_fuel_mgxs = coarse_mgxs_lib.get_mgxs(fuel_cell, 'nu-fission')\n", @@ -1083,7 +1250,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 37, "metadata": { "collapsed": false }, @@ -1102,7 +1269,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -1121,12 +1288,139 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 39, "metadata": { "collapsed": false, "scrolled": true }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "[ NORMAL ] Importing ray tracing data from file...\n", + "[ NORMAL ] Computing the eigenvalue...\n", + "[ NORMAL ] Iteration 0:\tk_eff = 0.854370\tres = 0.000E+00\n", + "[ NORMAL ] Iteration 1:\tk_eff = 0.801922\tres = 1.521E-01\n", + "[ NORMAL ] Iteration 2:\tk_eff = 0.761745\tres = 6.349E-02\n", + "[ NORMAL ] Iteration 3:\tk_eff = 0.732366\tres = 5.029E-02\n", + "[ NORMAL ] Iteration 4:\tk_eff = 0.711073\tres = 3.869E-02\n", + "[ NORMAL ] Iteration 5:\tk_eff = 0.696554\tres = 2.912E-02\n", + "[ NORMAL ] Iteration 6:\tk_eff = 0.687670\tres = 2.044E-02\n", + "[ NORMAL ] Iteration 7:\tk_eff = 0.683465\tres = 1.277E-02\n", + "[ NORMAL ] Iteration 8:\tk_eff = 0.683124\tres = 6.142E-03\n", + "[ NORMAL ] Iteration 9:\tk_eff = 0.685943\tres = 7.897E-04\n", + "[ NORMAL ] Iteration 10:\tk_eff = 0.691322\tres = 4.180E-03\n", + "[ NORMAL ] Iteration 11:\tk_eff = 0.698747\tres = 7.873E-03\n", + "[ NORMAL ] Iteration 12:\tk_eff = 0.707777\tres = 1.076E-02\n", + "[ NORMAL ] Iteration 13:\tk_eff = 0.718040\tres = 1.295E-02\n", + "[ NORMAL ] Iteration 14:\tk_eff = 0.729218\tres = 1.452E-02\n", + "[ NORMAL ] Iteration 15:\tk_eff = 0.741045\tres = 1.559E-02\n", + "[ NORMAL ] Iteration 16:\tk_eff = 0.753296\tres = 1.624E-02\n", + "[ NORMAL ] Iteration 17:\tk_eff = 0.765785\tres = 1.655E-02\n", + "[ NORMAL ] Iteration 18:\tk_eff = 0.778355\tres = 1.659E-02\n", + "[ NORMAL ] Iteration 19:\tk_eff = 0.790879\tres = 1.643E-02\n", + "[ NORMAL ] Iteration 20:\tk_eff = 0.803254\tres = 1.610E-02\n", + "[ NORMAL ] Iteration 21:\tk_eff = 0.815394\tres = 1.566E-02\n", + "[ NORMAL ] Iteration 22:\tk_eff = 0.827235\tres = 1.513E-02\n", + "[ NORMAL ] Iteration 23:\tk_eff = 0.838724\tres = 1.453E-02\n", + "[ NORMAL ] Iteration 24:\tk_eff = 0.849823\tres = 1.390E-02\n", + "[ NORMAL ] Iteration 25:\tk_eff = 0.860503\tres = 1.324E-02\n", + "[ NORMAL ] Iteration 26:\tk_eff = 0.870744\tres = 1.258E-02\n", + "[ NORMAL ] Iteration 27:\tk_eff = 0.880535\tres = 1.191E-02\n", + "[ NORMAL ] Iteration 28:\tk_eff = 0.889870\tres = 1.125E-02\n", + "[ NORMAL ] Iteration 29:\tk_eff = 0.898748\tres = 1.061E-02\n", + "[ NORMAL ] Iteration 30:\tk_eff = 0.907172\tres = 9.985E-03\n", + "[ NORMAL ] Iteration 31:\tk_eff = 0.915151\tres = 9.382E-03\n", + "[ NORMAL ] Iteration 32:\tk_eff = 0.922693\tres = 8.802E-03\n", + "[ NORMAL ] Iteration 33:\tk_eff = 0.929811\tres = 8.248E-03\n", + "[ NORMAL ] Iteration 34:\tk_eff = 0.936517\tres = 7.720E-03\n", + "[ NORMAL ] Iteration 35:\tk_eff = 0.942827\tres = 7.219E-03\n", + "[ NORMAL ] Iteration 36:\tk_eff = 0.948757\tres = 6.744E-03\n", + "[ NORMAL ] Iteration 37:\tk_eff = 0.954322\tres = 6.295E-03\n", + "[ NORMAL ] Iteration 38:\tk_eff = 0.959539\tres = 5.871E-03\n", + "[ NORMAL ] Iteration 39:\tk_eff = 0.964425\tres = 5.472E-03\n", + "[ NORMAL ] Iteration 40:\tk_eff = 0.968996\tres = 5.096E-03\n", + "[ NORMAL ] Iteration 41:\tk_eff = 0.973268\tres = 4.744E-03\n", + "[ NORMAL ] Iteration 42:\tk_eff = 0.977259\tres = 4.413E-03\n", + "[ NORMAL ] Iteration 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+ "[ NORMAL ] Iteration 88:\tk_eff = 1.027347\tres = 1.160E-04\n", + "[ NORMAL ] Iteration 89:\tk_eff = 1.027447\tres = 1.067E-04\n", + "[ NORMAL ] Iteration 90:\tk_eff = 1.027540\tres = 9.823E-05\n", + "[ NORMAL ] Iteration 91:\tk_eff = 1.027625\tres = 9.039E-05\n", + "[ NORMAL ] Iteration 92:\tk_eff = 1.027704\tres = 8.317E-05\n", + "[ NORMAL ] Iteration 93:\tk_eff = 1.027776\tres = 7.652E-05\n", + "[ NORMAL ] Iteration 94:\tk_eff = 1.027843\tres = 7.040E-05\n", + "[ NORMAL ] Iteration 95:\tk_eff = 1.027904\tres = 6.476E-05\n", + "[ NORMAL ] Iteration 96:\tk_eff = 1.027960\tres = 5.957E-05\n", + "[ NORMAL ] Iteration 97:\tk_eff = 1.028012\tres = 5.479E-05\n", + "[ NORMAL ] Iteration 98:\tk_eff = 1.028059\tres = 5.039E-05\n", + "[ NORMAL ] Iteration 99:\tk_eff = 1.028103\tres = 4.635E-05\n", + "[ NORMAL ] Iteration 100:\tk_eff = 1.028143\tres = 4.262E-05\n", + "[ NORMAL ] Iteration 101:\tk_eff = 1.028180\tres = 3.919E-05\n", + "[ NORMAL ] Iteration 102:\tk_eff = 1.028214\tres = 3.603E-05\n", + "[ NORMAL ] Iteration 103:\tk_eff = 1.028245\tres = 3.313E-05\n", + "[ NORMAL ] Iteration 104:\tk_eff = 1.028274\tres = 3.046E-05\n", + "[ NORMAL ] Iteration 105:\tk_eff = 1.028300\tres = 2.800E-05\n", + "[ NORMAL ] Iteration 106:\tk_eff = 1.028324\tres = 2.574E-05\n", + "[ NORMAL ] Iteration 107:\tk_eff = 1.028347\tres = 2.366E-05\n", + "[ NORMAL ] Iteration 108:\tk_eff = 1.028367\tres = 2.175E-05\n", + "[ NORMAL ] Iteration 109:\tk_eff = 1.028386\tres = 1.999E-05\n", + "[ NORMAL ] Iteration 110:\tk_eff = 1.028403\tres = 1.837E-05\n", + "[ NORMAL ] Iteration 111:\tk_eff = 1.028419\tres = 1.688E-05\n", + "[ NORMAL ] Iteration 112:\tk_eff = 1.028434\tres = 1.551E-05\n", + "[ NORMAL ] Iteration 113:\tk_eff = 1.028447\tres = 1.426E-05\n", + "[ NORMAL ] Iteration 114:\tk_eff = 1.028460\tres = 1.310E-05\n", + "[ NORMAL ] Iteration 115:\tk_eff = 1.028471\tres = 1.204E-05\n", + "[ NORMAL ] Iteration 116:\tk_eff = 1.028481\tres = 1.106E-05\n", + "[ NORMAL ] Iteration 117:\tk_eff = 1.028491\tres = 1.016E-05\n" + ] + } + ], "source": [ "# Generate tracks for OpenMOC\n", "track_generator = openmoc.TrackGenerator(openmoc_geometry, num_azim=32, azim_spacing=0.1)\n", @@ -1146,11 +1440,21 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 40, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "name": "stdout", + "output_type": "stream", + "text": [ + "openmc keff = 1.028263\n", + "openmoc keff = 1.028491\n", + "bias [pcm]: 22.8\n" + ] + } + ], "source": [ "# Print report of keff and bias with OpenMC\n", "openmoc_keff = solver.getKeff()\n", @@ -1189,7 +1493,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 41, "metadata": { "collapsed": false }, @@ -1215,7 +1519,7 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 42, "metadata": { "collapsed": false }, @@ -1247,11 +1551,32 @@ }, { "cell_type": "code", - "execution_count": null, + "execution_count": 43, "metadata": { "collapsed": false }, - "outputs": [], + "outputs": [ + { + "data": { + "text/plain": [ + "" + ] + }, + "execution_count": 43, + "metadata": {}, + "output_type": "execute_result" + }, + { + "data": { + "image/png": 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+ "text/plain": [ + "" + ] + }, + "metadata": {}, + "output_type": "display_data" + } + ], "source": [ "# Ignore zero fission rates in guide tubes with Matplotlib color scheme\n", "openmc_fission_rates[openmc_fission_rates == 0] = np.nan\n", @@ -1285,7 +1610,7 @@ "name": "python", "nbconvert_exporter": "python", "pygments_lexer": "ipython2", - "version": "2.7.6" + "version": "2.7.11" } }, "nbformat": 4, From 830277baf90278565c3168c89a1f596edd832339 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 13:25:45 -0400 Subject: [PATCH 127/147] Replicated MGXS docstring to all subclasses for clarity in Jupyter Notebook --- openmc/mgxs/mgxs.py | 1034 ++++++++++++++++++++++++++++++++++++++++++- 1 file changed, 1023 insertions(+), 11 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 182691283..4c00f9fef 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1525,7 +1525,85 @@ class MGXS(object): class TotalXS(MGXS): - """A total multi-group cross section.""" + """A total multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1535,7 +1613,85 @@ class TotalXS(MGXS): class TransportXS(MGXS): - """A transport-corrected total multi-group cross section.""" + """A transport-corrected total multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1571,7 +1727,85 @@ class TransportXS(MGXS): class NuTransportXS(TransportXS): """A transport-corrected total multi-group cross section which - accounts for neutron multiplicity in scattering reactions.""" + accounts for neutron multiplicity in scattering reactions. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1589,7 +1823,85 @@ class NuTransportXS(TransportXS): class AbsorptionXS(MGXS): - """An absorption multi-group cross section.""" + """An absorption multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1606,6 +1918,82 @@ class CaptureXS(MGXS): not only radiative capture, but all forms of neutron disappearance aside from fission (e.g., MT > 100). + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + """ def __init__(self, domain=None, domain_type=None, @@ -1628,7 +2016,85 @@ class CaptureXS(MGXS): class FissionXS(MGXS): - """A fission multi-group cross section.""" + """A fission multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1638,7 +2104,85 @@ class FissionXS(MGXS): class NuFissionXS(MGXS): - """A fission production multi-group cross section.""" + """A fission production multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1648,7 +2192,85 @@ class NuFissionXS(MGXS): class KappaFissionXS(MGXS): - """A recoverable fission energy production rate multi-group cross section.""" + """A recoverable fission energy production rate multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1658,7 +2280,85 @@ class KappaFissionXS(MGXS): class ScatterXS(MGXS): - """A scatter multi-group cross section.""" + """A scatter multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1668,7 +2368,85 @@ class ScatterXS(MGXS): class NuScatterXS(MGXS): - """A nu-scatter multi-group cross section.""" + """A nu-scatter multi-group cross section. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -1681,12 +2459,85 @@ class ScatterMatrixXS(MGXS): """A scattering matrix multi-group cross section for one or more Legendre moments. + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + Attributes ---------- correction : 'P0' or None Apply the P0 correction to scattering matrices if set to 'P0' legendre_order : int The highest legendre moment in the scattering matrix (default is 0) + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store """ @@ -2241,7 +3092,90 @@ class ScatterMatrixXS(MGXS): class NuScatterMatrixXS(ScatterMatrixXS): - """A scattering production matrix multi-group cross section.""" + """A scattering production matrix multi-group cross section for one or + more Legendre moments. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + correction : 'P0' or None + Apply the P0 correction to scattering matrices if set to 'P0' + legendre_order : int + The highest legendre moment in the scattering matrix (default is 0) + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): @@ -2252,7 +3186,85 @@ class NuScatterMatrixXS(ScatterMatrixXS): class Chi(MGXS): - """The fission spectrum.""" + """The fission spectrum. + + This class can be used for both OpenMC input generation and tally data + post-processing to compute spatially-homogenized and energy-integrated + multi-group cross sections for deterministic neutronics calculations. + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + The domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + The energy group structure for energy condensation + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + name : str, optional + Name of the multi-group cross section. Used as a label to identify + tallies in OpenMC 'tallies.xml' file. + + Attributes + ---------- + name : str, optional + Name of the multi-group cross section + rxn_type : str + Reaction type (e.g., 'total', 'nu-fission', etc.) + by_nuclide : bool + If true, computes cross sections for each nuclide in domain + domain : Material or Cell or Universe + Domain for spatial homogenization + domain_type : {'material', 'cell', 'distribcell', 'universe'} + Domain type for spatial homogenization + energy_groups : openmc.mgxs.EnergyGroups + Energy group structure for energy condensation + tally_trigger : openmc.Trigger + An (optional) tally precision trigger given to each tally used to + compute the cross section + scores : list of str + The scores in each tally used to compute the multi-group cross section + filters : list of openmc.Filter + The filters in each tally used to compute the multi-group cross section + tally_keys : list of str + The keys into the tallies dictionary for each tally used to compute + the multi-group cross section + estimator : {'tracklength', 'analog'} + The tally estimator used to compute the multi-group cross section + tallies : collections.OrderedDict + OpenMC tallies needed to compute the multi-group cross section + rxn_rate_tally : openmc.Tally + Derived tally for the reaction rate tally used in the numerator to + compute the multi-group cross section. This attribute is None + unless the multi-group cross section has been computed. + xs_tally : openmc.Tally + Derived tally for the multi-group cross section. This attribute + is None unless the multi-group cross section has been computed. + num_subdomains : int + The number of subdomains is unity for 'material', 'cell' and 'universe' + domain types. When the This is equal to the number of cell instances + for 'distribcell' domain types (it is equal to unity prior to loading + tally data from a statepoint file). + num_nuclides : int + The number of nuclides for which the multi-group cross section is + being tracked. This is unity if the by_nuclide attribute is False. + nuclides : Iterable of str or 'sum' + The optional user-specified nuclides for which to compute cross + sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides + are not specified by the user, all nuclides in the spatial domain + are included. This attribute is 'sum' if by_nuclide is false. + sparse : bool + Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format + for compressed data storage + loaded_sp : bool + Whether or not a statepoint file has been loaded with tally data + derived : bool + Whether or not the MGXS is merged from one or more other MGXS + hdf5_key : str + The key used to index multi-group cross sections in an HDF5 data store + + """ def __init__(self, domain=None, domain_type=None, groups=None, by_nuclide=False, name=''): From 9449ca6b891f4dede18790748ce5a0a1a4d5018c Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 15:50:40 -0400 Subject: [PATCH 128/147] MGXS tests now use a 3rd order legendre scattering moments --- .../inputs_true.dat | 2 +- .../results_true.dat | 116 +- .../test_mgxs_library_condense.py | 1 + .../inputs_true.dat | 2 +- .../results_true.dat | 9 +- .../test_mgxs_library_distribcell.py | 1 + tests/test_mgxs_library_hdf5/inputs_true.dat | 2 +- tests/test_mgxs_library_hdf5/results_true.dat | 168 +- .../test_mgxs_library_hdf5.py | 1 + .../inputs_true.dat | 2 +- .../results_true.dat | 350 +- .../test_mgxs_library_no_nuclides.py | 1 + .../inputs_true.dat | 2 +- .../results_true.dat | 5742 ++++++++++++----- .../test_mgxs_library_nuclides.py | 1 + 15 files changed, 4512 insertions(+), 1888 deletions(-) diff --git a/tests/test_mgxs_library_condense/inputs_true.dat b/tests/test_mgxs_library_condense/inputs_true.dat index 064981fa9..3643c9a2e 100644 --- a/tests/test_mgxs_library_condense/inputs_true.dat +++ b/tests/test_mgxs_library_condense/inputs_true.dat @@ -1 +1 @@ -ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file +104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f \ No newline at end of file diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index 8296aca11..f176c3007 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,49 +1,85 @@ material group in nuclide mean std. dev. 0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. -0 1 1 total 0.076425 0.003691 material group in group out nuclide mean std. dev. -0 1 1 1 total 0.345503 0.021465 material group out nuclide mean std. dev. -0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. +0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean +0 1 1 1 total P0 0.384780 +1 1 1 1 total P1 0.039277 +2 1 1 1 total P2 0.017574 +3 1 1 1 total P3 0.012203 material group out nuclide mean std. dev. +0 1 1 total 1 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 2 1 1 total 0.241262 0.00841 material group out nuclide mean std. dev. -0 2 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 2 1 total 0 0 material group in group out nuclide moment mean +0 2 1 1 total P0 0.272369 +1 2 1 1 total P1 0.031107 +2 2 1 1 total P2 0.025999 +3 2 1 1 total P3 0.003219 material group out nuclide mean std. dev. +0 2 1 total 0 0 material group in nuclide mean std. dev. 0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 3 1 1 total 0.393462 0.033646 material group out nuclide mean std. dev. -0 3 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 3 1 total 0 0 material group in group out nuclide moment mean +0 3 1 1 total P0 0.794999 +1 3 1 1 total P1 0.401537 +2 3 1 1 total P2 0.143623 +3 3 1 1 total P3 0.001991 material group out nuclide mean std. dev. +0 3 1 total 0 0 material group in nuclide mean std. dev. 0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 4 1 1 total 0.371473 0.071226 material group out nuclide mean std. dev. -0 4 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 5 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 6 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 7 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 8 1 1 total 0.0 0.0 material group out nuclide mean std. dev. -0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 4 1 total 0 0 material group in group out nuclide moment mean +0 4 1 1 total P0 0.727311 +1 4 1 1 total P1 0.355839 +2 4 1 1 total P2 0.124483 +3 4 1 1 total P3 0.012168 material group out nuclide mean std. dev. +0 4 1 total 0 0 material group in nuclide mean std. dev. +0 5 1 total 0 0 material group in nuclide mean std. dev. +0 5 1 total 0 0 material group in group out nuclide moment mean +0 5 1 1 total P0 0 +1 5 1 1 total P1 0 +2 5 1 1 total P2 0 +3 5 1 1 total P3 0 material group out nuclide mean std. dev. +0 5 1 total 0 0 material group in nuclide mean std. dev. +0 6 1 total 0 0 material group in nuclide mean std. dev. +0 6 1 total 0 0 material group in group out nuclide moment mean +0 6 1 1 total P0 0 +1 6 1 1 total P1 0 +2 6 1 1 total P2 0 +3 6 1 1 total P3 0 material group out nuclide mean std. dev. +0 6 1 total 0 0 material group in nuclide mean std. dev. +0 7 1 total 0 0 material group in nuclide mean std. dev. +0 7 1 total 0 0 material group in group out nuclide moment mean +0 7 1 1 total P0 0 +1 7 1 1 total P1 0 +2 7 1 1 total P2 0 +3 7 1 1 total P3 0 material group out nuclide mean std. dev. +0 7 1 total 0 0 material group in nuclide mean std. dev. +0 8 1 total 0 0 material group in nuclide mean std. dev. +0 8 1 total 0 0 material group in group out nuclide moment mean +0 8 1 1 total P0 0 +1 8 1 1 total P1 0 +2 8 1 1 total P2 0 +3 8 1 1 total P3 0 material group out nuclide mean std. dev. +0 8 1 total 0 0 material group in nuclide mean std. dev. 0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 9 1 1 total 0.600536 0.748875 material group out nuclide mean std. dev. -0 9 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 9 1 total 0 0 material group in group out nuclide moment mean +0 9 1 1 total P0 0.720380 +1 9 1 1 total P1 0.119844 +2 9 1 1 total P2 0.038522 +3 9 1 1 total P3 0.056023 material group out nuclide mean std. dev. +0 9 1 total 0 0 material group in nuclide mean std. dev. 0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 10 1 1 total 0.235515 0.613974 material group out nuclide mean std. dev. -0 10 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 10 1 total 0 0 material group in group out nuclide moment mean +0 10 1 1 total P0 0.501009 +1 10 1 1 total P1 0.265494 +2 10 1 1 total P2 0.141979 +3 10 1 1 total P3 0.074258 material group out nuclide mean std. dev. +0 10 1 total 0 0 material group in nuclide mean std. dev. 0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 11 1 1 total 0.491857 0.715554 material group out nuclide mean std. dev. -0 11 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 11 1 total 0 0 material group in group out nuclide moment mean +0 11 1 1 total P0 0.804661 +1 11 1 1 total P1 0.312803 +2 11 1 1 total P2 0.168113 +3 11 1 1 total P3 0.003808 material group out nuclide mean std. dev. +0 11 1 total 0 0 material group in nuclide mean std. dev. 0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0.0 0.0 material group in group out nuclide mean std. dev. -0 12 1 1 total 0.723265 0.808231 material group out nuclide mean std. dev. -0 12 1 total 0.0 0.0 \ No newline at end of file +0 12 1 total 0 0 material group in group out nuclide moment mean +0 12 1 1 total P0 0.943429 +1 12 1 1 total P1 0.220164 +2 12 1 1 total P2 0.052884 +3 12 1 1 total P3 0.039939 material group out nuclide mean std. dev. +0 12 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py index 3ca98904f..561232b22 100644 --- a/tests/test_mgxs_library_condense/test_mgxs_library_condense.py +++ b/tests/test_mgxs_library_condense/test_mgxs_library_condense.py @@ -28,6 +28,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] self.mgxs_lib.energy_groups = energy_groups + self.mgxs_lib.legendre_order = 3 self.mgxs_lib.domain_type = 'material' self.mgxs_lib.build_library() diff --git a/tests/test_mgxs_library_distribcell/inputs_true.dat b/tests/test_mgxs_library_distribcell/inputs_true.dat index 5ffea7f8f..21927c800 100644 --- a/tests/test_mgxs_library_distribcell/inputs_true.dat +++ b/tests/test_mgxs_library_distribcell/inputs_true.dat @@ -1 +1 @@ -c46381a2d86bd849ca20dc64022ffcf836ba0f236f392bba6335c42559df61d14d09a616bc3a9590d954a5bf099610eb071982296b75b10d1c168cc3e343d383 \ No newline at end of file +018bbbc2099f7b94180b391e46e42fc9a82498c60b3f8f7f4c91480ea373427932d287fe571d53b2397f329e71485e7155d7644f0f995bbcb458ba3e872ab043 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index 0d5c7c7b4..318ec408a 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,5 +1,8 @@ avg(distribcell) group in nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.695166 0.510606 avg(distribcell) group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 \ No newline at end of file +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 +1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 +2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 +3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 avg(distribcell) group out nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py index d488e8ec9..32f5ea1bd 100644 --- a/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py +++ b/tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py @@ -29,6 +29,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] self.mgxs_lib.energy_groups = energy_groups + self.mgxs_lib.legendre_order = 3 self.mgxs_lib.domain_type = 'distribcell' material_cells = self.mgxs_lib.openmc_geometry.get_all_material_cells() self.mgxs_lib.domains = [material_cells[-1]] diff --git a/tests/test_mgxs_library_hdf5/inputs_true.dat b/tests/test_mgxs_library_hdf5/inputs_true.dat index 064981fa9..3643c9a2e 100644 --- a/tests/test_mgxs_library_hdf5/inputs_true.dat +++ b/tests/test_mgxs_library_hdf5/inputs_true.dat @@ -1 +1 @@ -ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file +104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f \ No newline at end of file diff --git a/tests/test_mgxs_library_hdf5/results_true.dat b/tests/test_mgxs_library_hdf5/results_true.dat index 93aceba7d..3cae57747 100644 --- a/tests/test_mgxs_library_hdf5/results_true.dat +++ b/tests/test_mgxs_library_hdf5/results_true.dat @@ -5,10 +5,16 @@ domain=1 type=nu-fission [ 0.02178897 0.71407658] [ 0.00118187 0.04055185] domain=1 type=nu-scatter matrix -[[ 0.33724504 0.00155945] - [ 0. 0.42205129]] -[[ 0.02301463 0.00051015] - [ 0. 0.02161702]] +[[[ 3.81546297e-01 4.43012537e-02 2.06462886e-02 1.36952959e-02] + [ 1.55945353e-03 -5.97269486e-04 -2.38789528e-04 1.75508083e-04]] + + [[ 0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00] + [ 4.03915981e-01 -1.13103276e-02 -1.48065932e-02 -6.85505346e-03]]] +[[[ 0.02403322 0.00472203 0.00253903 0.00222437] + [ 0.00051015 0.00022485 0.00022157 0.00020939]] + + [[ 0. 0. 0. 0. ] + [ 0.01896646 0.00783919 0.00862908 0.00904704]]] domain=1 type=chi [ 1. 0.] [ 0.05533329 0. ] @@ -19,10 +25,16 @@ domain=2 type=nu-fission [ 0. 0.] [ 0. 0.] domain=2 type=nu-scatter matrix -[[ 0.23725441 0. ] - [ 0. 0.28593027]] -[[ 0.00818357 0. ] - [ 0. 0.04879593]] +[[[ 0.27311543 0.03586102 0.02970389 0.00224892] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0.26405068 -0.02187959 -0.01529469 0.01403395]]] +[[[ 0.00625287 0.00587756 0.00664018 0.00337568] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0.04539742 0.01221814 0.01027609 0.01431818]]] domain=2 type=chi [ 0. 0.] [ 0. 0.] @@ -33,10 +45,16 @@ domain=3 type=nu-fission [ 0. 0.] [ 0. 0.] domain=3 type=nu-scatter matrix -[[ 0.25993686 0.02618721] - [ 0. 1.35952132]] -[[ 0.02611466 0.00166461] - [ 0. 0.2585046 ]] +[[[ 0.64334557 0.38340871 0.15218526 0.00303724] + [ 0.02618721 0.00736219 -0.00273849 -0.00271989]] + + [[ 0. 0. 0. 0. ] + [ 1.92421362 0.4984312 0.09120485 0.01705441]]] +[[[ 0.02837604 0.01644677 0.00957372 0.00464802] + [ 0.00166461 0.00093414 0.00075617 0.00055807]] + + [[ 0. 0. 0. 0. ] + [ 0.28406198 0.06342067 0.01372628 0.01391602]]] domain=3 type=chi [ 0. 0.] [ 0. 0.] @@ -47,10 +65,16 @@ domain=4 type=nu-fission [ 0. 0.] [ 0. 0.] domain=4 type=nu-scatter matrix -[[ 0.2179296 0.023662 ] - [ 0. 1.21507398]] -[[ 0.0585649 0.00308328] - [ 0. 0.3810251 ]] +[[[ 0.54394096 0.32601136 0.13113269 0.01210477] + [ 0.023662 0.00752551 -0.00272975 -0.0031405 ]] + + [[ 0. 0. 0. 0. ] + [ 1.76464845 0.50069481 0.09902596 0.03297543]]] +[[[ 0.06542705 0.03860196 0.0174751 0.00607268] + [ 0.00308328 0.00130111 0.00084112 0.00057761]] + + [[ 0. 0. 0. 0. ] + [ 0.41620952 0.12217802 0.03871874 0.02510259]]] domain=4 type=chi [ 0. 0.] [ 0. 0.] @@ -61,10 +85,16 @@ domain=5 type=nu-fission [ 0. 0.] [ 0. 0.] domain=5 type=nu-scatter matrix -[[ 0. 0.] - [ 0. 0.]] -[[ 0. 0.] - [ 0. 0.]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] domain=5 type=chi [ 0. 0.] [ 0. 0.] @@ -75,10 +105,16 @@ domain=6 type=nu-fission [ 0. 0.] [ 0. 0.] domain=6 type=nu-scatter matrix -[[ 0. 0.] - [ 0. 0.]] -[[ 0. 0.] - [ 0. 0.]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] domain=6 type=chi [ 0. 0.] [ 0. 0.] @@ -89,10 +125,16 @@ domain=7 type=nu-fission [ 0. 0.] [ 0. 0.] domain=7 type=nu-scatter matrix -[[ 0. 0.] - [ 0. 0.]] -[[ 0. 0.] - [ 0. 0.]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] domain=7 type=chi [ 0. 0.] [ 0. 0.] @@ -103,10 +145,16 @@ domain=8 type=nu-fission [ 0. 0.] [ 0. 0.] domain=8 type=nu-scatter matrix -[[ 0. 0.] - [ 0. 0.]] -[[ 0. 0.] - [ 0. 0.]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] +[[[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]] + + [[ 0. 0. 0. 0.] + [ 0. 0. 0. 0.]]] domain=8 type=chi [ 0. 0.] [ 0. 0.] @@ -117,10 +165,16 @@ domain=9 type=nu-fission [ 0. 0.] [ 0. 0.] domain=9 type=nu-scatter matrix -[[ 0.60053598 0. ] - [ 0. 0. ]] -[[ 0.74887543 0. ] - [ 0. 0. ]] +[[[ 0.72037987 0.11984389 0.03852204 0.05602285] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0. 0. 0. 0. ]]] +[[[ 0.77101455 0.18469083 0.06448453 0.05059534] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0. 0. 0. 0. ]]] domain=9 type=chi [ 0. 0.] [ 0. 0.] @@ -131,10 +185,16 @@ domain=10 type=nu-fission [ 0. 0.] [ 0. 0.] domain=10 type=nu-scatter matrix -[[ 0.23551495 0. ] - [ 0. 0. ]] -[[ 0.61397415 0. ] - [ 0. 0. ]] +[[[ 0.50100891 0.26549396 0.14197875 0.07425836] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0. 0. 0. 0. ]]] +[[[ 0.70853359 0.37546516 0.20078827 0.10501718] + [ 0. 0. 0. 0. ]] + + [[ 0. 0. 0. 0. ] + [ 0. 0. 0. 0. ]]] domain=10 type=chi [ 0. 0.] [ 0. 0.] @@ -145,10 +205,16 @@ domain=11 type=nu-fission [ 0. 0.] [ 0. 0.] domain=11 type=nu-scatter matrix -[[ 0.15444875 0.03187517] - [ 0. 0.90308451]] -[[ 0.59768579 0.0450783 ] - [ 0. 1.53214394]] +[[[ 0.47812753 0.32367878 0.14337507 0.05400336] + [ 0.03187517 0.00858456 -0.01246962 -0.01132019]] + + [[ 0. 0. 0. 0. ] + [ 1.20124973 0.28661101 0.21819147 -0.04851424]]] +[[[ 0.67617444 0.45775092 0.20276296 0.07637229] + [ 0.0450783 0.0121404 0.01763471 0.01600917]] + + [[ 0. 0. 0. 0. ] + [ 1.69882367 0.40532917 0.30856933 0.0686095 ]]] domain=11 type=chi [ 0. 0.] [ 0. 0.] @@ -159,10 +225,16 @@ domain=12 type=nu-fission [ 0. 0.] [ 0. 0.] domain=12 type=nu-scatter matrix -[[ 0.18605249 0.02723959] - [ 0. 1.35711799]] -[[ 0.25763254 0.02955488] - [ 0. 2.08984614]] +[[[ 0.40859392 0.22254143 0.0909719 0.03100368] + [ 0.02723959 -0.01008785 -0.00694631 0.00969231]] + + [[ 0. 0. 0. 0. ] + [ 1.57432766 0.22974802 0.01417839 0.03899727]]] +[[[ 0.27812309 0.14577636 0.06962553 0.03598053] + [ 0.02955488 0.01094529 0.00753673 0.01051613]] + + [[ 0. 0. 0. 0. ] + [ 2.22643553 0.32491277 0.02005128 0.05515046]]] domain=12 type=chi [ 0. 0.] [ 0. 0.] diff --git a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py index 91bb036e3..2d7ed2ef3 100644 --- a/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py +++ b/tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py @@ -29,6 +29,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] self.mgxs_lib.energy_groups = energy_groups + self.mgxs_lib.legendre_order = 3 self.mgxs_lib.domain_type = 'material' self.mgxs_lib.build_library() diff --git a/tests/test_mgxs_library_no_nuclides/inputs_true.dat b/tests/test_mgxs_library_no_nuclides/inputs_true.dat index 064981fa9..3643c9a2e 100644 --- a/tests/test_mgxs_library_no_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_no_nuclides/inputs_true.dat @@ -1 +1 @@ -ee40a2b826dea8323249c7261502f8339c78a5dc236e019842cc5244c048d5978fe66e036b86d46b262260556fbd62b19cbb2f0d70325b92b8c40275e75afe4f \ No newline at end of file +104e7fb527770ac5d3fc636da7716e8fb05d55761253d30516c899f466e6b38ffd881611a3d0cdf65c6af058c32f6f6758c68782be7a170d21024bdae751862f \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 7361c60be..9d6e35871 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -2,120 +2,264 @@ 1 1 1 total 0.372745 0.024269 0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. 1 1 1 total 0.021789 0.001182 -0 1 2 total 0.714077 0.040552 material group in group out nuclide mean std. dev. -3 1 1 1 total 0.337245 0.023015 -2 1 1 2 total 0.001559 0.000510 -1 1 2 1 total 0.000000 0.000000 -0 1 2 2 total 0.422051 0.021617 material group out nuclide mean std. dev. -1 1 1 total 1.0 0.055333 -0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev. +0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean +12 1 1 1 total P0 0.381546 +13 1 1 1 total P1 0.044301 +14 1 1 1 total P2 0.020646 +15 1 1 1 total P3 0.013695 +8 1 1 2 total P0 0.001559 +9 1 1 2 total P1 -0.000597 +10 1 1 2 total P2 -0.000239 +11 1 1 2 total P3 0.000176 +4 1 2 1 total P0 0.000000 +5 1 2 1 total P1 0.000000 +6 1 2 1 total P2 0.000000 +7 1 2 1 total P3 0.000000 +0 1 2 2 total P0 0.403916 +1 1 2 2 total P1 -0.011310 +2 1 2 2 total P2 -0.014807 +3 1 2 2 total P3 -0.006855 material group out nuclide mean std. dev. +1 1 1 total 1 0.055333 +0 1 2 total 0 0.000000 material group in nuclide mean std. dev. 1 2 1 total 0.237254 0.008184 0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 2 1 1 total 0.237254 0.008184 -2 2 1 2 total 0.000000 0.000000 -1 2 2 1 total 0.000000 0.000000 -0 2 2 2 total 0.285930 0.048796 material group out nuclide mean std. dev. -1 2 1 total 0.0 0.0 -0 2 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 2 1 total 0 0 +0 2 2 total 0 0 material group in group out nuclide moment mean +12 2 1 1 total P0 0.273115 +13 2 1 1 total P1 0.035861 +14 2 1 1 total P2 0.029704 +15 2 1 1 total P3 0.002249 +8 2 1 2 total P0 0.000000 +9 2 1 2 total P1 0.000000 +10 2 1 2 total P2 0.000000 +11 2 1 2 total P3 0.000000 +4 2 2 1 total P0 0.000000 +5 2 2 1 total P1 0.000000 +6 2 2 1 total P2 0.000000 +7 2 2 1 total P3 0.000000 +0 2 2 2 total P0 0.264051 +1 2 2 2 total P1 -0.021880 +2 2 2 2 total P2 -0.015295 +3 2 2 2 total P3 0.014034 material group out nuclide mean std. dev. +1 2 1 total 0 0 +0 2 2 total 0 0 material group in nuclide mean std. dev. 1 3 1 total 0.286906 0.027401 0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 3 1 1 total 0.259937 0.026115 -2 3 1 2 total 0.026187 0.001665 -1 3 2 1 total 0.000000 0.000000 -0 3 2 2 total 1.359521 0.258505 material group out nuclide mean std. dev. -1 3 1 total 0.0 0.0 -0 3 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 3 1 total 0 0 +0 3 2 total 0 0 material group in group out nuclide moment mean +12 3 1 1 total P0 0.643346 +13 3 1 1 total P1 0.383409 +14 3 1 1 total P2 0.152185 +15 3 1 1 total P3 0.003037 +8 3 1 2 total P0 0.026187 +9 3 1 2 total P1 0.007362 +10 3 1 2 total P2 -0.002738 +11 3 1 2 total P3 -0.002720 +4 3 2 1 total P0 0.000000 +5 3 2 1 total P1 0.000000 +6 3 2 1 total P2 0.000000 +7 3 2 1 total P3 0.000000 +0 3 2 2 total P0 1.924214 +1 3 2 2 total P1 0.498431 +2 3 2 2 total P2 0.091205 +3 3 2 2 total P3 0.017054 material group out nuclide mean std. dev. +1 3 1 total 0 0 +0 3 2 total 0 0 material group in nuclide mean std. dev. 1 4 1 total 0.242447 0.061031 0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. -1 4 1 total 0.0 0.0 -0 4 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 4 1 1 total 0.217930 0.058565 -2 4 1 2 total 0.023662 0.003083 -1 4 2 1 total 0.000000 0.000000 -0 4 2 2 total 1.215074 0.381025 material group out nuclide mean std. dev. -1 4 1 total 0.0 0.0 -0 4 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 5 1 1 total 0.0 0.0 -2 5 1 2 total 0.0 0.0 -1 5 2 1 total 0.0 0.0 -0 5 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 5 1 total 0.0 0.0 -0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 6 1 1 total 0.0 0.0 -2 6 1 2 total 0.0 0.0 -1 6 2 1 total 0.0 0.0 -0 6 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 6 1 total 0.0 0.0 -0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 7 1 1 total 0.0 0.0 -2 7 1 2 total 0.0 0.0 -1 7 2 1 total 0.0 0.0 -0 7 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 7 1 total 0.0 0.0 -0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 8 1 1 total 0.0 0.0 -2 8 1 2 total 0.0 0.0 -1 8 2 1 total 0.0 0.0 -0 8 2 2 total 0.0 0.0 material group out nuclide mean std. dev. -1 8 1 total 0.0 0.0 -0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 4 1 total 0 0 +0 4 2 total 0 0 material group in group out nuclide moment mean +12 4 1 1 total P0 0.543941 +13 4 1 1 total P1 0.326011 +14 4 1 1 total P2 0.131133 +15 4 1 1 total P3 0.012105 +8 4 1 2 total P0 0.023662 +9 4 1 2 total P1 0.007526 +10 4 1 2 total P2 -0.002730 +11 4 1 2 total P3 -0.003140 +4 4 2 1 total P0 0.000000 +5 4 2 1 total P1 0.000000 +6 4 2 1 total P2 0.000000 +7 4 2 1 total P3 0.000000 +0 4 2 2 total P0 1.764648 +1 4 2 2 total P1 0.500695 +2 4 2 2 total P2 0.099026 +3 4 2 2 total P3 0.032975 material group out nuclide mean std. dev. +1 4 1 total 0 0 +0 4 2 total 0 0 material group in nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in group out nuclide moment mean +12 5 1 1 total P0 0 +13 5 1 1 total P1 0 +14 5 1 1 total P2 0 +15 5 1 1 total P3 0 +8 5 1 2 total P0 0 +9 5 1 2 total P1 0 +10 5 1 2 total P2 0 +11 5 1 2 total P3 0 +4 5 2 1 total P0 0 +5 5 2 1 total P1 0 +6 5 2 1 total P2 0 +7 5 2 1 total P3 0 +0 5 2 2 total P0 0 +1 5 2 2 total P1 0 +2 5 2 2 total P2 0 +3 5 2 2 total P3 0 material group out nuclide mean std. dev. +1 5 1 total 0 0 +0 5 2 total 0 0 material group in nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in group out nuclide moment mean +12 6 1 1 total P0 0 +13 6 1 1 total P1 0 +14 6 1 1 total P2 0 +15 6 1 1 total P3 0 +8 6 1 2 total P0 0 +9 6 1 2 total P1 0 +10 6 1 2 total P2 0 +11 6 1 2 total P3 0 +4 6 2 1 total P0 0 +5 6 2 1 total P1 0 +6 6 2 1 total P2 0 +7 6 2 1 total P3 0 +0 6 2 2 total P0 0 +1 6 2 2 total P1 0 +2 6 2 2 total P2 0 +3 6 2 2 total P3 0 material group out nuclide mean std. dev. +1 6 1 total 0 0 +0 6 2 total 0 0 material group in nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in group out nuclide moment mean +12 7 1 1 total P0 0 +13 7 1 1 total P1 0 +14 7 1 1 total P2 0 +15 7 1 1 total P3 0 +8 7 1 2 total P0 0 +9 7 1 2 total P1 0 +10 7 1 2 total P2 0 +11 7 1 2 total P3 0 +4 7 2 1 total P0 0 +5 7 2 1 total P1 0 +6 7 2 1 total P2 0 +7 7 2 1 total P3 0 +0 7 2 2 total P0 0 +1 7 2 2 total P1 0 +2 7 2 2 total P2 0 +3 7 2 2 total P3 0 material group out nuclide mean std. dev. +1 7 1 total 0 0 +0 7 2 total 0 0 material group in nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in group out nuclide moment mean +12 8 1 1 total P0 0 +13 8 1 1 total P1 0 +14 8 1 1 total P2 0 +15 8 1 1 total P3 0 +8 8 1 2 total P0 0 +9 8 1 2 total P1 0 +10 8 1 2 total P2 0 +11 8 1 2 total P3 0 +4 8 2 1 total P0 0 +5 8 2 1 total P1 0 +6 8 2 1 total P2 0 +7 8 2 1 total P3 0 +0 8 2 2 total P0 0 +1 8 2 2 total P1 0 +2 8 2 2 total P2 0 +3 8 2 2 total P3 0 material group out nuclide mean std. dev. +1 8 1 total 0 0 +0 8 2 total 0 0 material group in nuclide mean std. dev. 1 9 1 total 0.600536 0.748875 0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 9 1 total 0.0 0.0 -0 9 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 9 1 1 total 0.600536 0.748875 -2 9 1 2 total 0.000000 0.000000 -1 9 2 1 total 0.000000 0.000000 -0 9 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. -1 9 1 total 0.0 0.0 -0 9 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 9 1 total 0 0 +0 9 2 total 0 0 material group in group out nuclide moment mean +12 9 1 1 total P0 0.720380 +13 9 1 1 total P1 0.119844 +14 9 1 1 total P2 0.038522 +15 9 1 1 total P3 0.056023 +8 9 1 2 total P0 0.000000 +9 9 1 2 total P1 0.000000 +10 9 1 2 total P2 0.000000 +11 9 1 2 total P3 0.000000 +4 9 2 1 total P0 0.000000 +5 9 2 1 total P1 0.000000 +6 9 2 1 total P2 0.000000 +7 9 2 1 total P3 0.000000 +0 9 2 2 total P0 0.000000 +1 9 2 2 total P1 0.000000 +2 9 2 2 total P2 0.000000 +3 9 2 2 total P3 0.000000 material group out nuclide mean std. dev. +1 9 1 total 0 0 +0 9 2 total 0 0 material group in nuclide mean std. dev. 1 10 1 total 0.235515 0.613974 0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 10 1 total 0.0 0.0 -0 10 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 10 1 1 total 0.235515 0.613974 -2 10 1 2 total 0.000000 0.000000 -1 10 2 1 total 0.000000 0.000000 -0 10 2 2 total 0.000000 0.000000 material group out nuclide mean std. dev. -1 10 1 total 0.0 0.0 -0 10 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 10 1 total 0 0 +0 10 2 total 0 0 material group in group out nuclide moment mean +12 10 1 1 total P0 0.501009 +13 10 1 1 total P1 0.265494 +14 10 1 1 total P2 0.141979 +15 10 1 1 total P3 0.074258 +8 10 1 2 total P0 0.000000 +9 10 1 2 total P1 0.000000 +10 10 1 2 total P2 0.000000 +11 10 1 2 total P3 0.000000 +4 10 2 1 total P0 0.000000 +5 10 2 1 total P1 0.000000 +6 10 2 1 total P2 0.000000 +7 10 2 1 total P3 0.000000 +0 10 2 2 total P0 0.000000 +1 10 2 2 total P1 0.000000 +2 10 2 2 total P2 0.000000 +3 10 2 2 total P3 0.000000 material group out nuclide mean std. dev. +1 10 1 total 0 0 +0 10 2 total 0 0 material group in nuclide mean std. dev. 1 11 1 total 0.186324 0.632129 0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. -1 11 1 total 0.0 0.0 -0 11 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 11 1 1 total 0.154449 0.597686 -2 11 1 2 total 0.031875 0.045078 -1 11 2 1 total 0.000000 0.000000 -0 11 2 2 total 0.903085 1.532144 material group out nuclide mean std. dev. -1 11 1 total 0.0 0.0 -0 11 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 11 1 total 0 0 +0 11 2 total 0 0 material group in group out nuclide moment mean +12 11 1 1 total P0 0.478128 +13 11 1 1 total P1 0.323679 +14 11 1 1 total P2 0.143375 +15 11 1 1 total P3 0.054003 +8 11 1 2 total P0 0.031875 +9 11 1 2 total P1 0.008585 +10 11 1 2 total P2 -0.012470 +11 11 1 2 total P3 -0.011320 +4 11 2 1 total P0 0.000000 +5 11 2 1 total P1 0.000000 +6 11 2 1 total P2 0.000000 +7 11 2 1 total P3 0.000000 +0 11 2 2 total P0 1.201250 +1 11 2 2 total P1 0.286611 +2 11 2 2 total P2 0.218191 +3 11 2 2 total P3 -0.048514 material group out nuclide mean std. dev. +1 11 1 total 0 0 +0 11 2 total 0 0 material group in nuclide mean std. dev. 1 12 1 total 0.213292 0.271444 0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. -1 12 1 total 0.0 0.0 -0 12 2 total 0.0 0.0 material group in group out nuclide mean std. dev. -3 12 1 1 total 0.186052 0.257633 -2 12 1 2 total 0.027240 0.029555 -1 12 2 1 total 0.000000 0.000000 -0 12 2 2 total 1.357118 2.089846 material group out nuclide mean std. dev. -1 12 1 total 0.0 0.0 -0 12 2 total 0.0 0.0 \ No newline at end of file +1 12 1 total 0 0 +0 12 2 total 0 0 material group in group out nuclide moment mean +12 12 1 1 total P0 0.408594 +13 12 1 1 total P1 0.222541 +14 12 1 1 total P2 0.090972 +15 12 1 1 total P3 0.031004 +8 12 1 2 total P0 0.027240 +9 12 1 2 total P1 -0.010088 +10 12 1 2 total P2 -0.006946 +11 12 1 2 total P3 0.009692 +4 12 2 1 total P0 0.000000 +5 12 2 1 total P1 0.000000 +6 12 2 1 total P2 0.000000 +7 12 2 1 total P3 0.000000 +0 12 2 2 total P0 1.574328 +1 12 2 2 total P1 0.229748 +2 12 2 2 total P2 0.014178 +3 12 2 2 total P3 0.038997 material group out nuclide mean std. dev. +1 12 1 total 0 0 +0 12 2 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py index 15f90cb87..6ee8813d0 100644 --- a/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py +++ b/tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py @@ -28,6 +28,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] self.mgxs_lib.energy_groups = energy_groups + self.mgxs_lib.legendre_order = 3 self.mgxs_lib.domain_type = 'material' self.mgxs_lib.build_library() diff --git a/tests/test_mgxs_library_nuclides/inputs_true.dat b/tests/test_mgxs_library_nuclides/inputs_true.dat index d2c11978a..9e25fe96a 100644 --- a/tests/test_mgxs_library_nuclides/inputs_true.dat +++ b/tests/test_mgxs_library_nuclides/inputs_true.dat @@ -1 +1 @@ -f4abbd7867b0f0d2d9d93ed089c95904541f970522e1ef3a843373b60094ef4571a64a7b5f68efe9e51fd49754bc9e20a3bcc85c0bde3a8224608f8b97c01b85 \ No newline at end of file +791a2bd647b8bae03aafc39e29ff1ce1ffc44063b0d757ccba4e1eda6eb73b8a275020f4f5774b17dede49fbf15549787279c8b2fc45caba0097155b32e56fa8 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index b0d62ebd0..20d2d8d5a 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -134,211 +134,619 @@ 30 1 2 Sm-152 0.000000e+00 0.000000e+00 31 1 2 Eu-153 0.000000e+00 0.000000e+00 32 1 2 Gd-155 0.000000e+00 0.000000e+00 -33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide mean std. dev. -102 1 1 1 U-234 0.000000 0.000000 -103 1 1 1 U-235 0.003226 0.001139 -104 1 1 1 U-236 0.001697 0.000923 -105 1 1 1 U-238 0.194468 0.013279 -106 1 1 1 Np-237 0.000000 0.000000 -107 1 1 1 Pu-238 0.000000 0.000000 -108 1 1 1 Pu-239 0.001005 0.000477 -109 1 1 1 Pu-240 0.001307 0.000295 -110 1 1 1 Pu-241 0.000344 0.000244 -111 1 1 1 Pu-242 0.000000 0.000000 -112 1 1 1 Am-241 0.000000 0.000000 -113 1 1 1 Am-242m 0.000000 0.000000 -114 1 1 1 Am-243 0.000000 0.000000 -115 1 1 1 Cm-242 0.000000 0.000000 -116 1 1 1 Cm-243 0.000000 0.000000 -117 1 1 1 Cm-244 0.000000 0.000000 -118 1 1 1 Cm-245 0.000000 0.000000 -119 1 1 1 Mo-95 0.000000 0.000000 -120 1 1 1 Tc-99 0.000000 0.000000 -121 1 1 1 Ru-101 0.000238 0.000254 -122 1 1 1 Ru-103 0.000002 0.000243 -123 1 1 1 Ag-109 0.000000 0.000000 -124 1 1 1 Xe-135 0.000000 0.000000 -125 1 1 1 Cs-133 0.000000 0.000000 -126 1 1 1 Nd-143 0.000447 0.000292 -127 1 1 1 Nd-145 0.000564 0.000294 -128 1 1 1 Sm-147 0.000000 0.000000 -129 1 1 1 Sm-149 0.000000 0.000000 -130 1 1 1 Sm-150 0.000299 0.000238 -131 1 1 1 Sm-151 0.000000 0.000000 -132 1 1 1 Sm-152 0.000492 0.000352 -133 1 1 1 Eu-153 0.000000 0.000000 -134 1 1 1 Gd-155 0.000000 0.000000 -135 1 1 1 O-16 0.133156 0.009821 -68 1 1 2 U-234 0.000000 0.000000 -69 1 1 2 U-235 0.000000 0.000000 -70 1 1 2 U-236 0.000000 0.000000 -71 1 1 2 U-238 0.000173 0.000173 -72 1 1 2 Np-237 0.000000 0.000000 -73 1 1 2 Pu-238 0.000000 0.000000 -74 1 1 2 Pu-239 0.000000 0.000000 -75 1 1 2 Pu-240 0.000000 0.000000 -76 1 1 2 Pu-241 0.000000 0.000000 -77 1 1 2 Pu-242 0.000000 0.000000 -78 1 1 2 Am-241 0.000000 0.000000 -79 1 1 2 Am-242m 0.000000 0.000000 -80 1 1 2 Am-243 0.000000 0.000000 -81 1 1 2 Cm-242 0.000000 0.000000 -82 1 1 2 Cm-243 0.000000 0.000000 -83 1 1 2 Cm-244 0.000000 0.000000 -84 1 1 2 Cm-245 0.000000 0.000000 -85 1 1 2 Mo-95 0.000000 0.000000 -86 1 1 2 Tc-99 0.000000 0.000000 -87 1 1 2 Ru-101 0.000000 0.000000 -88 1 1 2 Ru-103 0.000000 0.000000 -89 1 1 2 Ag-109 0.000000 0.000000 -90 1 1 2 Xe-135 0.000000 0.000000 -91 1 1 2 Cs-133 0.000000 0.000000 -92 1 1 2 Nd-143 0.000000 0.000000 -93 1 1 2 Nd-145 0.000000 0.000000 -94 1 1 2 Sm-147 0.000000 0.000000 -95 1 1 2 Sm-149 0.000000 0.000000 -96 1 1 2 Sm-150 0.000000 0.000000 -97 1 1 2 Sm-151 0.000000 0.000000 -98 1 1 2 Sm-152 0.000000 0.000000 -99 1 1 2 Eu-153 0.000000 0.000000 -100 1 1 2 Gd-155 0.000000 0.000000 -101 1 1 2 O-16 0.001386 0.000446 -34 1 2 1 U-234 0.000000 0.000000 -35 1 2 1 U-235 0.000000 0.000000 -36 1 2 1 U-236 0.000000 0.000000 -37 1 2 1 U-238 0.000000 0.000000 -38 1 2 1 Np-237 0.000000 0.000000 -39 1 2 1 Pu-238 0.000000 0.000000 -40 1 2 1 Pu-239 0.000000 0.000000 -41 1 2 1 Pu-240 0.000000 0.000000 -42 1 2 1 Pu-241 0.000000 0.000000 -43 1 2 1 Pu-242 0.000000 0.000000 -44 1 2 1 Am-241 0.000000 0.000000 -45 1 2 1 Am-242m 0.000000 0.000000 -46 1 2 1 Am-243 0.000000 0.000000 -47 1 2 1 Cm-242 0.000000 0.000000 -48 1 2 1 Cm-243 0.000000 0.000000 -49 1 2 1 Cm-244 0.000000 0.000000 -50 1 2 1 Cm-245 0.000000 0.000000 -51 1 2 1 Mo-95 0.000000 0.000000 -52 1 2 1 Tc-99 0.000000 0.000000 -53 1 2 1 Ru-101 0.000000 0.000000 -54 1 2 1 Ru-103 0.000000 0.000000 -55 1 2 1 Ag-109 0.000000 0.000000 -56 1 2 1 Xe-135 0.000000 0.000000 -57 1 2 1 Cs-133 0.000000 0.000000 -58 1 2 1 Nd-143 0.000000 0.000000 -59 1 2 1 Nd-145 0.000000 0.000000 -60 1 2 1 Sm-147 0.000000 0.000000 -61 1 2 1 Sm-149 0.000000 0.000000 -62 1 2 1 Sm-150 0.000000 0.000000 -63 1 2 1 Sm-151 0.000000 0.000000 -64 1 2 1 Sm-152 0.000000 0.000000 -65 1 2 1 Eu-153 0.000000 0.000000 -66 1 2 1 Gd-155 0.000000 0.000000 -67 1 2 1 O-16 0.000000 0.000000 -0 1 2 2 U-234 0.000000 0.000000 -1 1 2 2 U-235 0.003889 0.003962 -2 1 2 2 U-236 0.001501 0.002037 -3 1 2 2 U-238 0.219715 0.025984 -4 1 2 2 Np-237 0.000000 0.000000 -5 1 2 2 Pu-238 0.000000 0.000000 -6 1 2 2 Pu-239 0.000000 0.000000 -7 1 2 2 Pu-240 0.000000 0.000000 -8 1 2 2 Pu-241 0.000000 0.000000 -9 1 2 2 Pu-242 0.000000 0.000000 -10 1 2 2 Am-241 0.000000 0.000000 -11 1 2 2 Am-242m 0.000000 0.000000 -12 1 2 2 Am-243 0.000000 0.000000 -13 1 2 2 Cm-242 0.000000 0.000000 -14 1 2 2 Cm-243 0.000000 0.000000 -15 1 2 2 Cm-244 0.000000 0.000000 -16 1 2 2 Cm-245 0.000000 0.000000 -17 1 2 2 Mo-95 0.000000 0.000000 -18 1 2 2 Tc-99 0.000000 0.000000 -19 1 2 2 Ru-101 0.000000 0.000000 -20 1 2 2 Ru-103 0.000000 0.000000 -21 1 2 2 Ag-109 0.000000 0.000000 -22 1 2 2 Xe-135 0.000000 0.000000 -23 1 2 2 Cs-133 0.000000 0.000000 -24 1 2 2 Nd-143 0.000000 0.000000 -25 1 2 2 Nd-145 0.000000 0.000000 -26 1 2 2 Sm-147 0.000000 0.000000 -27 1 2 2 Sm-149 0.000000 0.000000 -28 1 2 2 Sm-150 0.000000 0.000000 -29 1 2 2 Sm-151 0.000000 0.000000 -30 1 2 2 Sm-152 0.000000 0.000000 -31 1 2 2 Eu-153 0.000000 0.000000 -32 1 2 2 Gd-155 0.000000 0.000000 -33 1 2 2 O-16 0.196946 0.014729 material group out nuclide mean std. dev. -34 1 1 U-234 0.0 0.000000 -35 1 1 U-235 1.0 0.066362 -36 1 1 U-236 0.0 0.000000 -37 1 1 U-238 1.0 0.093082 -38 1 1 Np-237 0.0 0.000000 -39 1 1 Pu-238 0.0 0.000000 -40 1 1 Pu-239 1.0 0.104567 -41 1 1 Pu-240 0.0 0.000000 -42 1 1 Pu-241 1.0 0.263696 -43 1 1 Pu-242 0.0 0.000000 -44 1 1 Am-241 0.0 0.000000 -45 1 1 Am-242m 0.0 0.000000 -46 1 1 Am-243 0.0 0.000000 -47 1 1 Cm-242 0.0 0.000000 -48 1 1 Cm-243 0.0 0.000000 -49 1 1 Cm-244 0.0 0.000000 -50 1 1 Cm-245 0.0 0.000000 -51 1 1 Mo-95 0.0 0.000000 -52 1 1 Tc-99 0.0 0.000000 -53 1 1 Ru-101 0.0 0.000000 -54 1 1 Ru-103 0.0 0.000000 -55 1 1 Ag-109 0.0 0.000000 -56 1 1 Xe-135 0.0 0.000000 -57 1 1 Cs-133 0.0 0.000000 -58 1 1 Nd-143 0.0 0.000000 -59 1 1 Nd-145 0.0 0.000000 -60 1 1 Sm-147 0.0 0.000000 -61 1 1 Sm-149 0.0 0.000000 -62 1 1 Sm-150 0.0 0.000000 -63 1 1 Sm-151 0.0 0.000000 -64 1 1 Sm-152 0.0 0.000000 -65 1 1 Eu-153 0.0 0.000000 -66 1 1 Gd-155 0.0 0.000000 -67 1 1 O-16 0.0 0.000000 -0 1 2 U-234 0.0 0.000000 -1 1 2 U-235 0.0 0.000000 -2 1 2 U-236 0.0 0.000000 -3 1 2 U-238 0.0 0.000000 -4 1 2 Np-237 0.0 0.000000 -5 1 2 Pu-238 0.0 0.000000 -6 1 2 Pu-239 0.0 0.000000 -7 1 2 Pu-240 0.0 0.000000 -8 1 2 Pu-241 0.0 0.000000 -9 1 2 Pu-242 0.0 0.000000 -10 1 2 Am-241 0.0 0.000000 -11 1 2 Am-242m 0.0 0.000000 -12 1 2 Am-243 0.0 0.000000 -13 1 2 Cm-242 0.0 0.000000 -14 1 2 Cm-243 0.0 0.000000 -15 1 2 Cm-244 0.0 0.000000 -16 1 2 Cm-245 0.0 0.000000 -17 1 2 Mo-95 0.0 0.000000 -18 1 2 Tc-99 0.0 0.000000 -19 1 2 Ru-101 0.0 0.000000 -20 1 2 Ru-103 0.0 0.000000 -21 1 2 Ag-109 0.0 0.000000 -22 1 2 Xe-135 0.0 0.000000 -23 1 2 Cs-133 0.0 0.000000 -24 1 2 Nd-143 0.0 0.000000 -25 1 2 Nd-145 0.0 0.000000 -26 1 2 Sm-147 0.0 0.000000 -27 1 2 Sm-149 0.0 0.000000 -28 1 2 Sm-150 0.0 0.000000 -29 1 2 Sm-151 0.0 0.000000 -30 1 2 Sm-152 0.0 0.000000 -31 1 2 Eu-153 0.0 0.000000 -32 1 2 Gd-155 0.0 0.000000 -33 1 2 O-16 0.0 0.000000 material group in nuclide mean std. dev. +33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide moment mean +408 1 1 1 U-234 P0 0.000000 +409 1 1 1 U-234 P1 0.000000 +410 1 1 1 U-234 P2 0.000000 +411 1 1 1 U-234 P3 0.000000 +412 1 1 1 U-235 P0 0.003812 +413 1 1 1 U-235 P1 0.000586 +414 1 1 1 U-235 P2 0.000071 +415 1 1 1 U-235 P3 0.000277 +416 1 1 1 U-236 P0 0.001733 +417 1 1 1 U-236 P1 0.000035 +418 1 1 1 U-236 P2 -0.000183 +419 1 1 1 U-236 P3 -0.000087 +420 1 1 1 U-238 P0 0.224908 +421 1 1 1 U-238 P1 0.030440 +422 1 1 1 U-238 P2 0.014265 +423 1 1 1 U-238 P3 0.007698 +424 1 1 1 Np-237 P0 0.000000 +425 1 1 1 Np-237 P1 0.000000 +426 1 1 1 Np-237 P2 0.000000 +427 1 1 1 Np-237 P3 0.000000 +428 1 1 1 Pu-238 P0 0.000000 +429 1 1 1 Pu-238 P1 0.000000 +430 1 1 1 Pu-238 P2 0.000000 +431 1 1 1 Pu-238 P3 0.000000 +432 1 1 1 Pu-239 P0 0.001040 +433 1 1 1 Pu-239 P1 0.000034 +434 1 1 1 Pu-239 P2 0.000090 +435 1 1 1 Pu-239 P3 0.000110 +436 1 1 1 Pu-240 P0 0.001040 +437 1 1 1 Pu-240 P1 -0.000268 +438 1 1 1 Pu-240 P2 -0.000137 +439 1 1 1 Pu-240 P3 0.000132 +440 1 1 1 Pu-241 P0 0.000173 +441 1 1 1 Pu-241 P1 -0.000170 +442 1 1 1 Pu-241 P2 0.000165 +443 1 1 1 Pu-241 P3 -0.000156 +444 1 1 1 Pu-242 P0 0.000000 +445 1 1 1 Pu-242 P1 0.000000 +446 1 1 1 Pu-242 P2 0.000000 +447 1 1 1 Pu-242 P3 0.000000 +448 1 1 1 Am-241 P0 0.000000 +449 1 1 1 Am-241 P1 0.000000 +450 1 1 1 Am-241 P2 0.000000 +451 1 1 1 Am-241 P3 0.000000 +452 1 1 1 Am-242m P0 0.000000 +453 1 1 1 Am-242m P1 0.000000 +454 1 1 1 Am-242m P2 0.000000 +455 1 1 1 Am-242m P3 0.000000 +456 1 1 1 Am-243 P0 0.000000 +457 1 1 1 Am-243 P1 0.000000 +458 1 1 1 Am-243 P2 0.000000 +459 1 1 1 Am-243 P3 0.000000 +460 1 1 1 Cm-242 P0 0.000000 +461 1 1 1 Cm-242 P1 0.000000 +462 1 1 1 Cm-242 P2 0.000000 +463 1 1 1 Cm-242 P3 0.000000 +464 1 1 1 Cm-243 P0 0.000000 +465 1 1 1 Cm-243 P1 0.000000 +466 1 1 1 Cm-243 P2 0.000000 +467 1 1 1 Cm-243 P3 0.000000 +468 1 1 1 Cm-244 P0 0.000000 +469 1 1 1 Cm-244 P1 0.000000 +470 1 1 1 Cm-244 P2 0.000000 +471 1 1 1 Cm-244 P3 0.000000 +472 1 1 1 Cm-245 P0 0.000000 +473 1 1 1 Cm-245 P1 0.000000 +474 1 1 1 Cm-245 P2 0.000000 +475 1 1 1 Cm-245 P3 0.000000 +476 1 1 1 Mo-95 P0 0.000000 +477 1 1 1 Mo-95 P1 0.000000 +478 1 1 1 Mo-95 P2 0.000000 +479 1 1 1 Mo-95 P3 0.000000 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Sm-147 P1 0.000000 +514 1 1 1 Sm-147 P2 0.000000 +515 1 1 1 Sm-147 P3 0.000000 +516 1 1 1 Sm-149 P0 0.000000 +517 1 1 1 Sm-149 P1 0.000000 +518 1 1 1 Sm-149 P2 0.000000 +519 1 1 1 Sm-149 P3 0.000000 +520 1 1 1 Sm-150 P0 0.000347 +521 1 1 1 Sm-150 P1 0.000048 +522 1 1 1 Sm-150 P2 -0.000090 +523 1 1 1 Sm-150 P3 -0.000019 +524 1 1 1 Sm-151 P0 0.000000 +525 1 1 1 Sm-151 P1 0.000000 +526 1 1 1 Sm-151 P2 0.000000 +527 1 1 1 Sm-151 P3 0.000000 +528 1 1 1 Sm-152 P0 0.000693 +529 1 1 1 Sm-152 P1 0.000201 +530 1 1 1 Sm-152 P2 -0.000044 +531 1 1 1 Sm-152 P3 0.000138 +532 1 1 1 Eu-153 P0 0.000000 +533 1 1 1 Eu-153 P1 0.000000 +534 1 1 1 Eu-153 P2 0.000000 +535 1 1 1 Eu-153 P3 0.000000 +536 1 1 1 Gd-155 P0 0.000000 +537 1 1 1 Gd-155 P1 0.000000 +538 1 1 1 Gd-155 P2 0.000000 +539 1 1 1 Gd-155 P3 0.000000 +540 1 1 1 O-16 P0 0.146242 +541 1 1 1 O-16 P1 0.013087 +542 1 1 1 O-16 P2 0.006314 +543 1 1 1 O-16 P3 0.005397 +272 1 1 2 U-234 P0 0.000000 +273 1 1 2 U-234 P1 0.000000 +274 1 1 2 U-234 P2 0.000000 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Pu-241 P2 0.000000 +171 1 2 1 Pu-241 P3 0.000000 +172 1 2 1 Pu-242 P0 0.000000 +173 1 2 1 Pu-242 P1 0.000000 +174 1 2 1 Pu-242 P2 0.000000 +175 1 2 1 Pu-242 P3 0.000000 +176 1 2 1 Am-241 P0 0.000000 +177 1 2 1 Am-241 P1 0.000000 +178 1 2 1 Am-241 P2 0.000000 +179 1 2 1 Am-241 P3 0.000000 +180 1 2 1 Am-242m P0 0.000000 +181 1 2 1 Am-242m P1 0.000000 +182 1 2 1 Am-242m P2 0.000000 +183 1 2 1 Am-242m P3 0.000000 +184 1 2 1 Am-243 P0 0.000000 +185 1 2 1 Am-243 P1 0.000000 +186 1 2 1 Am-243 P2 0.000000 +187 1 2 1 Am-243 P3 0.000000 +188 1 2 1 Cm-242 P0 0.000000 +189 1 2 1 Cm-242 P1 0.000000 +190 1 2 1 Cm-242 P2 0.000000 +191 1 2 1 Cm-242 P3 0.000000 +192 1 2 1 Cm-243 P0 0.000000 +193 1 2 1 Cm-243 P1 0.000000 +194 1 2 1 Cm-243 P2 0.000000 +195 1 2 1 Cm-243 P3 0.000000 +196 1 2 1 Cm-244 P0 0.000000 +197 1 2 1 Cm-244 P1 0.000000 +198 1 2 1 Cm-244 P2 0.000000 +199 1 2 1 Cm-244 P3 0.000000 +200 1 2 1 Cm-245 P0 0.000000 +201 1 2 1 Cm-245 P1 0.000000 +202 1 2 1 Cm-245 P2 0.000000 +203 1 2 1 Cm-245 P3 0.000000 +204 1 2 1 Mo-95 P0 0.000000 +205 1 2 1 Mo-95 P1 0.000000 +206 1 2 1 Mo-95 P2 0.000000 +207 1 2 1 Mo-95 P3 0.000000 +208 1 2 1 Tc-99 P0 0.000000 +209 1 2 1 Tc-99 P1 0.000000 +210 1 2 1 Tc-99 P2 0.000000 +211 1 2 1 Tc-99 P3 0.000000 +212 1 2 1 Ru-101 P0 0.000000 +213 1 2 1 Ru-101 P1 0.000000 +214 1 2 1 Ru-101 P2 0.000000 +215 1 2 1 Ru-101 P3 0.000000 +216 1 2 1 Ru-103 P0 0.000000 +217 1 2 1 Ru-103 P1 0.000000 +218 1 2 1 Ru-103 P2 0.000000 +219 1 2 1 Ru-103 P3 0.000000 +220 1 2 1 Ag-109 P0 0.000000 +221 1 2 1 Ag-109 P1 0.000000 +222 1 2 1 Ag-109 P2 0.000000 +223 1 2 1 Ag-109 P3 0.000000 +224 1 2 1 Xe-135 P0 0.000000 +225 1 2 1 Xe-135 P1 0.000000 +226 1 2 1 Xe-135 P2 0.000000 +227 1 2 1 Xe-135 P3 0.000000 +228 1 2 1 Cs-133 P0 0.000000 +229 1 2 1 Cs-133 P1 0.000000 +230 1 2 1 Cs-133 P2 0.000000 +231 1 2 1 Cs-133 P3 0.000000 +232 1 2 1 Nd-143 P0 0.000000 +233 1 2 1 Nd-143 P1 0.000000 +234 1 2 1 Nd-143 P2 0.000000 +235 1 2 1 Nd-143 P3 0.000000 +236 1 2 1 Nd-145 P0 0.000000 +237 1 2 1 Nd-145 P1 0.000000 +238 1 2 1 Nd-145 P2 0.000000 +239 1 2 1 Nd-145 P3 0.000000 +240 1 2 1 Sm-147 P0 0.000000 +241 1 2 1 Sm-147 P1 0.000000 +242 1 2 1 Sm-147 P2 0.000000 +243 1 2 1 Sm-147 P3 0.000000 +244 1 2 1 Sm-149 P0 0.000000 +245 1 2 1 Sm-149 P1 0.000000 +246 1 2 1 Sm-149 P2 0.000000 +247 1 2 1 Sm-149 P3 0.000000 +248 1 2 1 Sm-150 P0 0.000000 +249 1 2 1 Sm-150 P1 0.000000 +250 1 2 1 Sm-150 P2 0.000000 +251 1 2 1 Sm-150 P3 0.000000 +252 1 2 1 Sm-151 P0 0.000000 +253 1 2 1 Sm-151 P1 0.000000 +254 1 2 1 Sm-151 P2 0.000000 +255 1 2 1 Sm-151 P3 0.000000 +256 1 2 1 Sm-152 P0 0.000000 +257 1 2 1 Sm-152 P1 0.000000 +258 1 2 1 Sm-152 P2 0.000000 +259 1 2 1 Sm-152 P3 0.000000 +260 1 2 1 Eu-153 P0 0.000000 +261 1 2 1 Eu-153 P1 0.000000 +262 1 2 1 Eu-153 P2 0.000000 +263 1 2 1 Eu-153 P3 0.000000 +264 1 2 1 Gd-155 P0 0.000000 +265 1 2 1 Gd-155 P1 0.000000 +266 1 2 1 Gd-155 P2 0.000000 +267 1 2 1 Gd-155 P3 0.000000 +268 1 2 1 O-16 P0 0.000000 +269 1 2 1 O-16 P1 0.000000 +270 1 2 1 O-16 P2 0.000000 +271 1 2 1 O-16 P3 0.000000 +0 1 2 2 U-234 P0 0.000000 +1 1 2 2 U-234 P1 0.000000 +2 1 2 2 U-234 P2 0.000000 +3 1 2 2 U-234 P3 0.000000 +4 1 2 2 U-235 P0 0.003960 +5 1 2 2 U-235 P1 0.000071 +6 1 2 2 U-235 P2 0.001232 +7 1 2 2 U-235 P3 0.000182 +8 1 2 2 U-236 P0 0.001980 +9 1 2 2 U-236 P1 0.000479 +10 1 2 2 U-236 P2 -0.000816 +11 1 2 2 U-236 P3 -0.000648 +12 1 2 2 U-238 P0 0.205918 +13 1 2 2 U-238 P1 -0.013364 +14 1 2 2 U-238 P2 -0.010941 +15 1 2 2 U-238 P3 0.000772 +16 1 2 2 Np-237 P0 0.000000 +17 1 2 2 Np-237 P1 0.000000 +18 1 2 2 Np-237 P2 0.000000 +19 1 2 2 Np-237 P3 0.000000 +20 1 2 2 Pu-238 P0 0.000000 +21 1 2 2 Pu-238 P1 0.000000 +22 1 2 2 Pu-238 P2 0.000000 +23 1 2 2 Pu-238 P3 0.000000 +24 1 2 2 Pu-239 P0 0.000000 +25 1 2 2 Pu-239 P1 0.000000 +26 1 2 2 Pu-239 P2 0.000000 +27 1 2 2 Pu-239 P3 0.000000 +28 1 2 2 Pu-240 P0 0.000000 +29 1 2 2 Pu-240 P1 0.000000 +30 1 2 2 Pu-240 P2 0.000000 +31 1 2 2 Pu-240 P3 0.000000 +32 1 2 2 Pu-241 P0 0.000000 +33 1 2 2 Pu-241 P1 0.000000 +34 1 2 2 Pu-241 P2 0.000000 +35 1 2 2 Pu-241 P3 0.000000 +36 1 2 2 Pu-242 P0 0.000000 +37 1 2 2 Pu-242 P1 0.000000 +38 1 2 2 Pu-242 P2 0.000000 +39 1 2 2 Pu-242 P3 0.000000 +40 1 2 2 Am-241 P0 0.000000 +41 1 2 2 Am-241 P1 0.000000 +42 1 2 2 Am-241 P2 0.000000 +43 1 2 2 Am-241 P3 0.000000 +44 1 2 2 Am-242m P0 0.000000 +45 1 2 2 Am-242m P1 0.000000 +46 1 2 2 Am-242m P2 0.000000 +47 1 2 2 Am-242m P3 0.000000 +48 1 2 2 Am-243 P0 0.000000 +49 1 2 2 Am-243 P1 0.000000 +50 1 2 2 Am-243 P2 0.000000 +51 1 2 2 Am-243 P3 0.000000 +52 1 2 2 Cm-242 P0 0.000000 +53 1 2 2 Cm-242 P1 0.000000 +54 1 2 2 Cm-242 P2 0.000000 +55 1 2 2 Cm-242 P3 0.000000 +56 1 2 2 Cm-243 P0 0.000000 +57 1 2 2 Cm-243 P1 0.000000 +58 1 2 2 Cm-243 P2 0.000000 +59 1 2 2 Cm-243 P3 0.000000 +60 1 2 2 Cm-244 P0 0.000000 +61 1 2 2 Cm-244 P1 0.000000 +62 1 2 2 Cm-244 P2 0.000000 +63 1 2 2 Cm-244 P3 0.000000 +64 1 2 2 Cm-245 P0 0.000000 +65 1 2 2 Cm-245 P1 0.000000 +66 1 2 2 Cm-245 P2 0.000000 +67 1 2 2 Cm-245 P3 0.000000 +68 1 2 2 Mo-95 P0 0.000000 +69 1 2 2 Mo-95 P1 0.000000 +70 1 2 2 Mo-95 P2 0.000000 +71 1 2 2 Mo-95 P3 0.000000 +72 1 2 2 Tc-99 P0 0.000000 +73 1 2 2 Tc-99 P1 0.000000 +74 1 2 2 Tc-99 P2 0.000000 +75 1 2 2 Tc-99 P3 0.000000 +76 1 2 2 Ru-101 P0 0.000000 +77 1 2 2 Ru-101 P1 0.000000 +78 1 2 2 Ru-101 P2 0.000000 +79 1 2 2 Ru-101 P3 0.000000 +80 1 2 2 Ru-103 P0 0.000000 +81 1 2 2 Ru-103 P1 0.000000 +82 1 2 2 Ru-103 P2 0.000000 +83 1 2 2 Ru-103 P3 0.000000 +84 1 2 2 Ag-109 P0 0.000000 +85 1 2 2 Ag-109 P1 0.000000 +86 1 2 2 Ag-109 P2 0.000000 +87 1 2 2 Ag-109 P3 0.000000 +88 1 2 2 Xe-135 P0 0.000000 +89 1 2 2 Xe-135 P1 0.000000 +90 1 2 2 Xe-135 P2 0.000000 +91 1 2 2 Xe-135 P3 0.000000 +92 1 2 2 Cs-133 P0 0.000000 +93 1 2 2 Cs-133 P1 0.000000 +94 1 2 2 Cs-133 P2 0.000000 +95 1 2 2 Cs-133 P3 0.000000 +96 1 2 2 Nd-143 P0 0.000000 +97 1 2 2 Nd-143 P1 0.000000 +98 1 2 2 Nd-143 P2 0.000000 +99 1 2 2 Nd-143 P3 0.000000 +100 1 2 2 Nd-145 P0 0.000000 +101 1 2 2 Nd-145 P1 0.000000 +102 1 2 2 Nd-145 P2 0.000000 +103 1 2 2 Nd-145 P3 0.000000 +104 1 2 2 Sm-147 P0 0.000000 +105 1 2 2 Sm-147 P1 0.000000 +106 1 2 2 Sm-147 P2 0.000000 +107 1 2 2 Sm-147 P3 0.000000 +108 1 2 2 Sm-149 P0 0.000000 +109 1 2 2 Sm-149 P1 0.000000 +110 1 2 2 Sm-149 P2 0.000000 +111 1 2 2 Sm-149 P3 0.000000 +112 1 2 2 Sm-150 P0 0.000000 +113 1 2 2 Sm-150 P1 0.000000 +114 1 2 2 Sm-150 P2 0.000000 +115 1 2 2 Sm-150 P3 0.000000 +116 1 2 2 Sm-151 P0 0.000000 +117 1 2 2 Sm-151 P1 0.000000 +118 1 2 2 Sm-151 P2 0.000000 +119 1 2 2 Sm-151 P3 0.000000 +120 1 2 2 Sm-152 P0 0.000000 +121 1 2 2 Sm-152 P1 0.000000 +122 1 2 2 Sm-152 P2 0.000000 +123 1 2 2 Sm-152 P3 0.000000 +124 1 2 2 Eu-153 P0 0.000000 +125 1 2 2 Eu-153 P1 0.000000 +126 1 2 2 Eu-153 P2 0.000000 +127 1 2 2 Eu-153 P3 0.000000 +128 1 2 2 Gd-155 P0 0.000000 +129 1 2 2 Gd-155 P1 0.000000 +130 1 2 2 Gd-155 P2 0.000000 +131 1 2 2 Gd-155 P3 0.000000 +132 1 2 2 O-16 P0 0.192058 +133 1 2 2 O-16 P1 0.001504 +134 1 2 2 O-16 P2 -0.004281 +135 1 2 2 O-16 P3 -0.007160 material group out nuclide mean std. dev. +34 1 1 U-234 0 0.000000 +35 1 1 U-235 1 0.066362 +36 1 1 U-236 0 0.000000 +37 1 1 U-238 1 0.093082 +38 1 1 Np-237 0 0.000000 +39 1 1 Pu-238 0 0.000000 +40 1 1 Pu-239 1 0.104567 +41 1 1 Pu-240 0 0.000000 +42 1 1 Pu-241 1 0.263696 +43 1 1 Pu-242 0 0.000000 +44 1 1 Am-241 0 0.000000 +45 1 1 Am-242m 0 0.000000 +46 1 1 Am-243 0 0.000000 +47 1 1 Cm-242 0 0.000000 +48 1 1 Cm-243 0 0.000000 +49 1 1 Cm-244 0 0.000000 +50 1 1 Cm-245 0 0.000000 +51 1 1 Mo-95 0 0.000000 +52 1 1 Tc-99 0 0.000000 +53 1 1 Ru-101 0 0.000000 +54 1 1 Ru-103 0 0.000000 +55 1 1 Ag-109 0 0.000000 +56 1 1 Xe-135 0 0.000000 +57 1 1 Cs-133 0 0.000000 +58 1 1 Nd-143 0 0.000000 +59 1 1 Nd-145 0 0.000000 +60 1 1 Sm-147 0 0.000000 +61 1 1 Sm-149 0 0.000000 +62 1 1 Sm-150 0 0.000000 +63 1 1 Sm-151 0 0.000000 +64 1 1 Sm-152 0 0.000000 +65 1 1 Eu-153 0 0.000000 +66 1 1 Gd-155 0 0.000000 +67 1 1 O-16 0 0.000000 +0 1 2 U-234 0 0.000000 +1 1 2 U-235 0 0.000000 +2 1 2 U-236 0 0.000000 +3 1 2 U-238 0 0.000000 +4 1 2 Np-237 0 0.000000 +5 1 2 Pu-238 0 0.000000 +6 1 2 Pu-239 0 0.000000 +7 1 2 Pu-240 0 0.000000 +8 1 2 Pu-241 0 0.000000 +9 1 2 Pu-242 0 0.000000 +10 1 2 Am-241 0 0.000000 +11 1 2 Am-242m 0 0.000000 +12 1 2 Am-243 0 0.000000 +13 1 2 Cm-242 0 0.000000 +14 1 2 Cm-243 0 0.000000 +15 1 2 Cm-244 0 0.000000 +16 1 2 Cm-245 0 0.000000 +17 1 2 Mo-95 0 0.000000 +18 1 2 Tc-99 0 0.000000 +19 1 2 Ru-101 0 0.000000 +20 1 2 Ru-103 0 0.000000 +21 1 2 Ag-109 0 0.000000 +22 1 2 Xe-135 0 0.000000 +23 1 2 Cs-133 0 0.000000 +24 1 2 Nd-143 0 0.000000 +25 1 2 Nd-145 0 0.000000 +26 1 2 Sm-147 0 0.000000 +27 1 2 Sm-149 0 0.000000 +28 1 2 Sm-150 0 0.000000 +29 1 2 Sm-151 0 0.000000 +30 1 2 Sm-152 0 0.000000 +31 1 2 Eu-153 0 0.000000 +32 1 2 Gd-155 0 0.000000 +33 1 2 O-16 0 0.000000 material group in nuclide mean std. dev. 5 2 1 Zr-90 0.104734 0.008915 6 2 1 Zr-91 0.036155 0.003735 7 2 1 Zr-92 0.042422 0.003029 @@ -349,46 +757,106 @@ 2 2 2 Zr-92 0.041633 0.016323 3 2 2 Zr-94 0.060818 0.021483 4 2 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0.0 0.0 -6 2 1 Zr-91 0.0 0.0 -7 2 1 Zr-92 0.0 0.0 -8 2 1 Zr-94 0.0 0.0 -9 2 1 Zr-96 0.0 0.0 -0 2 2 Zr-90 0.0 0.0 -1 2 2 Zr-91 0.0 0.0 -2 2 2 Zr-92 0.0 0.0 -3 2 2 Zr-94 0.0 0.0 -4 2 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -15 2 1 1 Zr-90 0.104734 0.008915 -16 2 1 1 Zr-91 0.036155 0.003735 -17 2 1 1 Zr-92 0.042422 0.003029 -18 2 1 1 Zr-94 0.046148 0.006251 -19 2 1 1 Zr-96 0.007794 0.001536 -10 2 1 2 Zr-90 0.000000 0.000000 -11 2 1 2 Zr-91 0.000000 0.000000 -12 2 1 2 Zr-92 0.000000 0.000000 -13 2 1 2 Zr-94 0.000000 0.000000 -14 2 1 2 Zr-96 0.000000 0.000000 -5 2 2 1 Zr-90 0.000000 0.000000 -6 2 2 1 Zr-91 0.000000 0.000000 -7 2 2 1 Zr-92 0.000000 0.000000 -8 2 2 1 Zr-94 0.000000 0.000000 -9 2 2 1 Zr-96 0.000000 0.000000 -0 2 2 2 Zr-90 0.121688 0.034934 -1 2 2 2 Zr-91 0.061792 0.024317 -2 2 2 2 Zr-92 0.041633 0.016323 -3 2 2 2 Zr-94 0.060818 0.021483 -4 2 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -5 2 1 Zr-90 0.0 0.0 -6 2 1 Zr-91 0.0 0.0 -7 2 1 Zr-92 0.0 0.0 -8 2 1 Zr-94 0.0 0.0 -9 2 1 Zr-96 0.0 0.0 -0 2 2 Zr-90 0.0 0.0 -1 2 2 Zr-91 0.0 0.0 -2 2 2 Zr-92 0.0 0.0 -3 2 2 Zr-94 0.0 0.0 -4 2 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. +5 2 1 Zr-90 0 0 +6 2 1 Zr-91 0 0 +7 2 1 Zr-92 0 0 +8 2 1 Zr-94 0 0 +9 2 1 Zr-96 0 0 +0 2 2 Zr-90 0 0 +1 2 2 Zr-91 0 0 +2 2 2 Zr-92 0 0 +3 2 2 Zr-94 0 0 +4 2 2 Zr-96 0 0 material group in group out nuclide moment mean +60 2 1 1 Zr-90 P0 0.122030 +61 2 1 1 Zr-90 P1 0.017296 +62 2 1 1 Zr-90 P2 0.020437 +63 2 1 1 Zr-90 P3 -0.000350 +64 2 1 1 Zr-91 P0 0.037548 +65 2 1 1 Zr-91 P1 0.001393 +66 2 1 1 Zr-91 P2 -0.000553 +67 2 1 1 Zr-91 P3 0.001719 +68 2 1 1 Zr-92 P0 0.047829 +69 2 1 1 Zr-92 P1 0.005406 +70 2 1 1 Zr-92 P2 0.004793 +71 2 1 1 Zr-92 P3 0.001907 +72 2 1 1 Zr-94 P0 0.058110 +73 2 1 1 Zr-94 P1 0.011962 +74 2 1 1 Zr-94 P2 0.006220 +75 2 1 1 Zr-94 P3 -0.000627 +76 2 1 1 Zr-96 P0 0.007599 +77 2 1 1 Zr-96 P1 -0.000196 +78 2 1 1 Zr-96 P2 -0.001193 +79 2 1 1 Zr-96 P3 -0.000401 +40 2 1 2 Zr-90 P0 0.000000 +41 2 1 2 Zr-90 P1 0.000000 +42 2 1 2 Zr-90 P2 0.000000 +43 2 1 2 Zr-90 P3 0.000000 +44 2 1 2 Zr-91 P0 0.000000 +45 2 1 2 Zr-91 P1 0.000000 +46 2 1 2 Zr-91 P2 0.000000 +47 2 1 2 Zr-91 P3 0.000000 +48 2 1 2 Zr-92 P0 0.000000 +49 2 1 2 Zr-92 P1 0.000000 +50 2 1 2 Zr-92 P2 0.000000 +51 2 1 2 Zr-92 P3 0.000000 +52 2 1 2 Zr-94 P0 0.000000 +53 2 1 2 Zr-94 P1 0.000000 +54 2 1 2 Zr-94 P2 0.000000 +55 2 1 2 Zr-94 P3 0.000000 +56 2 1 2 Zr-96 P0 0.000000 +57 2 1 2 Zr-96 P1 0.000000 +58 2 1 2 Zr-96 P2 0.000000 +59 2 1 2 Zr-96 P3 0.000000 +20 2 2 1 Zr-90 P0 0.000000 +21 2 2 1 Zr-90 P1 0.000000 +22 2 2 1 Zr-90 P2 0.000000 +23 2 2 1 Zr-90 P3 0.000000 +24 2 2 1 Zr-91 P0 0.000000 +25 2 2 1 Zr-91 P1 0.000000 +26 2 2 1 Zr-91 P2 0.000000 +27 2 2 1 Zr-91 P3 0.000000 +28 2 2 1 Zr-92 P0 0.000000 +29 2 2 1 Zr-92 P1 0.000000 +30 2 2 1 Zr-92 P2 0.000000 +31 2 2 1 Zr-92 P3 0.000000 +32 2 2 1 Zr-94 P0 0.000000 +33 2 2 1 Zr-94 P1 0.000000 +34 2 2 1 Zr-94 P2 0.000000 +35 2 2 1 Zr-94 P3 0.000000 +36 2 2 1 Zr-96 P0 0.000000 +37 2 2 1 Zr-96 P1 0.000000 +38 2 2 1 Zr-96 P2 0.000000 +39 2 2 1 Zr-96 P3 0.000000 +0 2 2 2 Zr-90 P0 0.119570 +1 2 2 2 Zr-90 P1 -0.002117 +2 2 2 2 Zr-90 P2 -0.015144 +3 2 2 2 Zr-90 P3 0.000965 +4 2 2 2 Zr-91 P0 0.054803 +5 2 2 2 Zr-91 P1 -0.006989 +6 2 2 2 Zr-91 P2 -0.010542 +7 2 2 2 Zr-91 P3 -0.001260 +8 2 2 2 Zr-92 P0 0.034875 +9 2 2 2 Zr-92 P1 -0.006759 +10 2 2 2 Zr-92 P2 0.008972 +11 2 2 2 Zr-92 P3 0.009834 +12 2 2 2 Zr-94 P0 0.054803 +13 2 2 2 Zr-94 P1 -0.006015 +14 2 2 2 Zr-94 P2 0.001420 +15 2 2 2 Zr-94 P3 0.004494 +16 2 2 2 Zr-96 P0 0.000000 +17 2 2 2 Zr-96 P1 0.000000 +18 2 2 2 Zr-96 P2 0.000000 +19 2 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. +5 2 1 Zr-90 0 0 +6 2 1 Zr-91 0 0 +7 2 1 Zr-92 0 0 +8 2 1 Zr-94 0 0 +9 2 1 Zr-96 0 0 +0 2 2 Zr-90 0 0 +1 2 2 Zr-91 0 0 +2 2 2 Zr-92 0 0 +3 2 2 Zr-94 0 0 +4 2 2 Zr-96 0 0 material group in nuclide mean std. dev. 4 3 1 H-1 0.207103 0.023028 5 3 1 O-16 0.079282 0.005197 6 3 1 B-10 0.000521 0.000244 @@ -397,38 +865,86 @@ 1 3 2 O-16 0.085363 0.014001 2 3 2 B-10 0.049249 0.008232 3 3 2 B-11 0.000195 0.001527 material group in nuclide mean std. dev. -4 3 1 H-1 0.0 0.0 -5 3 1 O-16 0.0 0.0 -6 3 1 B-10 0.0 0.0 -7 3 1 B-11 0.0 0.0 -0 3 2 H-1 0.0 0.0 -1 3 2 O-16 0.0 0.0 -2 3 2 B-10 0.0 0.0 -3 3 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. -12 3 1 1 H-1 0.181306 0.022102 -13 3 1 1 O-16 0.078631 0.005044 -14 3 1 1 B-10 0.000000 0.000000 -15 3 1 1 B-11 0.000000 0.000000 -8 3 1 2 H-1 0.025666 0.001582 -9 3 1 2 O-16 0.000521 0.000131 -10 3 1 2 B-10 0.000000 0.000000 -11 3 1 2 B-11 0.000000 0.000000 -4 3 2 1 H-1 0.000000 0.000000 -5 3 2 1 O-16 0.000000 0.000000 -6 3 2 1 B-10 0.000000 0.000000 -7 3 2 1 B-11 0.000000 0.000000 -0 3 2 2 H-1 1.273963 0.250623 -1 3 2 2 O-16 0.085363 0.014001 -2 3 2 2 B-10 0.000000 0.000000 -3 3 2 2 B-11 0.000195 0.001527 material group out nuclide mean std. dev. -4 3 1 H-1 0.0 0.0 -5 3 1 O-16 0.0 0.0 -6 3 1 B-10 0.0 0.0 -7 3 1 B-11 0.0 0.0 -0 3 2 H-1 0.0 0.0 -1 3 2 O-16 0.0 0.0 -2 3 2 B-10 0.0 0.0 -3 3 2 B-11 0.0 0.0 material group in nuclide mean std. dev. +4 3 1 H-1 0 0 +5 3 1 O-16 0 0 +6 3 1 B-10 0 0 +7 3 1 B-11 0 0 +0 3 2 H-1 0 0 +1 3 2 O-16 0 0 +2 3 2 B-10 0 0 +3 3 2 B-11 0 0 material group in group out nuclide moment mean +48 3 1 1 H-1 P0 0.560615 +49 3 1 1 H-1 P1 0.379309 +50 3 1 1 H-1 P2 0.149073 +51 3 1 1 H-1 P3 0.005293 +52 3 1 1 O-16 P0 0.082731 +53 3 1 1 O-16 P1 0.004100 +54 3 1 1 O-16 P2 0.003113 +55 3 1 1 O-16 P3 -0.002256 +56 3 1 1 B-10 P0 0.000000 +57 3 1 1 B-10 P1 0.000000 +58 3 1 1 B-10 P2 0.000000 +59 3 1 1 B-10 P3 0.000000 +60 3 1 1 B-11 P0 0.000000 +61 3 1 1 B-11 P1 0.000000 +62 3 1 1 B-11 P2 0.000000 +63 3 1 1 B-11 P3 0.000000 +32 3 1 2 H-1 P0 0.025666 +33 3 1 2 H-1 P1 0.007631 +34 3 1 2 H-1 P2 -0.002692 +35 3 1 2 H-1 P3 -0.002928 +36 3 1 2 O-16 P0 0.000521 +37 3 1 2 O-16 P1 -0.000268 +38 3 1 2 O-16 P2 -0.000046 +39 3 1 2 O-16 P3 0.000208 +40 3 1 2 B-10 P0 0.000000 +41 3 1 2 B-10 P1 0.000000 +42 3 1 2 B-10 P2 0.000000 +43 3 1 2 B-10 P3 0.000000 +44 3 1 2 B-11 P0 0.000000 +45 3 1 2 B-11 P1 0.000000 +46 3 1 2 B-11 P2 0.000000 +47 3 1 2 B-11 P3 0.000000 +16 3 2 1 H-1 P0 0.000000 +17 3 2 1 H-1 P1 0.000000 +18 3 2 1 H-1 P2 0.000000 +19 3 2 1 H-1 P3 0.000000 +20 3 2 1 O-16 P0 0.000000 +21 3 2 1 O-16 P1 0.000000 +22 3 2 1 O-16 P2 0.000000 +23 3 2 1 O-16 P3 0.000000 +24 3 2 1 B-10 P0 0.000000 +25 3 2 1 B-10 P1 0.000000 +26 3 2 1 B-10 P2 0.000000 +27 3 2 1 B-10 P3 0.000000 +28 3 2 1 B-11 P0 0.000000 +29 3 2 1 B-11 P1 0.000000 +30 3 2 1 B-11 P2 0.000000 +31 3 2 1 B-11 P3 0.000000 +0 3 2 2 H-1 P0 1.840960 +1 3 2 2 H-1 P1 0.498320 +2 3 2 2 H-1 P2 0.083870 +3 3 2 2 H-1 P3 0.013597 +4 3 2 2 O-16 P0 0.082081 +5 3 2 2 O-16 P1 -0.000867 +6 3 2 2 O-16 P2 0.006697 +7 3 2 2 O-16 P3 0.003223 +8 3 2 2 B-10 P0 0.000000 +9 3 2 2 B-10 P1 0.000000 +10 3 2 2 B-10 P2 0.000000 +11 3 2 2 B-10 P3 0.000000 +12 3 2 2 B-11 P0 0.001173 +13 3 2 2 B-11 P1 0.000978 +14 3 2 2 B-11 P2 0.000637 +15 3 2 2 B-11 P3 0.000234 material group out nuclide mean std. dev. +4 3 1 H-1 0 0 +5 3 1 O-16 0 0 +6 3 1 B-10 0 0 +7 3 1 B-11 0 0 +0 3 2 H-1 0 0 +1 3 2 O-16 0 0 +2 3 2 B-10 0 0 +3 3 2 B-11 0 0 material group in nuclide mean std. dev. 4 4 1 H-1 0.175242 0.053715 5 4 1 O-16 0.066545 0.010083 6 4 1 B-10 0.000570 0.000352 @@ -437,938 +953,2066 @@ 1 4 2 O-16 0.085141 0.028073 2 4 2 B-10 0.025923 0.007276 3 4 2 B-11 0.000000 0.000000 material group in nuclide mean std. dev. -4 4 1 H-1 0.0 0.0 -5 4 1 O-16 0.0 0.0 -6 4 1 B-10 0.0 0.0 -7 4 1 B-11 0.0 0.0 -0 4 2 H-1 0.0 0.0 -1 4 2 O-16 0.0 0.0 -2 4 2 B-10 0.0 0.0 -3 4 2 B-11 0.0 0.0 material group in group out nuclide mean std. dev. -12 4 1 1 H-1 0.151295 0.051491 -13 4 1 1 O-16 0.066545 0.010083 -14 4 1 1 B-10 0.000000 0.000000 -15 4 1 1 B-11 0.000089 0.000346 -8 4 1 2 H-1 0.023662 0.003083 -9 4 1 2 O-16 0.000000 0.000000 -10 4 1 2 B-10 0.000000 0.000000 -11 4 1 2 B-11 0.000000 0.000000 -4 4 2 1 H-1 0.000000 0.000000 -5 4 2 1 O-16 0.000000 0.000000 -6 4 2 1 B-10 0.000000 0.000000 -7 4 2 1 B-11 0.000000 0.000000 -0 4 2 2 H-1 1.129933 0.361681 -1 4 2 2 O-16 0.085141 0.028073 -2 4 2 2 B-10 0.000000 0.000000 -3 4 2 2 B-11 0.000000 0.000000 material group out nuclide mean std. dev. -4 4 1 H-1 0.0 0.0 -5 4 1 O-16 0.0 0.0 -6 4 1 B-10 0.0 0.0 -7 4 1 B-11 0.0 0.0 -0 4 2 H-1 0.0 0.0 -1 4 2 O-16 0.0 0.0 -2 4 2 B-10 0.0 0.0 -3 4 2 B-11 0.0 0.0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in group out nuclide mean std. dev. -81 5 1 1 Fe-54 0.0 0.0 -82 5 1 1 Fe-56 0.0 0.0 -83 5 1 1 Fe-57 0.0 0.0 -84 5 1 1 Fe-58 0.0 0.0 -85 5 1 1 Ni-58 0.0 0.0 -86 5 1 1 Ni-60 0.0 0.0 -87 5 1 1 Ni-61 0.0 0.0 -88 5 1 1 Ni-62 0.0 0.0 -89 5 1 1 Ni-64 0.0 0.0 -90 5 1 1 Mn-55 0.0 0.0 -91 5 1 1 Mo-92 0.0 0.0 -92 5 1 1 Mo-94 0.0 0.0 -93 5 1 1 Mo-95 0.0 0.0 -94 5 1 1 Mo-96 0.0 0.0 -95 5 1 1 Mo-97 0.0 0.0 -96 5 1 1 Mo-98 0.0 0.0 -97 5 1 1 Mo-100 0.0 0.0 -98 5 1 1 Si-28 0.0 0.0 -99 5 1 1 Si-29 0.0 0.0 -100 5 1 1 Si-30 0.0 0.0 -101 5 1 1 Cr-50 0.0 0.0 -102 5 1 1 Cr-52 0.0 0.0 -103 5 1 1 Cr-53 0.0 0.0 -104 5 1 1 Cr-54 0.0 0.0 -105 5 1 1 C-Nat 0.0 0.0 -106 5 1 1 Cu-63 0.0 0.0 -107 5 1 1 Cu-65 0.0 0.0 -54 5 1 2 Fe-54 0.0 0.0 -55 5 1 2 Fe-56 0.0 0.0 -56 5 1 2 Fe-57 0.0 0.0 -57 5 1 2 Fe-58 0.0 0.0 -58 5 1 2 Ni-58 0.0 0.0 -59 5 1 2 Ni-60 0.0 0.0 -60 5 1 2 Ni-61 0.0 0.0 -61 5 1 2 Ni-62 0.0 0.0 -62 5 1 2 Ni-64 0.0 0.0 -63 5 1 2 Mn-55 0.0 0.0 -64 5 1 2 Mo-92 0.0 0.0 -65 5 1 2 Mo-94 0.0 0.0 -66 5 1 2 Mo-95 0.0 0.0 -67 5 1 2 Mo-96 0.0 0.0 -68 5 1 2 Mo-97 0.0 0.0 -69 5 1 2 Mo-98 0.0 0.0 -70 5 1 2 Mo-100 0.0 0.0 -71 5 1 2 Si-28 0.0 0.0 -72 5 1 2 Si-29 0.0 0.0 -73 5 1 2 Si-30 0.0 0.0 -74 5 1 2 Cr-50 0.0 0.0 -75 5 1 2 Cr-52 0.0 0.0 -76 5 1 2 Cr-53 0.0 0.0 -77 5 1 2 Cr-54 0.0 0.0 -78 5 1 2 C-Nat 0.0 0.0 -79 5 1 2 Cu-63 0.0 0.0 -80 5 1 2 Cu-65 0.0 0.0 -27 5 2 1 Fe-54 0.0 0.0 -28 5 2 1 Fe-56 0.0 0.0 -29 5 2 1 Fe-57 0.0 0.0 -30 5 2 1 Fe-58 0.0 0.0 -31 5 2 1 Ni-58 0.0 0.0 -32 5 2 1 Ni-60 0.0 0.0 -33 5 2 1 Ni-61 0.0 0.0 -34 5 2 1 Ni-62 0.0 0.0 -35 5 2 1 Ni-64 0.0 0.0 -36 5 2 1 Mn-55 0.0 0.0 -37 5 2 1 Mo-92 0.0 0.0 -38 5 2 1 Mo-94 0.0 0.0 -39 5 2 1 Mo-95 0.0 0.0 -40 5 2 1 Mo-96 0.0 0.0 -41 5 2 1 Mo-97 0.0 0.0 -42 5 2 1 Mo-98 0.0 0.0 -43 5 2 1 Mo-100 0.0 0.0 -44 5 2 1 Si-28 0.0 0.0 -45 5 2 1 Si-29 0.0 0.0 -46 5 2 1 Si-30 0.0 0.0 -47 5 2 1 Cr-50 0.0 0.0 -48 5 2 1 Cr-52 0.0 0.0 -49 5 2 1 Cr-53 0.0 0.0 -50 5 2 1 Cr-54 0.0 0.0 -51 5 2 1 C-Nat 0.0 0.0 -52 5 2 1 Cu-63 0.0 0.0 -53 5 2 1 Cu-65 0.0 0.0 -0 5 2 2 Fe-54 0.0 0.0 -1 5 2 2 Fe-56 0.0 0.0 -2 5 2 2 Fe-57 0.0 0.0 -3 5 2 2 Fe-58 0.0 0.0 -4 5 2 2 Ni-58 0.0 0.0 -5 5 2 2 Ni-60 0.0 0.0 -6 5 2 2 Ni-61 0.0 0.0 -7 5 2 2 Ni-62 0.0 0.0 -8 5 2 2 Ni-64 0.0 0.0 -9 5 2 2 Mn-55 0.0 0.0 -10 5 2 2 Mo-92 0.0 0.0 -11 5 2 2 Mo-94 0.0 0.0 -12 5 2 2 Mo-95 0.0 0.0 -13 5 2 2 Mo-96 0.0 0.0 -14 5 2 2 Mo-97 0.0 0.0 -15 5 2 2 Mo-98 0.0 0.0 -16 5 2 2 Mo-100 0.0 0.0 -17 5 2 2 Si-28 0.0 0.0 -18 5 2 2 Si-29 0.0 0.0 -19 5 2 2 Si-30 0.0 0.0 -20 5 2 2 Cr-50 0.0 0.0 -21 5 2 2 Cr-52 0.0 0.0 -22 5 2 2 Cr-53 0.0 0.0 -23 5 2 2 Cr-54 0.0 0.0 -24 5 2 2 C-Nat 0.0 0.0 -25 5 2 2 Cu-63 0.0 0.0 -26 5 2 2 Cu-65 0.0 0.0 material group out nuclide mean std. dev. -27 5 1 Fe-54 0.0 0.0 -28 5 1 Fe-56 0.0 0.0 -29 5 1 Fe-57 0.0 0.0 -30 5 1 Fe-58 0.0 0.0 -31 5 1 Ni-58 0.0 0.0 -32 5 1 Ni-60 0.0 0.0 -33 5 1 Ni-61 0.0 0.0 -34 5 1 Ni-62 0.0 0.0 -35 5 1 Ni-64 0.0 0.0 -36 5 1 Mn-55 0.0 0.0 -37 5 1 Mo-92 0.0 0.0 -38 5 1 Mo-94 0.0 0.0 -39 5 1 Mo-95 0.0 0.0 -40 5 1 Mo-96 0.0 0.0 -41 5 1 Mo-97 0.0 0.0 -42 5 1 Mo-98 0.0 0.0 -43 5 1 Mo-100 0.0 0.0 -44 5 1 Si-28 0.0 0.0 -45 5 1 Si-29 0.0 0.0 -46 5 1 Si-30 0.0 0.0 -47 5 1 Cr-50 0.0 0.0 -48 5 1 Cr-52 0.0 0.0 -49 5 1 Cr-53 0.0 0.0 -50 5 1 Cr-54 0.0 0.0 -51 5 1 C-Nat 0.0 0.0 -52 5 1 Cu-63 0.0 0.0 -53 5 1 Cu-65 0.0 0.0 -0 5 2 Fe-54 0.0 0.0 -1 5 2 Fe-56 0.0 0.0 -2 5 2 Fe-57 0.0 0.0 -3 5 2 Fe-58 0.0 0.0 -4 5 2 Ni-58 0.0 0.0 -5 5 2 Ni-60 0.0 0.0 -6 5 2 Ni-61 0.0 0.0 -7 5 2 Ni-62 0.0 0.0 -8 5 2 Ni-64 0.0 0.0 -9 5 2 Mn-55 0.0 0.0 -10 5 2 Mo-92 0.0 0.0 -11 5 2 Mo-94 0.0 0.0 -12 5 2 Mo-95 0.0 0.0 -13 5 2 Mo-96 0.0 0.0 -14 5 2 Mo-97 0.0 0.0 -15 5 2 Mo-98 0.0 0.0 -16 5 2 Mo-100 0.0 0.0 -17 5 2 Si-28 0.0 0.0 -18 5 2 Si-29 0.0 0.0 -19 5 2 Si-30 0.0 0.0 -20 5 2 Cr-50 0.0 0.0 -21 5 2 Cr-52 0.0 0.0 -22 5 2 Cr-53 0.0 0.0 -23 5 2 Cr-54 0.0 0.0 -24 5 2 C-Nat 0.0 0.0 -25 5 2 Cu-63 0.0 0.0 -26 5 2 Cu-65 0.0 0.0 material group in nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 6 1 1 H-1 0.0 0.0 -64 6 1 1 O-16 0.0 0.0 -65 6 1 1 B-10 0.0 0.0 -66 6 1 1 B-11 0.0 0.0 -67 6 1 1 Fe-54 0.0 0.0 -68 6 1 1 Fe-56 0.0 0.0 -69 6 1 1 Fe-57 0.0 0.0 -70 6 1 1 Fe-58 0.0 0.0 -71 6 1 1 Ni-58 0.0 0.0 -72 6 1 1 Ni-60 0.0 0.0 -73 6 1 1 Ni-61 0.0 0.0 -74 6 1 1 Ni-62 0.0 0.0 -75 6 1 1 Ni-64 0.0 0.0 -76 6 1 1 Mn-55 0.0 0.0 -77 6 1 1 Si-28 0.0 0.0 -78 6 1 1 Si-29 0.0 0.0 -79 6 1 1 Si-30 0.0 0.0 -80 6 1 1 Cr-50 0.0 0.0 -81 6 1 1 Cr-52 0.0 0.0 -82 6 1 1 Cr-53 0.0 0.0 -83 6 1 1 Cr-54 0.0 0.0 -42 6 1 2 H-1 0.0 0.0 -43 6 1 2 O-16 0.0 0.0 -44 6 1 2 B-10 0.0 0.0 -45 6 1 2 B-11 0.0 0.0 -46 6 1 2 Fe-54 0.0 0.0 -47 6 1 2 Fe-56 0.0 0.0 -48 6 1 2 Fe-57 0.0 0.0 -49 6 1 2 Fe-58 0.0 0.0 -50 6 1 2 Ni-58 0.0 0.0 -51 6 1 2 Ni-60 0.0 0.0 -52 6 1 2 Ni-61 0.0 0.0 -53 6 1 2 Ni-62 0.0 0.0 -54 6 1 2 Ni-64 0.0 0.0 -55 6 1 2 Mn-55 0.0 0.0 -56 6 1 2 Si-28 0.0 0.0 -57 6 1 2 Si-29 0.0 0.0 -58 6 1 2 Si-30 0.0 0.0 -59 6 1 2 Cr-50 0.0 0.0 -60 6 1 2 Cr-52 0.0 0.0 -61 6 1 2 Cr-53 0.0 0.0 -62 6 1 2 Cr-54 0.0 0.0 -21 6 2 1 H-1 0.0 0.0 -22 6 2 1 O-16 0.0 0.0 -23 6 2 1 B-10 0.0 0.0 -24 6 2 1 B-11 0.0 0.0 -25 6 2 1 Fe-54 0.0 0.0 -26 6 2 1 Fe-56 0.0 0.0 -27 6 2 1 Fe-57 0.0 0.0 -28 6 2 1 Fe-58 0.0 0.0 -29 6 2 1 Ni-58 0.0 0.0 -30 6 2 1 Ni-60 0.0 0.0 -31 6 2 1 Ni-61 0.0 0.0 -32 6 2 1 Ni-62 0.0 0.0 -33 6 2 1 Ni-64 0.0 0.0 -34 6 2 1 Mn-55 0.0 0.0 -35 6 2 1 Si-28 0.0 0.0 -36 6 2 1 Si-29 0.0 0.0 -37 6 2 1 Si-30 0.0 0.0 -38 6 2 1 Cr-50 0.0 0.0 -39 6 2 1 Cr-52 0.0 0.0 -40 6 2 1 Cr-53 0.0 0.0 -41 6 2 1 Cr-54 0.0 0.0 -0 6 2 2 H-1 0.0 0.0 -1 6 2 2 O-16 0.0 0.0 -2 6 2 2 B-10 0.0 0.0 -3 6 2 2 B-11 0.0 0.0 -4 6 2 2 Fe-54 0.0 0.0 -5 6 2 2 Fe-56 0.0 0.0 -6 6 2 2 Fe-57 0.0 0.0 -7 6 2 2 Fe-58 0.0 0.0 -8 6 2 2 Ni-58 0.0 0.0 -9 6 2 2 Ni-60 0.0 0.0 -10 6 2 2 Ni-61 0.0 0.0 -11 6 2 2 Ni-62 0.0 0.0 -12 6 2 2 Ni-64 0.0 0.0 -13 6 2 2 Mn-55 0.0 0.0 -14 6 2 2 Si-28 0.0 0.0 -15 6 2 2 Si-29 0.0 0.0 -16 6 2 2 Si-30 0.0 0.0 -17 6 2 2 Cr-50 0.0 0.0 -18 6 2 2 Cr-52 0.0 0.0 -19 6 2 2 Cr-53 0.0 0.0 -20 6 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 6 1 H-1 0.0 0.0 -22 6 1 O-16 0.0 0.0 -23 6 1 B-10 0.0 0.0 -24 6 1 B-11 0.0 0.0 -25 6 1 Fe-54 0.0 0.0 -26 6 1 Fe-56 0.0 0.0 -27 6 1 Fe-57 0.0 0.0 -28 6 1 Fe-58 0.0 0.0 -29 6 1 Ni-58 0.0 0.0 -30 6 1 Ni-60 0.0 0.0 -31 6 1 Ni-61 0.0 0.0 -32 6 1 Ni-62 0.0 0.0 -33 6 1 Ni-64 0.0 0.0 -34 6 1 Mn-55 0.0 0.0 -35 6 1 Si-28 0.0 0.0 -36 6 1 Si-29 0.0 0.0 -37 6 1 Si-30 0.0 0.0 -38 6 1 Cr-50 0.0 0.0 -39 6 1 Cr-52 0.0 0.0 -40 6 1 Cr-53 0.0 0.0 -41 6 1 Cr-54 0.0 0.0 -0 6 2 H-1 0.0 0.0 -1 6 2 O-16 0.0 0.0 -2 6 2 B-10 0.0 0.0 -3 6 2 B-11 0.0 0.0 -4 6 2 Fe-54 0.0 0.0 -5 6 2 Fe-56 0.0 0.0 -6 6 2 Fe-57 0.0 0.0 -7 6 2 Fe-58 0.0 0.0 -8 6 2 Ni-58 0.0 0.0 -9 6 2 Ni-60 0.0 0.0 -10 6 2 Ni-61 0.0 0.0 -11 6 2 Ni-62 0.0 0.0 -12 6 2 Ni-64 0.0 0.0 -13 6 2 Mn-55 0.0 0.0 -14 6 2 Si-28 0.0 0.0 -15 6 2 Si-29 0.0 0.0 -16 6 2 Si-30 0.0 0.0 -17 6 2 Cr-50 0.0 0.0 -18 6 2 Cr-52 0.0 0.0 -19 6 2 Cr-53 0.0 0.0 -20 6 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 7 1 1 H-1 0.0 0.0 -64 7 1 1 O-16 0.0 0.0 -65 7 1 1 B-10 0.0 0.0 -66 7 1 1 B-11 0.0 0.0 -67 7 1 1 Fe-54 0.0 0.0 -68 7 1 1 Fe-56 0.0 0.0 -69 7 1 1 Fe-57 0.0 0.0 -70 7 1 1 Fe-58 0.0 0.0 -71 7 1 1 Ni-58 0.0 0.0 -72 7 1 1 Ni-60 0.0 0.0 -73 7 1 1 Ni-61 0.0 0.0 -74 7 1 1 Ni-62 0.0 0.0 -75 7 1 1 Ni-64 0.0 0.0 -76 7 1 1 Mn-55 0.0 0.0 -77 7 1 1 Si-28 0.0 0.0 -78 7 1 1 Si-29 0.0 0.0 -79 7 1 1 Si-30 0.0 0.0 -80 7 1 1 Cr-50 0.0 0.0 -81 7 1 1 Cr-52 0.0 0.0 -82 7 1 1 Cr-53 0.0 0.0 -83 7 1 1 Cr-54 0.0 0.0 -42 7 1 2 H-1 0.0 0.0 -43 7 1 2 O-16 0.0 0.0 -44 7 1 2 B-10 0.0 0.0 -45 7 1 2 B-11 0.0 0.0 -46 7 1 2 Fe-54 0.0 0.0 -47 7 1 2 Fe-56 0.0 0.0 -48 7 1 2 Fe-57 0.0 0.0 -49 7 1 2 Fe-58 0.0 0.0 -50 7 1 2 Ni-58 0.0 0.0 -51 7 1 2 Ni-60 0.0 0.0 -52 7 1 2 Ni-61 0.0 0.0 -53 7 1 2 Ni-62 0.0 0.0 -54 7 1 2 Ni-64 0.0 0.0 -55 7 1 2 Mn-55 0.0 0.0 -56 7 1 2 Si-28 0.0 0.0 -57 7 1 2 Si-29 0.0 0.0 -58 7 1 2 Si-30 0.0 0.0 -59 7 1 2 Cr-50 0.0 0.0 -60 7 1 2 Cr-52 0.0 0.0 -61 7 1 2 Cr-53 0.0 0.0 -62 7 1 2 Cr-54 0.0 0.0 -21 7 2 1 H-1 0.0 0.0 -22 7 2 1 O-16 0.0 0.0 -23 7 2 1 B-10 0.0 0.0 -24 7 2 1 B-11 0.0 0.0 -25 7 2 1 Fe-54 0.0 0.0 -26 7 2 1 Fe-56 0.0 0.0 -27 7 2 1 Fe-57 0.0 0.0 -28 7 2 1 Fe-58 0.0 0.0 -29 7 2 1 Ni-58 0.0 0.0 -30 7 2 1 Ni-60 0.0 0.0 -31 7 2 1 Ni-61 0.0 0.0 -32 7 2 1 Ni-62 0.0 0.0 -33 7 2 1 Ni-64 0.0 0.0 -34 7 2 1 Mn-55 0.0 0.0 -35 7 2 1 Si-28 0.0 0.0 -36 7 2 1 Si-29 0.0 0.0 -37 7 2 1 Si-30 0.0 0.0 -38 7 2 1 Cr-50 0.0 0.0 -39 7 2 1 Cr-52 0.0 0.0 -40 7 2 1 Cr-53 0.0 0.0 -41 7 2 1 Cr-54 0.0 0.0 -0 7 2 2 H-1 0.0 0.0 -1 7 2 2 O-16 0.0 0.0 -2 7 2 2 B-10 0.0 0.0 -3 7 2 2 B-11 0.0 0.0 -4 7 2 2 Fe-54 0.0 0.0 -5 7 2 2 Fe-56 0.0 0.0 -6 7 2 2 Fe-57 0.0 0.0 -7 7 2 2 Fe-58 0.0 0.0 -8 7 2 2 Ni-58 0.0 0.0 -9 7 2 2 Ni-60 0.0 0.0 -10 7 2 2 Ni-61 0.0 0.0 -11 7 2 2 Ni-62 0.0 0.0 -12 7 2 2 Ni-64 0.0 0.0 -13 7 2 2 Mn-55 0.0 0.0 -14 7 2 2 Si-28 0.0 0.0 -15 7 2 2 Si-29 0.0 0.0 -16 7 2 2 Si-30 0.0 0.0 -17 7 2 2 Cr-50 0.0 0.0 -18 7 2 2 Cr-52 0.0 0.0 -19 7 2 2 Cr-53 0.0 0.0 -20 7 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 7 1 H-1 0.0 0.0 -22 7 1 O-16 0.0 0.0 -23 7 1 B-10 0.0 0.0 -24 7 1 B-11 0.0 0.0 -25 7 1 Fe-54 0.0 0.0 -26 7 1 Fe-56 0.0 0.0 -27 7 1 Fe-57 0.0 0.0 -28 7 1 Fe-58 0.0 0.0 -29 7 1 Ni-58 0.0 0.0 -30 7 1 Ni-60 0.0 0.0 -31 7 1 Ni-61 0.0 0.0 -32 7 1 Ni-62 0.0 0.0 -33 7 1 Ni-64 0.0 0.0 -34 7 1 Mn-55 0.0 0.0 -35 7 1 Si-28 0.0 0.0 -36 7 1 Si-29 0.0 0.0 -37 7 1 Si-30 0.0 0.0 -38 7 1 Cr-50 0.0 0.0 -39 7 1 Cr-52 0.0 0.0 -40 7 1 Cr-53 0.0 0.0 -41 7 1 Cr-54 0.0 0.0 -0 7 2 H-1 0.0 0.0 -1 7 2 O-16 0.0 0.0 -2 7 2 B-10 0.0 0.0 -3 7 2 B-11 0.0 0.0 -4 7 2 Fe-54 0.0 0.0 -5 7 2 Fe-56 0.0 0.0 -6 7 2 Fe-57 0.0 0.0 -7 7 2 Fe-58 0.0 0.0 -8 7 2 Ni-58 0.0 0.0 -9 7 2 Ni-60 0.0 0.0 -10 7 2 Ni-61 0.0 0.0 -11 7 2 Ni-62 0.0 0.0 -12 7 2 Ni-64 0.0 0.0 -13 7 2 Mn-55 0.0 0.0 -14 7 2 Si-28 0.0 0.0 -15 7 2 Si-29 0.0 0.0 -16 7 2 Si-30 0.0 0.0 -17 7 2 Cr-50 0.0 0.0 -18 7 2 Cr-52 0.0 0.0 -19 7 2 Cr-53 0.0 0.0 -20 7 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 8 1 1 H-1 0.0 0.0 -64 8 1 1 O-16 0.0 0.0 -65 8 1 1 B-10 0.0 0.0 -66 8 1 1 B-11 0.0 0.0 -67 8 1 1 Fe-54 0.0 0.0 -68 8 1 1 Fe-56 0.0 0.0 -69 8 1 1 Fe-57 0.0 0.0 -70 8 1 1 Fe-58 0.0 0.0 -71 8 1 1 Ni-58 0.0 0.0 -72 8 1 1 Ni-60 0.0 0.0 -73 8 1 1 Ni-61 0.0 0.0 -74 8 1 1 Ni-62 0.0 0.0 -75 8 1 1 Ni-64 0.0 0.0 -76 8 1 1 Mn-55 0.0 0.0 -77 8 1 1 Si-28 0.0 0.0 -78 8 1 1 Si-29 0.0 0.0 -79 8 1 1 Si-30 0.0 0.0 -80 8 1 1 Cr-50 0.0 0.0 -81 8 1 1 Cr-52 0.0 0.0 -82 8 1 1 Cr-53 0.0 0.0 -83 8 1 1 Cr-54 0.0 0.0 -42 8 1 2 H-1 0.0 0.0 -43 8 1 2 O-16 0.0 0.0 -44 8 1 2 B-10 0.0 0.0 -45 8 1 2 B-11 0.0 0.0 -46 8 1 2 Fe-54 0.0 0.0 -47 8 1 2 Fe-56 0.0 0.0 -48 8 1 2 Fe-57 0.0 0.0 -49 8 1 2 Fe-58 0.0 0.0 -50 8 1 2 Ni-58 0.0 0.0 -51 8 1 2 Ni-60 0.0 0.0 -52 8 1 2 Ni-61 0.0 0.0 -53 8 1 2 Ni-62 0.0 0.0 -54 8 1 2 Ni-64 0.0 0.0 -55 8 1 2 Mn-55 0.0 0.0 -56 8 1 2 Si-28 0.0 0.0 -57 8 1 2 Si-29 0.0 0.0 -58 8 1 2 Si-30 0.0 0.0 -59 8 1 2 Cr-50 0.0 0.0 -60 8 1 2 Cr-52 0.0 0.0 -61 8 1 2 Cr-53 0.0 0.0 -62 8 1 2 Cr-54 0.0 0.0 -21 8 2 1 H-1 0.0 0.0 -22 8 2 1 O-16 0.0 0.0 -23 8 2 1 B-10 0.0 0.0 -24 8 2 1 B-11 0.0 0.0 -25 8 2 1 Fe-54 0.0 0.0 -26 8 2 1 Fe-56 0.0 0.0 -27 8 2 1 Fe-57 0.0 0.0 -28 8 2 1 Fe-58 0.0 0.0 -29 8 2 1 Ni-58 0.0 0.0 -30 8 2 1 Ni-60 0.0 0.0 -31 8 2 1 Ni-61 0.0 0.0 -32 8 2 1 Ni-62 0.0 0.0 -33 8 2 1 Ni-64 0.0 0.0 -34 8 2 1 Mn-55 0.0 0.0 -35 8 2 1 Si-28 0.0 0.0 -36 8 2 1 Si-29 0.0 0.0 -37 8 2 1 Si-30 0.0 0.0 -38 8 2 1 Cr-50 0.0 0.0 -39 8 2 1 Cr-52 0.0 0.0 -40 8 2 1 Cr-53 0.0 0.0 -41 8 2 1 Cr-54 0.0 0.0 -0 8 2 2 H-1 0.0 0.0 -1 8 2 2 O-16 0.0 0.0 -2 8 2 2 B-10 0.0 0.0 -3 8 2 2 B-11 0.0 0.0 -4 8 2 2 Fe-54 0.0 0.0 -5 8 2 2 Fe-56 0.0 0.0 -6 8 2 2 Fe-57 0.0 0.0 -7 8 2 2 Fe-58 0.0 0.0 -8 8 2 2 Ni-58 0.0 0.0 -9 8 2 2 Ni-60 0.0 0.0 -10 8 2 2 Ni-61 0.0 0.0 -11 8 2 2 Ni-62 0.0 0.0 -12 8 2 2 Ni-64 0.0 0.0 -13 8 2 2 Mn-55 0.0 0.0 -14 8 2 2 Si-28 0.0 0.0 -15 8 2 2 Si-29 0.0 0.0 -16 8 2 2 Si-30 0.0 0.0 -17 8 2 2 Cr-50 0.0 0.0 -18 8 2 2 Cr-52 0.0 0.0 -19 8 2 2 Cr-53 0.0 0.0 -20 8 2 2 Cr-54 0.0 0.0 material group out nuclide mean std. dev. -21 8 1 H-1 0.0 0.0 -22 8 1 O-16 0.0 0.0 -23 8 1 B-10 0.0 0.0 -24 8 1 B-11 0.0 0.0 -25 8 1 Fe-54 0.0 0.0 -26 8 1 Fe-56 0.0 0.0 -27 8 1 Fe-57 0.0 0.0 -28 8 1 Fe-58 0.0 0.0 -29 8 1 Ni-58 0.0 0.0 -30 8 1 Ni-60 0.0 0.0 -31 8 1 Ni-61 0.0 0.0 -32 8 1 Ni-62 0.0 0.0 -33 8 1 Ni-64 0.0 0.0 -34 8 1 Mn-55 0.0 0.0 -35 8 1 Si-28 0.0 0.0 -36 8 1 Si-29 0.0 0.0 -37 8 1 Si-30 0.0 0.0 -38 8 1 Cr-50 0.0 0.0 -39 8 1 Cr-52 0.0 0.0 -40 8 1 Cr-53 0.0 0.0 -41 8 1 Cr-54 0.0 0.0 -0 8 2 H-1 0.0 0.0 -1 8 2 O-16 0.0 0.0 -2 8 2 B-10 0.0 0.0 -3 8 2 B-11 0.0 0.0 -4 8 2 Fe-54 0.0 0.0 -5 8 2 Fe-56 0.0 0.0 -6 8 2 Fe-57 0.0 0.0 -7 8 2 Fe-58 0.0 0.0 -8 8 2 Ni-58 0.0 0.0 -9 8 2 Ni-60 0.0 0.0 -10 8 2 Ni-61 0.0 0.0 -11 8 2 Ni-62 0.0 0.0 -12 8 2 Ni-64 0.0 0.0 -13 8 2 Mn-55 0.0 0.0 -14 8 2 Si-28 0.0 0.0 -15 8 2 Si-29 0.0 0.0 -16 8 2 Si-30 0.0 0.0 -17 8 2 Cr-50 0.0 0.0 -18 8 2 Cr-52 0.0 0.0 -19 8 2 Cr-53 0.0 0.0 -20 8 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +4 4 1 H-1 0 0 +5 4 1 O-16 0 0 +6 4 1 B-10 0 0 +7 4 1 B-11 0 0 +0 4 2 H-1 0 0 +1 4 2 O-16 0 0 +2 4 2 B-10 0 0 +3 4 2 B-11 0 0 material group in group out nuclide moment mean +48 4 1 1 H-1 P0 0.468964 +49 4 1 1 H-1 P1 0.317668 +50 4 1 1 H-1 P2 0.127157 +51 4 1 1 H-1 P3 0.009844 +52 4 1 1 O-16 P0 0.074692 +53 4 1 1 O-16 P1 0.008147 +54 4 1 1 O-16 P2 0.003915 +55 4 1 1 O-16 P3 0.002322 +56 4 1 1 B-10 P0 0.000000 +57 4 1 1 B-10 P1 0.000000 +58 4 1 1 B-10 P2 0.000000 +59 4 1 1 B-10 P3 0.000000 +60 4 1 1 B-11 P0 0.000285 +61 4 1 1 B-11 P1 0.000196 +62 4 1 1 B-11 P2 0.000060 +63 4 1 1 B-11 P3 -0.000062 +32 4 1 2 H-1 P0 0.023662 +33 4 1 2 H-1 P1 0.007526 +34 4 1 2 H-1 P2 -0.002730 +35 4 1 2 H-1 P3 -0.003140 +36 4 1 2 O-16 P0 0.000000 +37 4 1 2 O-16 P1 0.000000 +38 4 1 2 O-16 P2 0.000000 +39 4 1 2 O-16 P3 0.000000 +40 4 1 2 B-10 P0 0.000000 +41 4 1 2 B-10 P1 0.000000 +42 4 1 2 B-10 P2 0.000000 +43 4 1 2 B-10 P3 0.000000 +44 4 1 2 B-11 P0 0.000000 +45 4 1 2 B-11 P1 0.000000 +46 4 1 2 B-11 P2 0.000000 +47 4 1 2 B-11 P3 0.000000 +16 4 2 1 H-1 P0 0.000000 +17 4 2 1 H-1 P1 0.000000 +18 4 2 1 H-1 P2 0.000000 +19 4 2 1 H-1 P3 0.000000 +20 4 2 1 O-16 P0 0.000000 +21 4 2 1 O-16 P1 0.000000 +22 4 2 1 O-16 P2 0.000000 +23 4 2 1 O-16 P3 0.000000 +24 4 2 1 B-10 P0 0.000000 +25 4 2 1 B-10 P1 0.000000 +26 4 2 1 B-10 P2 0.000000 +27 4 2 1 B-10 P3 0.000000 +28 4 2 1 B-11 P0 0.000000 +29 4 2 1 B-11 P1 0.000000 +30 4 2 1 B-11 P2 0.000000 +31 4 2 1 B-11 P3 0.000000 +0 4 2 2 H-1 P0 1.672065 +1 4 2 2 H-1 P1 0.493252 +2 4 2 2 H-1 P2 0.104511 +3 4 2 2 H-1 P3 0.039078 +4 4 2 2 O-16 P0 0.092584 +5 4 2 2 O-16 P1 0.007443 +6 4 2 2 O-16 P2 -0.005485 +7 4 2 2 O-16 P3 -0.006103 +8 4 2 2 B-10 P0 0.000000 +9 4 2 2 B-10 P1 0.000000 +10 4 2 2 B-10 P2 0.000000 +11 4 2 2 B-10 P3 0.000000 +12 4 2 2 B-11 P0 0.000000 +13 4 2 2 B-11 P1 0.000000 +14 4 2 2 B-11 P2 0.000000 +15 4 2 2 B-11 P3 0.000000 material group out nuclide mean std. dev. +4 4 1 H-1 0 0 +5 4 1 O-16 0 0 +6 4 1 B-10 0 0 +7 4 1 B-11 0 0 +0 4 2 H-1 0 0 +1 4 2 O-16 0 0 +2 4 2 B-10 0 0 +3 4 2 B-11 0 0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in group out nuclide moment mean +324 5 1 1 Fe-54 P0 0 +325 5 1 1 Fe-54 P1 0 +326 5 1 1 Fe-54 P2 0 +327 5 1 1 Fe-54 P3 0 +328 5 1 1 Fe-56 P0 0 +329 5 1 1 Fe-56 P1 0 +330 5 1 1 Fe-56 P2 0 +331 5 1 1 Fe-56 P3 0 +332 5 1 1 Fe-57 P0 0 +333 5 1 1 Fe-57 P1 0 +334 5 1 1 Fe-57 P2 0 +335 5 1 1 Fe-57 P3 0 +336 5 1 1 Fe-58 P0 0 +337 5 1 1 Fe-58 P1 0 +338 5 1 1 Fe-58 P2 0 +339 5 1 1 Fe-58 P3 0 +340 5 1 1 Ni-58 P0 0 +341 5 1 1 Ni-58 P1 0 +342 5 1 1 Ni-58 P2 0 +343 5 1 1 Ni-58 P3 0 +344 5 1 1 Ni-60 P0 0 +345 5 1 1 Ni-60 P1 0 +346 5 1 1 Ni-60 P2 0 +347 5 1 1 Ni-60 P3 0 +348 5 1 1 Ni-61 P0 0 +349 5 1 1 Ni-61 P1 0 +350 5 1 1 Ni-61 P2 0 +351 5 1 1 Ni-61 P3 0 +352 5 1 1 Ni-62 P0 0 +353 5 1 1 Ni-62 P1 0 +354 5 1 1 Ni-62 P2 0 +355 5 1 1 Ni-62 P3 0 +356 5 1 1 Ni-64 P0 0 +357 5 1 1 Ni-64 P1 0 +358 5 1 1 Ni-64 P2 0 +359 5 1 1 Ni-64 P3 0 +360 5 1 1 Mn-55 P0 0 +361 5 1 1 Mn-55 P1 0 +362 5 1 1 Mn-55 P2 0 +363 5 1 1 Mn-55 P3 0 +364 5 1 1 Mo-92 P0 0 +365 5 1 1 Mo-92 P1 0 +366 5 1 1 Mo-92 P2 0 +367 5 1 1 Mo-92 P3 0 +368 5 1 1 Mo-94 P0 0 +369 5 1 1 Mo-94 P1 0 +370 5 1 1 Mo-94 P2 0 +371 5 1 1 Mo-94 P3 0 +372 5 1 1 Mo-95 P0 0 +373 5 1 1 Mo-95 P1 0 +374 5 1 1 Mo-95 P2 0 +375 5 1 1 Mo-95 P3 0 +376 5 1 1 Mo-96 P0 0 +377 5 1 1 Mo-96 P1 0 +378 5 1 1 Mo-96 P2 0 +379 5 1 1 Mo-96 P3 0 +380 5 1 1 Mo-97 P0 0 +381 5 1 1 Mo-97 P1 0 +382 5 1 1 Mo-97 P2 0 +383 5 1 1 Mo-97 P3 0 +384 5 1 1 Mo-98 P0 0 +385 5 1 1 Mo-98 P1 0 +386 5 1 1 Mo-98 P2 0 +387 5 1 1 Mo-98 P3 0 +388 5 1 1 Mo-100 P0 0 +389 5 1 1 Mo-100 P1 0 +390 5 1 1 Mo-100 P2 0 +391 5 1 1 Mo-100 P3 0 +392 5 1 1 Si-28 P0 0 +393 5 1 1 Si-28 P1 0 +394 5 1 1 Si-28 P2 0 +395 5 1 1 Si-28 P3 0 +396 5 1 1 Si-29 P0 0 +397 5 1 1 Si-29 P1 0 +398 5 1 1 Si-29 P2 0 +399 5 1 1 Si-29 P3 0 +400 5 1 1 Si-30 P0 0 +401 5 1 1 Si-30 P1 0 +402 5 1 1 Si-30 P2 0 +403 5 1 1 Si-30 P3 0 +404 5 1 1 Cr-50 P0 0 +405 5 1 1 Cr-50 P1 0 +406 5 1 1 Cr-50 P2 0 +407 5 1 1 Cr-50 P3 0 +408 5 1 1 Cr-52 P0 0 +409 5 1 1 Cr-52 P1 0 +410 5 1 1 Cr-52 P2 0 +411 5 1 1 Cr-52 P3 0 +412 5 1 1 Cr-53 P0 0 +413 5 1 1 Cr-53 P1 0 +414 5 1 1 Cr-53 P2 0 +415 5 1 1 Cr-53 P3 0 +416 5 1 1 Cr-54 P0 0 +417 5 1 1 Cr-54 P1 0 +418 5 1 1 Cr-54 P2 0 +419 5 1 1 Cr-54 P3 0 +420 5 1 1 C-Nat P0 0 +421 5 1 1 C-Nat P1 0 +422 5 1 1 C-Nat P2 0 +423 5 1 1 C-Nat P3 0 +424 5 1 1 Cu-63 P0 0 +425 5 1 1 Cu-63 P1 0 +426 5 1 1 Cu-63 P2 0 +427 5 1 1 Cu-63 P3 0 +428 5 1 1 Cu-65 P0 0 +429 5 1 1 Cu-65 P1 0 +430 5 1 1 Cu-65 P2 0 +431 5 1 1 Cu-65 P3 0 +216 5 1 2 Fe-54 P0 0 +217 5 1 2 Fe-54 P1 0 +218 5 1 2 Fe-54 P2 0 +219 5 1 2 Fe-54 P3 0 +220 5 1 2 Fe-56 P0 0 +221 5 1 2 Fe-56 P1 0 +222 5 1 2 Fe-56 P2 0 +223 5 1 2 Fe-56 P3 0 +224 5 1 2 Fe-57 P0 0 +225 5 1 2 Fe-57 P1 0 +226 5 1 2 Fe-57 P2 0 +227 5 1 2 Fe-57 P3 0 +228 5 1 2 Fe-58 P0 0 +229 5 1 2 Fe-58 P1 0 +230 5 1 2 Fe-58 P2 0 +231 5 1 2 Fe-58 P3 0 +232 5 1 2 Ni-58 P0 0 +233 5 1 2 Ni-58 P1 0 +234 5 1 2 Ni-58 P2 0 +235 5 1 2 Ni-58 P3 0 +236 5 1 2 Ni-60 P0 0 +237 5 1 2 Ni-60 P1 0 +238 5 1 2 Ni-60 P2 0 +239 5 1 2 Ni-60 P3 0 +240 5 1 2 Ni-61 P0 0 +241 5 1 2 Ni-61 P1 0 +242 5 1 2 Ni-61 P2 0 +243 5 1 2 Ni-61 P3 0 +244 5 1 2 Ni-62 P0 0 +245 5 1 2 Ni-62 P1 0 +246 5 1 2 Ni-62 P2 0 +247 5 1 2 Ni-62 P3 0 +248 5 1 2 Ni-64 P0 0 +249 5 1 2 Ni-64 P1 0 +250 5 1 2 Ni-64 P2 0 +251 5 1 2 Ni-64 P3 0 +252 5 1 2 Mn-55 P0 0 +253 5 1 2 Mn-55 P1 0 +254 5 1 2 Mn-55 P2 0 +255 5 1 2 Mn-55 P3 0 +256 5 1 2 Mo-92 P0 0 +257 5 1 2 Mo-92 P1 0 +258 5 1 2 Mo-92 P2 0 +259 5 1 2 Mo-92 P3 0 +260 5 1 2 Mo-94 P0 0 +261 5 1 2 Mo-94 P1 0 +262 5 1 2 Mo-94 P2 0 +263 5 1 2 Mo-94 P3 0 +264 5 1 2 Mo-95 P0 0 +265 5 1 2 Mo-95 P1 0 +266 5 1 2 Mo-95 P2 0 +267 5 1 2 Mo-95 P3 0 +268 5 1 2 Mo-96 P0 0 +269 5 1 2 Mo-96 P1 0 +270 5 1 2 Mo-96 P2 0 +271 5 1 2 Mo-96 P3 0 +272 5 1 2 Mo-97 P0 0 +273 5 1 2 Mo-97 P1 0 +274 5 1 2 Mo-97 P2 0 +275 5 1 2 Mo-97 P3 0 +276 5 1 2 Mo-98 P0 0 +277 5 1 2 Mo-98 P1 0 +278 5 1 2 Mo-98 P2 0 +279 5 1 2 Mo-98 P3 0 +280 5 1 2 Mo-100 P0 0 +281 5 1 2 Mo-100 P1 0 +282 5 1 2 Mo-100 P2 0 +283 5 1 2 Mo-100 P3 0 +284 5 1 2 Si-28 P0 0 +285 5 1 2 Si-28 P1 0 +286 5 1 2 Si-28 P2 0 +287 5 1 2 Si-28 P3 0 +288 5 1 2 Si-29 P0 0 +289 5 1 2 Si-29 P1 0 +290 5 1 2 Si-29 P2 0 +291 5 1 2 Si-29 P3 0 +292 5 1 2 Si-30 P0 0 +293 5 1 2 Si-30 P1 0 +294 5 1 2 Si-30 P2 0 +295 5 1 2 Si-30 P3 0 +296 5 1 2 Cr-50 P0 0 +297 5 1 2 Cr-50 P1 0 +298 5 1 2 Cr-50 P2 0 +299 5 1 2 Cr-50 P3 0 +300 5 1 2 Cr-52 P0 0 +301 5 1 2 Cr-52 P1 0 +302 5 1 2 Cr-52 P2 0 +303 5 1 2 Cr-52 P3 0 +304 5 1 2 Cr-53 P0 0 +305 5 1 2 Cr-53 P1 0 +306 5 1 2 Cr-53 P2 0 +307 5 1 2 Cr-53 P3 0 +308 5 1 2 Cr-54 P0 0 +309 5 1 2 Cr-54 P1 0 +310 5 1 2 Cr-54 P2 0 +311 5 1 2 Cr-54 P3 0 +312 5 1 2 C-Nat P0 0 +313 5 1 2 C-Nat P1 0 +314 5 1 2 C-Nat P2 0 +315 5 1 2 C-Nat P3 0 +316 5 1 2 Cu-63 P0 0 +317 5 1 2 Cu-63 P1 0 +318 5 1 2 Cu-63 P2 0 +319 5 1 2 Cu-63 P3 0 +320 5 1 2 Cu-65 P0 0 +321 5 1 2 Cu-65 P1 0 +322 5 1 2 Cu-65 P2 0 +323 5 1 2 Cu-65 P3 0 +108 5 2 1 Fe-54 P0 0 +109 5 2 1 Fe-54 P1 0 +110 5 2 1 Fe-54 P2 0 +111 5 2 1 Fe-54 P3 0 +112 5 2 1 Fe-56 P0 0 +113 5 2 1 Fe-56 P1 0 +114 5 2 1 Fe-56 P2 0 +115 5 2 1 Fe-56 P3 0 +116 5 2 1 Fe-57 P0 0 +117 5 2 1 Fe-57 P1 0 +118 5 2 1 Fe-57 P2 0 +119 5 2 1 Fe-57 P3 0 +120 5 2 1 Fe-58 P0 0 +121 5 2 1 Fe-58 P1 0 +122 5 2 1 Fe-58 P2 0 +123 5 2 1 Fe-58 P3 0 +124 5 2 1 Ni-58 P0 0 +125 5 2 1 Ni-58 P1 0 +126 5 2 1 Ni-58 P2 0 +127 5 2 1 Ni-58 P3 0 +128 5 2 1 Ni-60 P0 0 +129 5 2 1 Ni-60 P1 0 +130 5 2 1 Ni-60 P2 0 +131 5 2 1 Ni-60 P3 0 +132 5 2 1 Ni-61 P0 0 +133 5 2 1 Ni-61 P1 0 +134 5 2 1 Ni-61 P2 0 +135 5 2 1 Ni-61 P3 0 +136 5 2 1 Ni-62 P0 0 +137 5 2 1 Ni-62 P1 0 +138 5 2 1 Ni-62 P2 0 +139 5 2 1 Ni-62 P3 0 +140 5 2 1 Ni-64 P0 0 +141 5 2 1 Ni-64 P1 0 +142 5 2 1 Ni-64 P2 0 +143 5 2 1 Ni-64 P3 0 +144 5 2 1 Mn-55 P0 0 +145 5 2 1 Mn-55 P1 0 +146 5 2 1 Mn-55 P2 0 +147 5 2 1 Mn-55 P3 0 +148 5 2 1 Mo-92 P0 0 +149 5 2 1 Mo-92 P1 0 +150 5 2 1 Mo-92 P2 0 +151 5 2 1 Mo-92 P3 0 +152 5 2 1 Mo-94 P0 0 +153 5 2 1 Mo-94 P1 0 +154 5 2 1 Mo-94 P2 0 +155 5 2 1 Mo-94 P3 0 +156 5 2 1 Mo-95 P0 0 +157 5 2 1 Mo-95 P1 0 +158 5 2 1 Mo-95 P2 0 +159 5 2 1 Mo-95 P3 0 +160 5 2 1 Mo-96 P0 0 +161 5 2 1 Mo-96 P1 0 +162 5 2 1 Mo-96 P2 0 +163 5 2 1 Mo-96 P3 0 +164 5 2 1 Mo-97 P0 0 +165 5 2 1 Mo-97 P1 0 +166 5 2 1 Mo-97 P2 0 +167 5 2 1 Mo-97 P3 0 +168 5 2 1 Mo-98 P0 0 +169 5 2 1 Mo-98 P1 0 +170 5 2 1 Mo-98 P2 0 +171 5 2 1 Mo-98 P3 0 +172 5 2 1 Mo-100 P0 0 +173 5 2 1 Mo-100 P1 0 +174 5 2 1 Mo-100 P2 0 +175 5 2 1 Mo-100 P3 0 +176 5 2 1 Si-28 P0 0 +177 5 2 1 Si-28 P1 0 +178 5 2 1 Si-28 P2 0 +179 5 2 1 Si-28 P3 0 +180 5 2 1 Si-29 P0 0 +181 5 2 1 Si-29 P1 0 +182 5 2 1 Si-29 P2 0 +183 5 2 1 Si-29 P3 0 +184 5 2 1 Si-30 P0 0 +185 5 2 1 Si-30 P1 0 +186 5 2 1 Si-30 P2 0 +187 5 2 1 Si-30 P3 0 +188 5 2 1 Cr-50 P0 0 +189 5 2 1 Cr-50 P1 0 +190 5 2 1 Cr-50 P2 0 +191 5 2 1 Cr-50 P3 0 +192 5 2 1 Cr-52 P0 0 +193 5 2 1 Cr-52 P1 0 +194 5 2 1 Cr-52 P2 0 +195 5 2 1 Cr-52 P3 0 +196 5 2 1 Cr-53 P0 0 +197 5 2 1 Cr-53 P1 0 +198 5 2 1 Cr-53 P2 0 +199 5 2 1 Cr-53 P3 0 +200 5 2 1 Cr-54 P0 0 +201 5 2 1 Cr-54 P1 0 +202 5 2 1 Cr-54 P2 0 +203 5 2 1 Cr-54 P3 0 +204 5 2 1 C-Nat P0 0 +205 5 2 1 C-Nat P1 0 +206 5 2 1 C-Nat P2 0 +207 5 2 1 C-Nat P3 0 +208 5 2 1 Cu-63 P0 0 +209 5 2 1 Cu-63 P1 0 +210 5 2 1 Cu-63 P2 0 +211 5 2 1 Cu-63 P3 0 +212 5 2 1 Cu-65 P0 0 +213 5 2 1 Cu-65 P1 0 +214 5 2 1 Cu-65 P2 0 +215 5 2 1 Cu-65 P3 0 +0 5 2 2 Fe-54 P0 0 +1 5 2 2 Fe-54 P1 0 +2 5 2 2 Fe-54 P2 0 +3 5 2 2 Fe-54 P3 0 +4 5 2 2 Fe-56 P0 0 +5 5 2 2 Fe-56 P1 0 +6 5 2 2 Fe-56 P2 0 +7 5 2 2 Fe-56 P3 0 +8 5 2 2 Fe-57 P0 0 +9 5 2 2 Fe-57 P1 0 +10 5 2 2 Fe-57 P2 0 +11 5 2 2 Fe-57 P3 0 +12 5 2 2 Fe-58 P0 0 +13 5 2 2 Fe-58 P1 0 +14 5 2 2 Fe-58 P2 0 +15 5 2 2 Fe-58 P3 0 +16 5 2 2 Ni-58 P0 0 +17 5 2 2 Ni-58 P1 0 +18 5 2 2 Ni-58 P2 0 +19 5 2 2 Ni-58 P3 0 +20 5 2 2 Ni-60 P0 0 +21 5 2 2 Ni-60 P1 0 +22 5 2 2 Ni-60 P2 0 +23 5 2 2 Ni-60 P3 0 +24 5 2 2 Ni-61 P0 0 +25 5 2 2 Ni-61 P1 0 +26 5 2 2 Ni-61 P2 0 +27 5 2 2 Ni-61 P3 0 +28 5 2 2 Ni-62 P0 0 +29 5 2 2 Ni-62 P1 0 +30 5 2 2 Ni-62 P2 0 +31 5 2 2 Ni-62 P3 0 +32 5 2 2 Ni-64 P0 0 +33 5 2 2 Ni-64 P1 0 +34 5 2 2 Ni-64 P2 0 +35 5 2 2 Ni-64 P3 0 +36 5 2 2 Mn-55 P0 0 +37 5 2 2 Mn-55 P1 0 +38 5 2 2 Mn-55 P2 0 +39 5 2 2 Mn-55 P3 0 +40 5 2 2 Mo-92 P0 0 +41 5 2 2 Mo-92 P1 0 +42 5 2 2 Mo-92 P2 0 +43 5 2 2 Mo-92 P3 0 +44 5 2 2 Mo-94 P0 0 +45 5 2 2 Mo-94 P1 0 +46 5 2 2 Mo-94 P2 0 +47 5 2 2 Mo-94 P3 0 +48 5 2 2 Mo-95 P0 0 +49 5 2 2 Mo-95 P1 0 +50 5 2 2 Mo-95 P2 0 +51 5 2 2 Mo-95 P3 0 +52 5 2 2 Mo-96 P0 0 +53 5 2 2 Mo-96 P1 0 +54 5 2 2 Mo-96 P2 0 +55 5 2 2 Mo-96 P3 0 +56 5 2 2 Mo-97 P0 0 +57 5 2 2 Mo-97 P1 0 +58 5 2 2 Mo-97 P2 0 +59 5 2 2 Mo-97 P3 0 +60 5 2 2 Mo-98 P0 0 +61 5 2 2 Mo-98 P1 0 +62 5 2 2 Mo-98 P2 0 +63 5 2 2 Mo-98 P3 0 +64 5 2 2 Mo-100 P0 0 +65 5 2 2 Mo-100 P1 0 +66 5 2 2 Mo-100 P2 0 +67 5 2 2 Mo-100 P3 0 +68 5 2 2 Si-28 P0 0 +69 5 2 2 Si-28 P1 0 +70 5 2 2 Si-28 P2 0 +71 5 2 2 Si-28 P3 0 +72 5 2 2 Si-29 P0 0 +73 5 2 2 Si-29 P1 0 +74 5 2 2 Si-29 P2 0 +75 5 2 2 Si-29 P3 0 +76 5 2 2 Si-30 P0 0 +77 5 2 2 Si-30 P1 0 +78 5 2 2 Si-30 P2 0 +79 5 2 2 Si-30 P3 0 +80 5 2 2 Cr-50 P0 0 +81 5 2 2 Cr-50 P1 0 +82 5 2 2 Cr-50 P2 0 +83 5 2 2 Cr-50 P3 0 +84 5 2 2 Cr-52 P0 0 +85 5 2 2 Cr-52 P1 0 +86 5 2 2 Cr-52 P2 0 +87 5 2 2 Cr-52 P3 0 +88 5 2 2 Cr-53 P0 0 +89 5 2 2 Cr-53 P1 0 +90 5 2 2 Cr-53 P2 0 +91 5 2 2 Cr-53 P3 0 +92 5 2 2 Cr-54 P0 0 +93 5 2 2 Cr-54 P1 0 +94 5 2 2 Cr-54 P2 0 +95 5 2 2 Cr-54 P3 0 +96 5 2 2 C-Nat P0 0 +97 5 2 2 C-Nat P1 0 +98 5 2 2 C-Nat P2 0 +99 5 2 2 C-Nat P3 0 +100 5 2 2 Cu-63 P0 0 +101 5 2 2 Cu-63 P1 0 +102 5 2 2 Cu-63 P2 0 +103 5 2 2 Cu-63 P3 0 +104 5 2 2 Cu-65 P0 0 +105 5 2 2 Cu-65 P1 0 +106 5 2 2 Cu-65 P2 0 +107 5 2 2 Cu-65 P3 0 material group out nuclide mean std. dev. +27 5 1 Fe-54 0 0 +28 5 1 Fe-56 0 0 +29 5 1 Fe-57 0 0 +30 5 1 Fe-58 0 0 +31 5 1 Ni-58 0 0 +32 5 1 Ni-60 0 0 +33 5 1 Ni-61 0 0 +34 5 1 Ni-62 0 0 +35 5 1 Ni-64 0 0 +36 5 1 Mn-55 0 0 +37 5 1 Mo-92 0 0 +38 5 1 Mo-94 0 0 +39 5 1 Mo-95 0 0 +40 5 1 Mo-96 0 0 +41 5 1 Mo-97 0 0 +42 5 1 Mo-98 0 0 +43 5 1 Mo-100 0 0 +44 5 1 Si-28 0 0 +45 5 1 Si-29 0 0 +46 5 1 Si-30 0 0 +47 5 1 Cr-50 0 0 +48 5 1 Cr-52 0 0 +49 5 1 Cr-53 0 0 +50 5 1 Cr-54 0 0 +51 5 1 C-Nat 0 0 +52 5 1 Cu-63 0 0 +53 5 1 Cu-65 0 0 +0 5 2 Fe-54 0 0 +1 5 2 Fe-56 0 0 +2 5 2 Fe-57 0 0 +3 5 2 Fe-58 0 0 +4 5 2 Ni-58 0 0 +5 5 2 Ni-60 0 0 +6 5 2 Ni-61 0 0 +7 5 2 Ni-62 0 0 +8 5 2 Ni-64 0 0 +9 5 2 Mn-55 0 0 +10 5 2 Mo-92 0 0 +11 5 2 Mo-94 0 0 +12 5 2 Mo-95 0 0 +13 5 2 Mo-96 0 0 +14 5 2 Mo-97 0 0 +15 5 2 Mo-98 0 0 +16 5 2 Mo-100 0 0 +17 5 2 Si-28 0 0 +18 5 2 Si-29 0 0 +19 5 2 Si-30 0 0 +20 5 2 Cr-50 0 0 +21 5 2 Cr-52 0 0 +22 5 2 Cr-53 0 0 +23 5 2 Cr-54 0 0 +24 5 2 C-Nat 0 0 +25 5 2 Cu-63 0 0 +26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in group out nuclide moment mean +252 6 1 1 H-1 P0 0 +253 6 1 1 H-1 P1 0 +254 6 1 1 H-1 P2 0 +255 6 1 1 H-1 P3 0 +256 6 1 1 O-16 P0 0 +257 6 1 1 O-16 P1 0 +258 6 1 1 O-16 P2 0 +259 6 1 1 O-16 P3 0 +260 6 1 1 B-10 P0 0 +261 6 1 1 B-10 P1 0 +262 6 1 1 B-10 P2 0 +263 6 1 1 B-10 P3 0 +264 6 1 1 B-11 P0 0 +265 6 1 1 B-11 P1 0 +266 6 1 1 B-11 P2 0 +267 6 1 1 B-11 P3 0 +268 6 1 1 Fe-54 P0 0 +269 6 1 1 Fe-54 P1 0 +270 6 1 1 Fe-54 P2 0 +271 6 1 1 Fe-54 P3 0 +272 6 1 1 Fe-56 P0 0 +273 6 1 1 Fe-56 P1 0 +274 6 1 1 Fe-56 P2 0 +275 6 1 1 Fe-56 P3 0 +276 6 1 1 Fe-57 P0 0 +277 6 1 1 Fe-57 P1 0 +278 6 1 1 Fe-57 P2 0 +279 6 1 1 Fe-57 P3 0 +280 6 1 1 Fe-58 P0 0 +281 6 1 1 Fe-58 P1 0 +282 6 1 1 Fe-58 P2 0 +283 6 1 1 Fe-58 P3 0 +284 6 1 1 Ni-58 P0 0 +285 6 1 1 Ni-58 P1 0 +286 6 1 1 Ni-58 P2 0 +287 6 1 1 Ni-58 P3 0 +288 6 1 1 Ni-60 P0 0 +289 6 1 1 Ni-60 P1 0 +290 6 1 1 Ni-60 P2 0 +291 6 1 1 Ni-60 P3 0 +292 6 1 1 Ni-61 P0 0 +293 6 1 1 Ni-61 P1 0 +294 6 1 1 Ni-61 P2 0 +295 6 1 1 Ni-61 P3 0 +296 6 1 1 Ni-62 P0 0 +297 6 1 1 Ni-62 P1 0 +298 6 1 1 Ni-62 P2 0 +299 6 1 1 Ni-62 P3 0 +300 6 1 1 Ni-64 P0 0 +301 6 1 1 Ni-64 P1 0 +302 6 1 1 Ni-64 P2 0 +303 6 1 1 Ni-64 P3 0 +304 6 1 1 Mn-55 P0 0 +305 6 1 1 Mn-55 P1 0 +306 6 1 1 Mn-55 P2 0 +307 6 1 1 Mn-55 P3 0 +308 6 1 1 Si-28 P0 0 +309 6 1 1 Si-28 P1 0 +310 6 1 1 Si-28 P2 0 +311 6 1 1 Si-28 P3 0 +312 6 1 1 Si-29 P0 0 +313 6 1 1 Si-29 P1 0 +314 6 1 1 Si-29 P2 0 +315 6 1 1 Si-29 P3 0 +316 6 1 1 Si-30 P0 0 +317 6 1 1 Si-30 P1 0 +318 6 1 1 Si-30 P2 0 +319 6 1 1 Si-30 P3 0 +320 6 1 1 Cr-50 P0 0 +321 6 1 1 Cr-50 P1 0 +322 6 1 1 Cr-50 P2 0 +323 6 1 1 Cr-50 P3 0 +324 6 1 1 Cr-52 P0 0 +325 6 1 1 Cr-52 P1 0 +326 6 1 1 Cr-52 P2 0 +327 6 1 1 Cr-52 P3 0 +328 6 1 1 Cr-53 P0 0 +329 6 1 1 Cr-53 P1 0 +330 6 1 1 Cr-53 P2 0 +331 6 1 1 Cr-53 P3 0 +332 6 1 1 Cr-54 P0 0 +333 6 1 1 Cr-54 P1 0 +334 6 1 1 Cr-54 P2 0 +335 6 1 1 Cr-54 P3 0 +168 6 1 2 H-1 P0 0 +169 6 1 2 H-1 P1 0 +170 6 1 2 H-1 P2 0 +171 6 1 2 H-1 P3 0 +172 6 1 2 O-16 P0 0 +173 6 1 2 O-16 P1 0 +174 6 1 2 O-16 P2 0 +175 6 1 2 O-16 P3 0 +176 6 1 2 B-10 P0 0 +177 6 1 2 B-10 P1 0 +178 6 1 2 B-10 P2 0 +179 6 1 2 B-10 P3 0 +180 6 1 2 B-11 P0 0 +181 6 1 2 B-11 P1 0 +182 6 1 2 B-11 P2 0 +183 6 1 2 B-11 P3 0 +184 6 1 2 Fe-54 P0 0 +185 6 1 2 Fe-54 P1 0 +186 6 1 2 Fe-54 P2 0 +187 6 1 2 Fe-54 P3 0 +188 6 1 2 Fe-56 P0 0 +189 6 1 2 Fe-56 P1 0 +190 6 1 2 Fe-56 P2 0 +191 6 1 2 Fe-56 P3 0 +192 6 1 2 Fe-57 P0 0 +193 6 1 2 Fe-57 P1 0 +194 6 1 2 Fe-57 P2 0 +195 6 1 2 Fe-57 P3 0 +196 6 1 2 Fe-58 P0 0 +197 6 1 2 Fe-58 P1 0 +198 6 1 2 Fe-58 P2 0 +199 6 1 2 Fe-58 P3 0 +200 6 1 2 Ni-58 P0 0 +201 6 1 2 Ni-58 P1 0 +202 6 1 2 Ni-58 P2 0 +203 6 1 2 Ni-58 P3 0 +204 6 1 2 Ni-60 P0 0 +205 6 1 2 Ni-60 P1 0 +206 6 1 2 Ni-60 P2 0 +207 6 1 2 Ni-60 P3 0 +208 6 1 2 Ni-61 P0 0 +209 6 1 2 Ni-61 P1 0 +210 6 1 2 Ni-61 P2 0 +211 6 1 2 Ni-61 P3 0 +212 6 1 2 Ni-62 P0 0 +213 6 1 2 Ni-62 P1 0 +214 6 1 2 Ni-62 P2 0 +215 6 1 2 Ni-62 P3 0 +216 6 1 2 Ni-64 P0 0 +217 6 1 2 Ni-64 P1 0 +218 6 1 2 Ni-64 P2 0 +219 6 1 2 Ni-64 P3 0 +220 6 1 2 Mn-55 P0 0 +221 6 1 2 Mn-55 P1 0 +222 6 1 2 Mn-55 P2 0 +223 6 1 2 Mn-55 P3 0 +224 6 1 2 Si-28 P0 0 +225 6 1 2 Si-28 P1 0 +226 6 1 2 Si-28 P2 0 +227 6 1 2 Si-28 P3 0 +228 6 1 2 Si-29 P0 0 +229 6 1 2 Si-29 P1 0 +230 6 1 2 Si-29 P2 0 +231 6 1 2 Si-29 P3 0 +232 6 1 2 Si-30 P0 0 +233 6 1 2 Si-30 P1 0 +234 6 1 2 Si-30 P2 0 +235 6 1 2 Si-30 P3 0 +236 6 1 2 Cr-50 P0 0 +237 6 1 2 Cr-50 P1 0 +238 6 1 2 Cr-50 P2 0 +239 6 1 2 Cr-50 P3 0 +240 6 1 2 Cr-52 P0 0 +241 6 1 2 Cr-52 P1 0 +242 6 1 2 Cr-52 P2 0 +243 6 1 2 Cr-52 P3 0 +244 6 1 2 Cr-53 P0 0 +245 6 1 2 Cr-53 P1 0 +246 6 1 2 Cr-53 P2 0 +247 6 1 2 Cr-53 P3 0 +248 6 1 2 Cr-54 P0 0 +249 6 1 2 Cr-54 P1 0 +250 6 1 2 Cr-54 P2 0 +251 6 1 2 Cr-54 P3 0 +84 6 2 1 H-1 P0 0 +85 6 2 1 H-1 P1 0 +86 6 2 1 H-1 P2 0 +87 6 2 1 H-1 P3 0 +88 6 2 1 O-16 P0 0 +89 6 2 1 O-16 P1 0 +90 6 2 1 O-16 P2 0 +91 6 2 1 O-16 P3 0 +92 6 2 1 B-10 P0 0 +93 6 2 1 B-10 P1 0 +94 6 2 1 B-10 P2 0 +95 6 2 1 B-10 P3 0 +96 6 2 1 B-11 P0 0 +97 6 2 1 B-11 P1 0 +98 6 2 1 B-11 P2 0 +99 6 2 1 B-11 P3 0 +100 6 2 1 Fe-54 P0 0 +101 6 2 1 Fe-54 P1 0 +102 6 2 1 Fe-54 P2 0 +103 6 2 1 Fe-54 P3 0 +104 6 2 1 Fe-56 P0 0 +105 6 2 1 Fe-56 P1 0 +106 6 2 1 Fe-56 P2 0 +107 6 2 1 Fe-56 P3 0 +108 6 2 1 Fe-57 P0 0 +109 6 2 1 Fe-57 P1 0 +110 6 2 1 Fe-57 P2 0 +111 6 2 1 Fe-57 P3 0 +112 6 2 1 Fe-58 P0 0 +113 6 2 1 Fe-58 P1 0 +114 6 2 1 Fe-58 P2 0 +115 6 2 1 Fe-58 P3 0 +116 6 2 1 Ni-58 P0 0 +117 6 2 1 Ni-58 P1 0 +118 6 2 1 Ni-58 P2 0 +119 6 2 1 Ni-58 P3 0 +120 6 2 1 Ni-60 P0 0 +121 6 2 1 Ni-60 P1 0 +122 6 2 1 Ni-60 P2 0 +123 6 2 1 Ni-60 P3 0 +124 6 2 1 Ni-61 P0 0 +125 6 2 1 Ni-61 P1 0 +126 6 2 1 Ni-61 P2 0 +127 6 2 1 Ni-61 P3 0 +128 6 2 1 Ni-62 P0 0 +129 6 2 1 Ni-62 P1 0 +130 6 2 1 Ni-62 P2 0 +131 6 2 1 Ni-62 P3 0 +132 6 2 1 Ni-64 P0 0 +133 6 2 1 Ni-64 P1 0 +134 6 2 1 Ni-64 P2 0 +135 6 2 1 Ni-64 P3 0 +136 6 2 1 Mn-55 P0 0 +137 6 2 1 Mn-55 P1 0 +138 6 2 1 Mn-55 P2 0 +139 6 2 1 Mn-55 P3 0 +140 6 2 1 Si-28 P0 0 +141 6 2 1 Si-28 P1 0 +142 6 2 1 Si-28 P2 0 +143 6 2 1 Si-28 P3 0 +144 6 2 1 Si-29 P0 0 +145 6 2 1 Si-29 P1 0 +146 6 2 1 Si-29 P2 0 +147 6 2 1 Si-29 P3 0 +148 6 2 1 Si-30 P0 0 +149 6 2 1 Si-30 P1 0 +150 6 2 1 Si-30 P2 0 +151 6 2 1 Si-30 P3 0 +152 6 2 1 Cr-50 P0 0 +153 6 2 1 Cr-50 P1 0 +154 6 2 1 Cr-50 P2 0 +155 6 2 1 Cr-50 P3 0 +156 6 2 1 Cr-52 P0 0 +157 6 2 1 Cr-52 P1 0 +158 6 2 1 Cr-52 P2 0 +159 6 2 1 Cr-52 P3 0 +160 6 2 1 Cr-53 P0 0 +161 6 2 1 Cr-53 P1 0 +162 6 2 1 Cr-53 P2 0 +163 6 2 1 Cr-53 P3 0 +164 6 2 1 Cr-54 P0 0 +165 6 2 1 Cr-54 P1 0 +166 6 2 1 Cr-54 P2 0 +167 6 2 1 Cr-54 P3 0 +0 6 2 2 H-1 P0 0 +1 6 2 2 H-1 P1 0 +2 6 2 2 H-1 P2 0 +3 6 2 2 H-1 P3 0 +4 6 2 2 O-16 P0 0 +5 6 2 2 O-16 P1 0 +6 6 2 2 O-16 P2 0 +7 6 2 2 O-16 P3 0 +8 6 2 2 B-10 P0 0 +9 6 2 2 B-10 P1 0 +10 6 2 2 B-10 P2 0 +11 6 2 2 B-10 P3 0 +12 6 2 2 B-11 P0 0 +13 6 2 2 B-11 P1 0 +14 6 2 2 B-11 P2 0 +15 6 2 2 B-11 P3 0 +16 6 2 2 Fe-54 P0 0 +17 6 2 2 Fe-54 P1 0 +18 6 2 2 Fe-54 P2 0 +19 6 2 2 Fe-54 P3 0 +20 6 2 2 Fe-56 P0 0 +21 6 2 2 Fe-56 P1 0 +22 6 2 2 Fe-56 P2 0 +23 6 2 2 Fe-56 P3 0 +24 6 2 2 Fe-57 P0 0 +25 6 2 2 Fe-57 P1 0 +26 6 2 2 Fe-57 P2 0 +27 6 2 2 Fe-57 P3 0 +28 6 2 2 Fe-58 P0 0 +29 6 2 2 Fe-58 P1 0 +30 6 2 2 Fe-58 P2 0 +31 6 2 2 Fe-58 P3 0 +32 6 2 2 Ni-58 P0 0 +33 6 2 2 Ni-58 P1 0 +34 6 2 2 Ni-58 P2 0 +35 6 2 2 Ni-58 P3 0 +36 6 2 2 Ni-60 P0 0 +37 6 2 2 Ni-60 P1 0 +38 6 2 2 Ni-60 P2 0 +39 6 2 2 Ni-60 P3 0 +40 6 2 2 Ni-61 P0 0 +41 6 2 2 Ni-61 P1 0 +42 6 2 2 Ni-61 P2 0 +43 6 2 2 Ni-61 P3 0 +44 6 2 2 Ni-62 P0 0 +45 6 2 2 Ni-62 P1 0 +46 6 2 2 Ni-62 P2 0 +47 6 2 2 Ni-62 P3 0 +48 6 2 2 Ni-64 P0 0 +49 6 2 2 Ni-64 P1 0 +50 6 2 2 Ni-64 P2 0 +51 6 2 2 Ni-64 P3 0 +52 6 2 2 Mn-55 P0 0 +53 6 2 2 Mn-55 P1 0 +54 6 2 2 Mn-55 P2 0 +55 6 2 2 Mn-55 P3 0 +56 6 2 2 Si-28 P0 0 +57 6 2 2 Si-28 P1 0 +58 6 2 2 Si-28 P2 0 +59 6 2 2 Si-28 P3 0 +60 6 2 2 Si-29 P0 0 +61 6 2 2 Si-29 P1 0 +62 6 2 2 Si-29 P2 0 +63 6 2 2 Si-29 P3 0 +64 6 2 2 Si-30 P0 0 +65 6 2 2 Si-30 P1 0 +66 6 2 2 Si-30 P2 0 +67 6 2 2 Si-30 P3 0 +68 6 2 2 Cr-50 P0 0 +69 6 2 2 Cr-50 P1 0 +70 6 2 2 Cr-50 P2 0 +71 6 2 2 Cr-50 P3 0 +72 6 2 2 Cr-52 P0 0 +73 6 2 2 Cr-52 P1 0 +74 6 2 2 Cr-52 P2 0 +75 6 2 2 Cr-52 P3 0 +76 6 2 2 Cr-53 P0 0 +77 6 2 2 Cr-53 P1 0 +78 6 2 2 Cr-53 P2 0 +79 6 2 2 Cr-53 P3 0 +80 6 2 2 Cr-54 P0 0 +81 6 2 2 Cr-54 P1 0 +82 6 2 2 Cr-54 P2 0 +83 6 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. +21 6 1 H-1 0 0 +22 6 1 O-16 0 0 +23 6 1 B-10 0 0 +24 6 1 B-11 0 0 +25 6 1 Fe-54 0 0 +26 6 1 Fe-56 0 0 +27 6 1 Fe-57 0 0 +28 6 1 Fe-58 0 0 +29 6 1 Ni-58 0 0 +30 6 1 Ni-60 0 0 +31 6 1 Ni-61 0 0 +32 6 1 Ni-62 0 0 +33 6 1 Ni-64 0 0 +34 6 1 Mn-55 0 0 +35 6 1 Si-28 0 0 +36 6 1 Si-29 0 0 +37 6 1 Si-30 0 0 +38 6 1 Cr-50 0 0 +39 6 1 Cr-52 0 0 +40 6 1 Cr-53 0 0 +41 6 1 Cr-54 0 0 +0 6 2 H-1 0 0 +1 6 2 O-16 0 0 +2 6 2 B-10 0 0 +3 6 2 B-11 0 0 +4 6 2 Fe-54 0 0 +5 6 2 Fe-56 0 0 +6 6 2 Fe-57 0 0 +7 6 2 Fe-58 0 0 +8 6 2 Ni-58 0 0 +9 6 2 Ni-60 0 0 +10 6 2 Ni-61 0 0 +11 6 2 Ni-62 0 0 +12 6 2 Ni-64 0 0 +13 6 2 Mn-55 0 0 +14 6 2 Si-28 0 0 +15 6 2 Si-29 0 0 +16 6 2 Si-30 0 0 +17 6 2 Cr-50 0 0 +18 6 2 Cr-52 0 0 +19 6 2 Cr-53 0 0 +20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in group out nuclide moment mean +252 7 1 1 H-1 P0 0 +253 7 1 1 H-1 P1 0 +254 7 1 1 H-1 P2 0 +255 7 1 1 H-1 P3 0 +256 7 1 1 O-16 P0 0 +257 7 1 1 O-16 P1 0 +258 7 1 1 O-16 P2 0 +259 7 1 1 O-16 P3 0 +260 7 1 1 B-10 P0 0 +261 7 1 1 B-10 P1 0 +262 7 1 1 B-10 P2 0 +263 7 1 1 B-10 P3 0 +264 7 1 1 B-11 P0 0 +265 7 1 1 B-11 P1 0 +266 7 1 1 B-11 P2 0 +267 7 1 1 B-11 P3 0 +268 7 1 1 Fe-54 P0 0 +269 7 1 1 Fe-54 P1 0 +270 7 1 1 Fe-54 P2 0 +271 7 1 1 Fe-54 P3 0 +272 7 1 1 Fe-56 P0 0 +273 7 1 1 Fe-56 P1 0 +274 7 1 1 Fe-56 P2 0 +275 7 1 1 Fe-56 P3 0 +276 7 1 1 Fe-57 P0 0 +277 7 1 1 Fe-57 P1 0 +278 7 1 1 Fe-57 P2 0 +279 7 1 1 Fe-57 P3 0 +280 7 1 1 Fe-58 P0 0 +281 7 1 1 Fe-58 P1 0 +282 7 1 1 Fe-58 P2 0 +283 7 1 1 Fe-58 P3 0 +284 7 1 1 Ni-58 P0 0 +285 7 1 1 Ni-58 P1 0 +286 7 1 1 Ni-58 P2 0 +287 7 1 1 Ni-58 P3 0 +288 7 1 1 Ni-60 P0 0 +289 7 1 1 Ni-60 P1 0 +290 7 1 1 Ni-60 P2 0 +291 7 1 1 Ni-60 P3 0 +292 7 1 1 Ni-61 P0 0 +293 7 1 1 Ni-61 P1 0 +294 7 1 1 Ni-61 P2 0 +295 7 1 1 Ni-61 P3 0 +296 7 1 1 Ni-62 P0 0 +297 7 1 1 Ni-62 P1 0 +298 7 1 1 Ni-62 P2 0 +299 7 1 1 Ni-62 P3 0 +300 7 1 1 Ni-64 P0 0 +301 7 1 1 Ni-64 P1 0 +302 7 1 1 Ni-64 P2 0 +303 7 1 1 Ni-64 P3 0 +304 7 1 1 Mn-55 P0 0 +305 7 1 1 Mn-55 P1 0 +306 7 1 1 Mn-55 P2 0 +307 7 1 1 Mn-55 P3 0 +308 7 1 1 Si-28 P0 0 +309 7 1 1 Si-28 P1 0 +310 7 1 1 Si-28 P2 0 +311 7 1 1 Si-28 P3 0 +312 7 1 1 Si-29 P0 0 +313 7 1 1 Si-29 P1 0 +314 7 1 1 Si-29 P2 0 +315 7 1 1 Si-29 P3 0 +316 7 1 1 Si-30 P0 0 +317 7 1 1 Si-30 P1 0 +318 7 1 1 Si-30 P2 0 +319 7 1 1 Si-30 P3 0 +320 7 1 1 Cr-50 P0 0 +321 7 1 1 Cr-50 P1 0 +322 7 1 1 Cr-50 P2 0 +323 7 1 1 Cr-50 P3 0 +324 7 1 1 Cr-52 P0 0 +325 7 1 1 Cr-52 P1 0 +326 7 1 1 Cr-52 P2 0 +327 7 1 1 Cr-52 P3 0 +328 7 1 1 Cr-53 P0 0 +329 7 1 1 Cr-53 P1 0 +330 7 1 1 Cr-53 P2 0 +331 7 1 1 Cr-53 P3 0 +332 7 1 1 Cr-54 P0 0 +333 7 1 1 Cr-54 P1 0 +334 7 1 1 Cr-54 P2 0 +335 7 1 1 Cr-54 P3 0 +168 7 1 2 H-1 P0 0 +169 7 1 2 H-1 P1 0 +170 7 1 2 H-1 P2 0 +171 7 1 2 H-1 P3 0 +172 7 1 2 O-16 P0 0 +173 7 1 2 O-16 P1 0 +174 7 1 2 O-16 P2 0 +175 7 1 2 O-16 P3 0 +176 7 1 2 B-10 P0 0 +177 7 1 2 B-10 P1 0 +178 7 1 2 B-10 P2 0 +179 7 1 2 B-10 P3 0 +180 7 1 2 B-11 P0 0 +181 7 1 2 B-11 P1 0 +182 7 1 2 B-11 P2 0 +183 7 1 2 B-11 P3 0 +184 7 1 2 Fe-54 P0 0 +185 7 1 2 Fe-54 P1 0 +186 7 1 2 Fe-54 P2 0 +187 7 1 2 Fe-54 P3 0 +188 7 1 2 Fe-56 P0 0 +189 7 1 2 Fe-56 P1 0 +190 7 1 2 Fe-56 P2 0 +191 7 1 2 Fe-56 P3 0 +192 7 1 2 Fe-57 P0 0 +193 7 1 2 Fe-57 P1 0 +194 7 1 2 Fe-57 P2 0 +195 7 1 2 Fe-57 P3 0 +196 7 1 2 Fe-58 P0 0 +197 7 1 2 Fe-58 P1 0 +198 7 1 2 Fe-58 P2 0 +199 7 1 2 Fe-58 P3 0 +200 7 1 2 Ni-58 P0 0 +201 7 1 2 Ni-58 P1 0 +202 7 1 2 Ni-58 P2 0 +203 7 1 2 Ni-58 P3 0 +204 7 1 2 Ni-60 P0 0 +205 7 1 2 Ni-60 P1 0 +206 7 1 2 Ni-60 P2 0 +207 7 1 2 Ni-60 P3 0 +208 7 1 2 Ni-61 P0 0 +209 7 1 2 Ni-61 P1 0 +210 7 1 2 Ni-61 P2 0 +211 7 1 2 Ni-61 P3 0 +212 7 1 2 Ni-62 P0 0 +213 7 1 2 Ni-62 P1 0 +214 7 1 2 Ni-62 P2 0 +215 7 1 2 Ni-62 P3 0 +216 7 1 2 Ni-64 P0 0 +217 7 1 2 Ni-64 P1 0 +218 7 1 2 Ni-64 P2 0 +219 7 1 2 Ni-64 P3 0 +220 7 1 2 Mn-55 P0 0 +221 7 1 2 Mn-55 P1 0 +222 7 1 2 Mn-55 P2 0 +223 7 1 2 Mn-55 P3 0 +224 7 1 2 Si-28 P0 0 +225 7 1 2 Si-28 P1 0 +226 7 1 2 Si-28 P2 0 +227 7 1 2 Si-28 P3 0 +228 7 1 2 Si-29 P0 0 +229 7 1 2 Si-29 P1 0 +230 7 1 2 Si-29 P2 0 +231 7 1 2 Si-29 P3 0 +232 7 1 2 Si-30 P0 0 +233 7 1 2 Si-30 P1 0 +234 7 1 2 Si-30 P2 0 +235 7 1 2 Si-30 P3 0 +236 7 1 2 Cr-50 P0 0 +237 7 1 2 Cr-50 P1 0 +238 7 1 2 Cr-50 P2 0 +239 7 1 2 Cr-50 P3 0 +240 7 1 2 Cr-52 P0 0 +241 7 1 2 Cr-52 P1 0 +242 7 1 2 Cr-52 P2 0 +243 7 1 2 Cr-52 P3 0 +244 7 1 2 Cr-53 P0 0 +245 7 1 2 Cr-53 P1 0 +246 7 1 2 Cr-53 P2 0 +247 7 1 2 Cr-53 P3 0 +248 7 1 2 Cr-54 P0 0 +249 7 1 2 Cr-54 P1 0 +250 7 1 2 Cr-54 P2 0 +251 7 1 2 Cr-54 P3 0 +84 7 2 1 H-1 P0 0 +85 7 2 1 H-1 P1 0 +86 7 2 1 H-1 P2 0 +87 7 2 1 H-1 P3 0 +88 7 2 1 O-16 P0 0 +89 7 2 1 O-16 P1 0 +90 7 2 1 O-16 P2 0 +91 7 2 1 O-16 P3 0 +92 7 2 1 B-10 P0 0 +93 7 2 1 B-10 P1 0 +94 7 2 1 B-10 P2 0 +95 7 2 1 B-10 P3 0 +96 7 2 1 B-11 P0 0 +97 7 2 1 B-11 P1 0 +98 7 2 1 B-11 P2 0 +99 7 2 1 B-11 P3 0 +100 7 2 1 Fe-54 P0 0 +101 7 2 1 Fe-54 P1 0 +102 7 2 1 Fe-54 P2 0 +103 7 2 1 Fe-54 P3 0 +104 7 2 1 Fe-56 P0 0 +105 7 2 1 Fe-56 P1 0 +106 7 2 1 Fe-56 P2 0 +107 7 2 1 Fe-56 P3 0 +108 7 2 1 Fe-57 P0 0 +109 7 2 1 Fe-57 P1 0 +110 7 2 1 Fe-57 P2 0 +111 7 2 1 Fe-57 P3 0 +112 7 2 1 Fe-58 P0 0 +113 7 2 1 Fe-58 P1 0 +114 7 2 1 Fe-58 P2 0 +115 7 2 1 Fe-58 P3 0 +116 7 2 1 Ni-58 P0 0 +117 7 2 1 Ni-58 P1 0 +118 7 2 1 Ni-58 P2 0 +119 7 2 1 Ni-58 P3 0 +120 7 2 1 Ni-60 P0 0 +121 7 2 1 Ni-60 P1 0 +122 7 2 1 Ni-60 P2 0 +123 7 2 1 Ni-60 P3 0 +124 7 2 1 Ni-61 P0 0 +125 7 2 1 Ni-61 P1 0 +126 7 2 1 Ni-61 P2 0 +127 7 2 1 Ni-61 P3 0 +128 7 2 1 Ni-62 P0 0 +129 7 2 1 Ni-62 P1 0 +130 7 2 1 Ni-62 P2 0 +131 7 2 1 Ni-62 P3 0 +132 7 2 1 Ni-64 P0 0 +133 7 2 1 Ni-64 P1 0 +134 7 2 1 Ni-64 P2 0 +135 7 2 1 Ni-64 P3 0 +136 7 2 1 Mn-55 P0 0 +137 7 2 1 Mn-55 P1 0 +138 7 2 1 Mn-55 P2 0 +139 7 2 1 Mn-55 P3 0 +140 7 2 1 Si-28 P0 0 +141 7 2 1 Si-28 P1 0 +142 7 2 1 Si-28 P2 0 +143 7 2 1 Si-28 P3 0 +144 7 2 1 Si-29 P0 0 +145 7 2 1 Si-29 P1 0 +146 7 2 1 Si-29 P2 0 +147 7 2 1 Si-29 P3 0 +148 7 2 1 Si-30 P0 0 +149 7 2 1 Si-30 P1 0 +150 7 2 1 Si-30 P2 0 +151 7 2 1 Si-30 P3 0 +152 7 2 1 Cr-50 P0 0 +153 7 2 1 Cr-50 P1 0 +154 7 2 1 Cr-50 P2 0 +155 7 2 1 Cr-50 P3 0 +156 7 2 1 Cr-52 P0 0 +157 7 2 1 Cr-52 P1 0 +158 7 2 1 Cr-52 P2 0 +159 7 2 1 Cr-52 P3 0 +160 7 2 1 Cr-53 P0 0 +161 7 2 1 Cr-53 P1 0 +162 7 2 1 Cr-53 P2 0 +163 7 2 1 Cr-53 P3 0 +164 7 2 1 Cr-54 P0 0 +165 7 2 1 Cr-54 P1 0 +166 7 2 1 Cr-54 P2 0 +167 7 2 1 Cr-54 P3 0 +0 7 2 2 H-1 P0 0 +1 7 2 2 H-1 P1 0 +2 7 2 2 H-1 P2 0 +3 7 2 2 H-1 P3 0 +4 7 2 2 O-16 P0 0 +5 7 2 2 O-16 P1 0 +6 7 2 2 O-16 P2 0 +7 7 2 2 O-16 P3 0 +8 7 2 2 B-10 P0 0 +9 7 2 2 B-10 P1 0 +10 7 2 2 B-10 P2 0 +11 7 2 2 B-10 P3 0 +12 7 2 2 B-11 P0 0 +13 7 2 2 B-11 P1 0 +14 7 2 2 B-11 P2 0 +15 7 2 2 B-11 P3 0 +16 7 2 2 Fe-54 P0 0 +17 7 2 2 Fe-54 P1 0 +18 7 2 2 Fe-54 P2 0 +19 7 2 2 Fe-54 P3 0 +20 7 2 2 Fe-56 P0 0 +21 7 2 2 Fe-56 P1 0 +22 7 2 2 Fe-56 P2 0 +23 7 2 2 Fe-56 P3 0 +24 7 2 2 Fe-57 P0 0 +25 7 2 2 Fe-57 P1 0 +26 7 2 2 Fe-57 P2 0 +27 7 2 2 Fe-57 P3 0 +28 7 2 2 Fe-58 P0 0 +29 7 2 2 Fe-58 P1 0 +30 7 2 2 Fe-58 P2 0 +31 7 2 2 Fe-58 P3 0 +32 7 2 2 Ni-58 P0 0 +33 7 2 2 Ni-58 P1 0 +34 7 2 2 Ni-58 P2 0 +35 7 2 2 Ni-58 P3 0 +36 7 2 2 Ni-60 P0 0 +37 7 2 2 Ni-60 P1 0 +38 7 2 2 Ni-60 P2 0 +39 7 2 2 Ni-60 P3 0 +40 7 2 2 Ni-61 P0 0 +41 7 2 2 Ni-61 P1 0 +42 7 2 2 Ni-61 P2 0 +43 7 2 2 Ni-61 P3 0 +44 7 2 2 Ni-62 P0 0 +45 7 2 2 Ni-62 P1 0 +46 7 2 2 Ni-62 P2 0 +47 7 2 2 Ni-62 P3 0 +48 7 2 2 Ni-64 P0 0 +49 7 2 2 Ni-64 P1 0 +50 7 2 2 Ni-64 P2 0 +51 7 2 2 Ni-64 P3 0 +52 7 2 2 Mn-55 P0 0 +53 7 2 2 Mn-55 P1 0 +54 7 2 2 Mn-55 P2 0 +55 7 2 2 Mn-55 P3 0 +56 7 2 2 Si-28 P0 0 +57 7 2 2 Si-28 P1 0 +58 7 2 2 Si-28 P2 0 +59 7 2 2 Si-28 P3 0 +60 7 2 2 Si-29 P0 0 +61 7 2 2 Si-29 P1 0 +62 7 2 2 Si-29 P2 0 +63 7 2 2 Si-29 P3 0 +64 7 2 2 Si-30 P0 0 +65 7 2 2 Si-30 P1 0 +66 7 2 2 Si-30 P2 0 +67 7 2 2 Si-30 P3 0 +68 7 2 2 Cr-50 P0 0 +69 7 2 2 Cr-50 P1 0 +70 7 2 2 Cr-50 P2 0 +71 7 2 2 Cr-50 P3 0 +72 7 2 2 Cr-52 P0 0 +73 7 2 2 Cr-52 P1 0 +74 7 2 2 Cr-52 P2 0 +75 7 2 2 Cr-52 P3 0 +76 7 2 2 Cr-53 P0 0 +77 7 2 2 Cr-53 P1 0 +78 7 2 2 Cr-53 P2 0 +79 7 2 2 Cr-53 P3 0 +80 7 2 2 Cr-54 P0 0 +81 7 2 2 Cr-54 P1 0 +82 7 2 2 Cr-54 P2 0 +83 7 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. +21 7 1 H-1 0 0 +22 7 1 O-16 0 0 +23 7 1 B-10 0 0 +24 7 1 B-11 0 0 +25 7 1 Fe-54 0 0 +26 7 1 Fe-56 0 0 +27 7 1 Fe-57 0 0 +28 7 1 Fe-58 0 0 +29 7 1 Ni-58 0 0 +30 7 1 Ni-60 0 0 +31 7 1 Ni-61 0 0 +32 7 1 Ni-62 0 0 +33 7 1 Ni-64 0 0 +34 7 1 Mn-55 0 0 +35 7 1 Si-28 0 0 +36 7 1 Si-29 0 0 +37 7 1 Si-30 0 0 +38 7 1 Cr-50 0 0 +39 7 1 Cr-52 0 0 +40 7 1 Cr-53 0 0 +41 7 1 Cr-54 0 0 +0 7 2 H-1 0 0 +1 7 2 O-16 0 0 +2 7 2 B-10 0 0 +3 7 2 B-11 0 0 +4 7 2 Fe-54 0 0 +5 7 2 Fe-56 0 0 +6 7 2 Fe-57 0 0 +7 7 2 Fe-58 0 0 +8 7 2 Ni-58 0 0 +9 7 2 Ni-60 0 0 +10 7 2 Ni-61 0 0 +11 7 2 Ni-62 0 0 +12 7 2 Ni-64 0 0 +13 7 2 Mn-55 0 0 +14 7 2 Si-28 0 0 +15 7 2 Si-29 0 0 +16 7 2 Si-30 0 0 +17 7 2 Cr-50 0 0 +18 7 2 Cr-52 0 0 +19 7 2 Cr-53 0 0 +20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in group out nuclide moment mean +252 8 1 1 H-1 P0 0 +253 8 1 1 H-1 P1 0 +254 8 1 1 H-1 P2 0 +255 8 1 1 H-1 P3 0 +256 8 1 1 O-16 P0 0 +257 8 1 1 O-16 P1 0 +258 8 1 1 O-16 P2 0 +259 8 1 1 O-16 P3 0 +260 8 1 1 B-10 P0 0 +261 8 1 1 B-10 P1 0 +262 8 1 1 B-10 P2 0 +263 8 1 1 B-10 P3 0 +264 8 1 1 B-11 P0 0 +265 8 1 1 B-11 P1 0 +266 8 1 1 B-11 P2 0 +267 8 1 1 B-11 P3 0 +268 8 1 1 Fe-54 P0 0 +269 8 1 1 Fe-54 P1 0 +270 8 1 1 Fe-54 P2 0 +271 8 1 1 Fe-54 P3 0 +272 8 1 1 Fe-56 P0 0 +273 8 1 1 Fe-56 P1 0 +274 8 1 1 Fe-56 P2 0 +275 8 1 1 Fe-56 P3 0 +276 8 1 1 Fe-57 P0 0 +277 8 1 1 Fe-57 P1 0 +278 8 1 1 Fe-57 P2 0 +279 8 1 1 Fe-57 P3 0 +280 8 1 1 Fe-58 P0 0 +281 8 1 1 Fe-58 P1 0 +282 8 1 1 Fe-58 P2 0 +283 8 1 1 Fe-58 P3 0 +284 8 1 1 Ni-58 P0 0 +285 8 1 1 Ni-58 P1 0 +286 8 1 1 Ni-58 P2 0 +287 8 1 1 Ni-58 P3 0 +288 8 1 1 Ni-60 P0 0 +289 8 1 1 Ni-60 P1 0 +290 8 1 1 Ni-60 P2 0 +291 8 1 1 Ni-60 P3 0 +292 8 1 1 Ni-61 P0 0 +293 8 1 1 Ni-61 P1 0 +294 8 1 1 Ni-61 P2 0 +295 8 1 1 Ni-61 P3 0 +296 8 1 1 Ni-62 P0 0 +297 8 1 1 Ni-62 P1 0 +298 8 1 1 Ni-62 P2 0 +299 8 1 1 Ni-62 P3 0 +300 8 1 1 Ni-64 P0 0 +301 8 1 1 Ni-64 P1 0 +302 8 1 1 Ni-64 P2 0 +303 8 1 1 Ni-64 P3 0 +304 8 1 1 Mn-55 P0 0 +305 8 1 1 Mn-55 P1 0 +306 8 1 1 Mn-55 P2 0 +307 8 1 1 Mn-55 P3 0 +308 8 1 1 Si-28 P0 0 +309 8 1 1 Si-28 P1 0 +310 8 1 1 Si-28 P2 0 +311 8 1 1 Si-28 P3 0 +312 8 1 1 Si-29 P0 0 +313 8 1 1 Si-29 P1 0 +314 8 1 1 Si-29 P2 0 +315 8 1 1 Si-29 P3 0 +316 8 1 1 Si-30 P0 0 +317 8 1 1 Si-30 P1 0 +318 8 1 1 Si-30 P2 0 +319 8 1 1 Si-30 P3 0 +320 8 1 1 Cr-50 P0 0 +321 8 1 1 Cr-50 P1 0 +322 8 1 1 Cr-50 P2 0 +323 8 1 1 Cr-50 P3 0 +324 8 1 1 Cr-52 P0 0 +325 8 1 1 Cr-52 P1 0 +326 8 1 1 Cr-52 P2 0 +327 8 1 1 Cr-52 P3 0 +328 8 1 1 Cr-53 P0 0 +329 8 1 1 Cr-53 P1 0 +330 8 1 1 Cr-53 P2 0 +331 8 1 1 Cr-53 P3 0 +332 8 1 1 Cr-54 P0 0 +333 8 1 1 Cr-54 P1 0 +334 8 1 1 Cr-54 P2 0 +335 8 1 1 Cr-54 P3 0 +168 8 1 2 H-1 P0 0 +169 8 1 2 H-1 P1 0 +170 8 1 2 H-1 P2 0 +171 8 1 2 H-1 P3 0 +172 8 1 2 O-16 P0 0 +173 8 1 2 O-16 P1 0 +174 8 1 2 O-16 P2 0 +175 8 1 2 O-16 P3 0 +176 8 1 2 B-10 P0 0 +177 8 1 2 B-10 P1 0 +178 8 1 2 B-10 P2 0 +179 8 1 2 B-10 P3 0 +180 8 1 2 B-11 P0 0 +181 8 1 2 B-11 P1 0 +182 8 1 2 B-11 P2 0 +183 8 1 2 B-11 P3 0 +184 8 1 2 Fe-54 P0 0 +185 8 1 2 Fe-54 P1 0 +186 8 1 2 Fe-54 P2 0 +187 8 1 2 Fe-54 P3 0 +188 8 1 2 Fe-56 P0 0 +189 8 1 2 Fe-56 P1 0 +190 8 1 2 Fe-56 P2 0 +191 8 1 2 Fe-56 P3 0 +192 8 1 2 Fe-57 P0 0 +193 8 1 2 Fe-57 P1 0 +194 8 1 2 Fe-57 P2 0 +195 8 1 2 Fe-57 P3 0 +196 8 1 2 Fe-58 P0 0 +197 8 1 2 Fe-58 P1 0 +198 8 1 2 Fe-58 P2 0 +199 8 1 2 Fe-58 P3 0 +200 8 1 2 Ni-58 P0 0 +201 8 1 2 Ni-58 P1 0 +202 8 1 2 Ni-58 P2 0 +203 8 1 2 Ni-58 P3 0 +204 8 1 2 Ni-60 P0 0 +205 8 1 2 Ni-60 P1 0 +206 8 1 2 Ni-60 P2 0 +207 8 1 2 Ni-60 P3 0 +208 8 1 2 Ni-61 P0 0 +209 8 1 2 Ni-61 P1 0 +210 8 1 2 Ni-61 P2 0 +211 8 1 2 Ni-61 P3 0 +212 8 1 2 Ni-62 P0 0 +213 8 1 2 Ni-62 P1 0 +214 8 1 2 Ni-62 P2 0 +215 8 1 2 Ni-62 P3 0 +216 8 1 2 Ni-64 P0 0 +217 8 1 2 Ni-64 P1 0 +218 8 1 2 Ni-64 P2 0 +219 8 1 2 Ni-64 P3 0 +220 8 1 2 Mn-55 P0 0 +221 8 1 2 Mn-55 P1 0 +222 8 1 2 Mn-55 P2 0 +223 8 1 2 Mn-55 P3 0 +224 8 1 2 Si-28 P0 0 +225 8 1 2 Si-28 P1 0 +226 8 1 2 Si-28 P2 0 +227 8 1 2 Si-28 P3 0 +228 8 1 2 Si-29 P0 0 +229 8 1 2 Si-29 P1 0 +230 8 1 2 Si-29 P2 0 +231 8 1 2 Si-29 P3 0 +232 8 1 2 Si-30 P0 0 +233 8 1 2 Si-30 P1 0 +234 8 1 2 Si-30 P2 0 +235 8 1 2 Si-30 P3 0 +236 8 1 2 Cr-50 P0 0 +237 8 1 2 Cr-50 P1 0 +238 8 1 2 Cr-50 P2 0 +239 8 1 2 Cr-50 P3 0 +240 8 1 2 Cr-52 P0 0 +241 8 1 2 Cr-52 P1 0 +242 8 1 2 Cr-52 P2 0 +243 8 1 2 Cr-52 P3 0 +244 8 1 2 Cr-53 P0 0 +245 8 1 2 Cr-53 P1 0 +246 8 1 2 Cr-53 P2 0 +247 8 1 2 Cr-53 P3 0 +248 8 1 2 Cr-54 P0 0 +249 8 1 2 Cr-54 P1 0 +250 8 1 2 Cr-54 P2 0 +251 8 1 2 Cr-54 P3 0 +84 8 2 1 H-1 P0 0 +85 8 2 1 H-1 P1 0 +86 8 2 1 H-1 P2 0 +87 8 2 1 H-1 P3 0 +88 8 2 1 O-16 P0 0 +89 8 2 1 O-16 P1 0 +90 8 2 1 O-16 P2 0 +91 8 2 1 O-16 P3 0 +92 8 2 1 B-10 P0 0 +93 8 2 1 B-10 P1 0 +94 8 2 1 B-10 P2 0 +95 8 2 1 B-10 P3 0 +96 8 2 1 B-11 P0 0 +97 8 2 1 B-11 P1 0 +98 8 2 1 B-11 P2 0 +99 8 2 1 B-11 P3 0 +100 8 2 1 Fe-54 P0 0 +101 8 2 1 Fe-54 P1 0 +102 8 2 1 Fe-54 P2 0 +103 8 2 1 Fe-54 P3 0 +104 8 2 1 Fe-56 P0 0 +105 8 2 1 Fe-56 P1 0 +106 8 2 1 Fe-56 P2 0 +107 8 2 1 Fe-56 P3 0 +108 8 2 1 Fe-57 P0 0 +109 8 2 1 Fe-57 P1 0 +110 8 2 1 Fe-57 P2 0 +111 8 2 1 Fe-57 P3 0 +112 8 2 1 Fe-58 P0 0 +113 8 2 1 Fe-58 P1 0 +114 8 2 1 Fe-58 P2 0 +115 8 2 1 Fe-58 P3 0 +116 8 2 1 Ni-58 P0 0 +117 8 2 1 Ni-58 P1 0 +118 8 2 1 Ni-58 P2 0 +119 8 2 1 Ni-58 P3 0 +120 8 2 1 Ni-60 P0 0 +121 8 2 1 Ni-60 P1 0 +122 8 2 1 Ni-60 P2 0 +123 8 2 1 Ni-60 P3 0 +124 8 2 1 Ni-61 P0 0 +125 8 2 1 Ni-61 P1 0 +126 8 2 1 Ni-61 P2 0 +127 8 2 1 Ni-61 P3 0 +128 8 2 1 Ni-62 P0 0 +129 8 2 1 Ni-62 P1 0 +130 8 2 1 Ni-62 P2 0 +131 8 2 1 Ni-62 P3 0 +132 8 2 1 Ni-64 P0 0 +133 8 2 1 Ni-64 P1 0 +134 8 2 1 Ni-64 P2 0 +135 8 2 1 Ni-64 P3 0 +136 8 2 1 Mn-55 P0 0 +137 8 2 1 Mn-55 P1 0 +138 8 2 1 Mn-55 P2 0 +139 8 2 1 Mn-55 P3 0 +140 8 2 1 Si-28 P0 0 +141 8 2 1 Si-28 P1 0 +142 8 2 1 Si-28 P2 0 +143 8 2 1 Si-28 P3 0 +144 8 2 1 Si-29 P0 0 +145 8 2 1 Si-29 P1 0 +146 8 2 1 Si-29 P2 0 +147 8 2 1 Si-29 P3 0 +148 8 2 1 Si-30 P0 0 +149 8 2 1 Si-30 P1 0 +150 8 2 1 Si-30 P2 0 +151 8 2 1 Si-30 P3 0 +152 8 2 1 Cr-50 P0 0 +153 8 2 1 Cr-50 P1 0 +154 8 2 1 Cr-50 P2 0 +155 8 2 1 Cr-50 P3 0 +156 8 2 1 Cr-52 P0 0 +157 8 2 1 Cr-52 P1 0 +158 8 2 1 Cr-52 P2 0 +159 8 2 1 Cr-52 P3 0 +160 8 2 1 Cr-53 P0 0 +161 8 2 1 Cr-53 P1 0 +162 8 2 1 Cr-53 P2 0 +163 8 2 1 Cr-53 P3 0 +164 8 2 1 Cr-54 P0 0 +165 8 2 1 Cr-54 P1 0 +166 8 2 1 Cr-54 P2 0 +167 8 2 1 Cr-54 P3 0 +0 8 2 2 H-1 P0 0 +1 8 2 2 H-1 P1 0 +2 8 2 2 H-1 P2 0 +3 8 2 2 H-1 P3 0 +4 8 2 2 O-16 P0 0 +5 8 2 2 O-16 P1 0 +6 8 2 2 O-16 P2 0 +7 8 2 2 O-16 P3 0 +8 8 2 2 B-10 P0 0 +9 8 2 2 B-10 P1 0 +10 8 2 2 B-10 P2 0 +11 8 2 2 B-10 P3 0 +12 8 2 2 B-11 P0 0 +13 8 2 2 B-11 P1 0 +14 8 2 2 B-11 P2 0 +15 8 2 2 B-11 P3 0 +16 8 2 2 Fe-54 P0 0 +17 8 2 2 Fe-54 P1 0 +18 8 2 2 Fe-54 P2 0 +19 8 2 2 Fe-54 P3 0 +20 8 2 2 Fe-56 P0 0 +21 8 2 2 Fe-56 P1 0 +22 8 2 2 Fe-56 P2 0 +23 8 2 2 Fe-56 P3 0 +24 8 2 2 Fe-57 P0 0 +25 8 2 2 Fe-57 P1 0 +26 8 2 2 Fe-57 P2 0 +27 8 2 2 Fe-57 P3 0 +28 8 2 2 Fe-58 P0 0 +29 8 2 2 Fe-58 P1 0 +30 8 2 2 Fe-58 P2 0 +31 8 2 2 Fe-58 P3 0 +32 8 2 2 Ni-58 P0 0 +33 8 2 2 Ni-58 P1 0 +34 8 2 2 Ni-58 P2 0 +35 8 2 2 Ni-58 P3 0 +36 8 2 2 Ni-60 P0 0 +37 8 2 2 Ni-60 P1 0 +38 8 2 2 Ni-60 P2 0 +39 8 2 2 Ni-60 P3 0 +40 8 2 2 Ni-61 P0 0 +41 8 2 2 Ni-61 P1 0 +42 8 2 2 Ni-61 P2 0 +43 8 2 2 Ni-61 P3 0 +44 8 2 2 Ni-62 P0 0 +45 8 2 2 Ni-62 P1 0 +46 8 2 2 Ni-62 P2 0 +47 8 2 2 Ni-62 P3 0 +48 8 2 2 Ni-64 P0 0 +49 8 2 2 Ni-64 P1 0 +50 8 2 2 Ni-64 P2 0 +51 8 2 2 Ni-64 P3 0 +52 8 2 2 Mn-55 P0 0 +53 8 2 2 Mn-55 P1 0 +54 8 2 2 Mn-55 P2 0 +55 8 2 2 Mn-55 P3 0 +56 8 2 2 Si-28 P0 0 +57 8 2 2 Si-28 P1 0 +58 8 2 2 Si-28 P2 0 +59 8 2 2 Si-28 P3 0 +60 8 2 2 Si-29 P0 0 +61 8 2 2 Si-29 P1 0 +62 8 2 2 Si-29 P2 0 +63 8 2 2 Si-29 P3 0 +64 8 2 2 Si-30 P0 0 +65 8 2 2 Si-30 P1 0 +66 8 2 2 Si-30 P2 0 +67 8 2 2 Si-30 P3 0 +68 8 2 2 Cr-50 P0 0 +69 8 2 2 Cr-50 P1 0 +70 8 2 2 Cr-50 P2 0 +71 8 2 2 Cr-50 P3 0 +72 8 2 2 Cr-52 P0 0 +73 8 2 2 Cr-52 P1 0 +74 8 2 2 Cr-52 P2 0 +75 8 2 2 Cr-52 P3 0 +76 8 2 2 Cr-53 P0 0 +77 8 2 2 Cr-53 P1 0 +78 8 2 2 Cr-53 P2 0 +79 8 2 2 Cr-53 P3 0 +80 8 2 2 Cr-54 P0 0 +81 8 2 2 Cr-54 P1 0 +82 8 2 2 Cr-54 P2 0 +83 8 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. +21 8 1 H-1 0 0 +22 8 1 O-16 0 0 +23 8 1 B-10 0 0 +24 8 1 B-11 0 0 +25 8 1 Fe-54 0 0 +26 8 1 Fe-56 0 0 +27 8 1 Fe-57 0 0 +28 8 1 Fe-58 0 0 +29 8 1 Ni-58 0 0 +30 8 1 Ni-60 0 0 +31 8 1 Ni-61 0 0 +32 8 1 Ni-62 0 0 +33 8 1 Ni-64 0 0 +34 8 1 Mn-55 0 0 +35 8 1 Si-28 0 0 +36 8 1 Si-29 0 0 +37 8 1 Si-30 0 0 +38 8 1 Cr-50 0 0 +39 8 1 Cr-52 0 0 +40 8 1 Cr-53 0 0 +41 8 1 Cr-54 0 0 +0 8 2 H-1 0 0 +1 8 2 O-16 0 0 +2 8 2 B-10 0 0 +3 8 2 B-11 0 0 +4 8 2 Fe-54 0 0 +5 8 2 Fe-56 0 0 +6 8 2 Fe-57 0 0 +7 8 2 Fe-58 0 0 +8 8 2 Ni-58 0 0 +9 8 2 Ni-60 0 0 +10 8 2 Ni-61 0 0 +11 8 2 Ni-62 0 0 +12 8 2 Ni-64 0 0 +13 8 2 Mn-55 0 0 +14 8 2 Si-28 0 0 +15 8 2 Si-29 0 0 +16 8 2 Si-30 0 0 +17 8 2 Cr-50 0 0 +18 8 2 Cr-52 0 0 +19 8 2 Cr-53 0 0 +20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. 21 9 1 H-1 0.150655 0.480993 22 9 1 O-16 0.116221 0.114089 23 9 1 B-10 0.000000 0.000000 @@ -1411,174 +3055,426 @@ 18 9 2 Cr-52 0.000000 0.000000 19 9 2 Cr-53 0.000000 0.000000 20 9 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 9 1 H-1 0.0 0.0 -22 9 1 O-16 0.0 0.0 -23 9 1 B-10 0.0 0.0 -24 9 1 B-11 0.0 0.0 -25 9 1 Fe-54 0.0 0.0 -26 9 1 Fe-56 0.0 0.0 -27 9 1 Fe-57 0.0 0.0 -28 9 1 Fe-58 0.0 0.0 -29 9 1 Ni-58 0.0 0.0 -30 9 1 Ni-60 0.0 0.0 -31 9 1 Ni-61 0.0 0.0 -32 9 1 Ni-62 0.0 0.0 -33 9 1 Ni-64 0.0 0.0 -34 9 1 Mn-55 0.0 0.0 -35 9 1 Si-28 0.0 0.0 -36 9 1 Si-29 0.0 0.0 -37 9 1 Si-30 0.0 0.0 -38 9 1 Cr-50 0.0 0.0 -39 9 1 Cr-52 0.0 0.0 -40 9 1 Cr-53 0.0 0.0 -41 9 1 Cr-54 0.0 0.0 -0 9 2 H-1 0.0 0.0 -1 9 2 O-16 0.0 0.0 -2 9 2 B-10 0.0 0.0 -3 9 2 B-11 0.0 0.0 -4 9 2 Fe-54 0.0 0.0 -5 9 2 Fe-56 0.0 0.0 -6 9 2 Fe-57 0.0 0.0 -7 9 2 Fe-58 0.0 0.0 -8 9 2 Ni-58 0.0 0.0 -9 9 2 Ni-60 0.0 0.0 -10 9 2 Ni-61 0.0 0.0 -11 9 2 Ni-62 0.0 0.0 -12 9 2 Ni-64 0.0 0.0 -13 9 2 Mn-55 0.0 0.0 -14 9 2 Si-28 0.0 0.0 -15 9 2 Si-29 0.0 0.0 -16 9 2 Si-30 0.0 0.0 -17 9 2 Cr-50 0.0 0.0 -18 9 2 Cr-52 0.0 0.0 -19 9 2 Cr-53 0.0 0.0 -20 9 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 9 1 1 H-1 0.150655 0.480993 -64 9 1 1 O-16 0.116221 0.114089 -65 9 1 1 B-10 0.000000 0.000000 -66 9 1 1 B-11 0.000000 0.000000 -67 9 1 1 Fe-54 0.000000 0.000000 -68 9 1 1 Fe-56 0.186217 0.199795 -69 9 1 1 Fe-57 0.000000 0.000000 -70 9 1 1 Fe-58 0.000000 0.000000 -71 9 1 1 Ni-58 0.000000 0.000000 -72 9 1 1 Ni-60 0.000000 0.000000 -73 9 1 1 Ni-61 0.000000 0.000000 -74 9 1 1 Ni-62 0.000000 0.000000 -75 9 1 1 Ni-64 0.000000 0.000000 -76 9 1 1 Mn-55 0.000000 0.000000 -77 9 1 1 Si-28 0.000000 0.000000 -78 9 1 1 Si-29 0.000000 0.000000 -79 9 1 1 Si-30 0.000000 0.000000 -80 9 1 1 Cr-50 0.000000 0.000000 -81 9 1 1 Cr-52 0.000000 0.000000 -82 9 1 1 Cr-53 0.147443 0.139574 -83 9 1 1 Cr-54 0.000000 0.000000 -42 9 1 2 H-1 0.000000 0.000000 -43 9 1 2 O-16 0.000000 0.000000 -44 9 1 2 B-10 0.000000 0.000000 -45 9 1 2 B-11 0.000000 0.000000 -46 9 1 2 Fe-54 0.000000 0.000000 -47 9 1 2 Fe-56 0.000000 0.000000 -48 9 1 2 Fe-57 0.000000 0.000000 -49 9 1 2 Fe-58 0.000000 0.000000 -50 9 1 2 Ni-58 0.000000 0.000000 -51 9 1 2 Ni-60 0.000000 0.000000 -52 9 1 2 Ni-61 0.000000 0.000000 -53 9 1 2 Ni-62 0.000000 0.000000 -54 9 1 2 Ni-64 0.000000 0.000000 -55 9 1 2 Mn-55 0.000000 0.000000 -56 9 1 2 Si-28 0.000000 0.000000 -57 9 1 2 Si-29 0.000000 0.000000 -58 9 1 2 Si-30 0.000000 0.000000 -59 9 1 2 Cr-50 0.000000 0.000000 -60 9 1 2 Cr-52 0.000000 0.000000 -61 9 1 2 Cr-53 0.000000 0.000000 -62 9 1 2 Cr-54 0.000000 0.000000 -21 9 2 1 H-1 0.000000 0.000000 -22 9 2 1 O-16 0.000000 0.000000 -23 9 2 1 B-10 0.000000 0.000000 -24 9 2 1 B-11 0.000000 0.000000 -25 9 2 1 Fe-54 0.000000 0.000000 -26 9 2 1 Fe-56 0.000000 0.000000 -27 9 2 1 Fe-57 0.000000 0.000000 -28 9 2 1 Fe-58 0.000000 0.000000 -29 9 2 1 Ni-58 0.000000 0.000000 -30 9 2 1 Ni-60 0.000000 0.000000 -31 9 2 1 Ni-61 0.000000 0.000000 -32 9 2 1 Ni-62 0.000000 0.000000 -33 9 2 1 Ni-64 0.000000 0.000000 -34 9 2 1 Mn-55 0.000000 0.000000 -35 9 2 1 Si-28 0.000000 0.000000 -36 9 2 1 Si-29 0.000000 0.000000 -37 9 2 1 Si-30 0.000000 0.000000 -38 9 2 1 Cr-50 0.000000 0.000000 -39 9 2 1 Cr-52 0.000000 0.000000 -40 9 2 1 Cr-53 0.000000 0.000000 -41 9 2 1 Cr-54 0.000000 0.000000 -0 9 2 2 H-1 0.000000 0.000000 -1 9 2 2 O-16 0.000000 0.000000 -2 9 2 2 B-10 0.000000 0.000000 -3 9 2 2 B-11 0.000000 0.000000 -4 9 2 2 Fe-54 0.000000 0.000000 -5 9 2 2 Fe-56 0.000000 0.000000 -6 9 2 2 Fe-57 0.000000 0.000000 -7 9 2 2 Fe-58 0.000000 0.000000 -8 9 2 2 Ni-58 0.000000 0.000000 -9 9 2 2 Ni-60 0.000000 0.000000 -10 9 2 2 Ni-61 0.000000 0.000000 -11 9 2 2 Ni-62 0.000000 0.000000 -12 9 2 2 Ni-64 0.000000 0.000000 -13 9 2 2 Mn-55 0.000000 0.000000 -14 9 2 2 Si-28 0.000000 0.000000 -15 9 2 2 Si-29 0.000000 0.000000 -16 9 2 2 Si-30 0.000000 0.000000 -17 9 2 2 Cr-50 0.000000 0.000000 -18 9 2 2 Cr-52 0.000000 0.000000 -19 9 2 2 Cr-53 0.000000 0.000000 -20 9 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. -21 9 1 H-1 0.0 0.0 -22 9 1 O-16 0.0 0.0 -23 9 1 B-10 0.0 0.0 -24 9 1 B-11 0.0 0.0 -25 9 1 Fe-54 0.0 0.0 -26 9 1 Fe-56 0.0 0.0 -27 9 1 Fe-57 0.0 0.0 -28 9 1 Fe-58 0.0 0.0 -29 9 1 Ni-58 0.0 0.0 -30 9 1 Ni-60 0.0 0.0 -31 9 1 Ni-61 0.0 0.0 -32 9 1 Ni-62 0.0 0.0 -33 9 1 Ni-64 0.0 0.0 -34 9 1 Mn-55 0.0 0.0 -35 9 1 Si-28 0.0 0.0 -36 9 1 Si-29 0.0 0.0 -37 9 1 Si-30 0.0 0.0 -38 9 1 Cr-50 0.0 0.0 -39 9 1 Cr-52 0.0 0.0 -40 9 1 Cr-53 0.0 0.0 -41 9 1 Cr-54 0.0 0.0 -0 9 2 H-1 0.0 0.0 -1 9 2 O-16 0.0 0.0 -2 9 2 B-10 0.0 0.0 -3 9 2 B-11 0.0 0.0 -4 9 2 Fe-54 0.0 0.0 -5 9 2 Fe-56 0.0 0.0 -6 9 2 Fe-57 0.0 0.0 -7 9 2 Fe-58 0.0 0.0 -8 9 2 Ni-58 0.0 0.0 -9 9 2 Ni-60 0.0 0.0 -10 9 2 Ni-61 0.0 0.0 -11 9 2 Ni-62 0.0 0.0 -12 9 2 Ni-64 0.0 0.0 -13 9 2 Mn-55 0.0 0.0 -14 9 2 Si-28 0.0 0.0 -15 9 2 Si-29 0.0 0.0 -16 9 2 Si-30 0.0 0.0 -17 9 2 Cr-50 0.0 0.0 -18 9 2 Cr-52 0.0 0.0 -19 9 2 Cr-53 0.0 0.0 -20 9 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 9 1 H-1 0 0 +22 9 1 O-16 0 0 +23 9 1 B-10 0 0 +24 9 1 B-11 0 0 +25 9 1 Fe-54 0 0 +26 9 1 Fe-56 0 0 +27 9 1 Fe-57 0 0 +28 9 1 Fe-58 0 0 +29 9 1 Ni-58 0 0 +30 9 1 Ni-60 0 0 +31 9 1 Ni-61 0 0 +32 9 1 Ni-62 0 0 +33 9 1 Ni-64 0 0 +34 9 1 Mn-55 0 0 +35 9 1 Si-28 0 0 +36 9 1 Si-29 0 0 +37 9 1 Si-30 0 0 +38 9 1 Cr-50 0 0 +39 9 1 Cr-52 0 0 +40 9 1 Cr-53 0 0 +41 9 1 Cr-54 0 0 +0 9 2 H-1 0 0 +1 9 2 O-16 0 0 +2 9 2 B-10 0 0 +3 9 2 B-11 0 0 +4 9 2 Fe-54 0 0 +5 9 2 Fe-56 0 0 +6 9 2 Fe-57 0 0 +7 9 2 Fe-58 0 0 +8 9 2 Ni-58 0 0 +9 9 2 Ni-60 0 0 +10 9 2 Ni-61 0 0 +11 9 2 Ni-62 0 0 +12 9 2 Ni-64 0 0 +13 9 2 Mn-55 0 0 +14 9 2 Si-28 0 0 +15 9 2 Si-29 0 0 +16 9 2 Si-30 0 0 +17 9 2 Cr-50 0 0 +18 9 2 Cr-52 0 0 +19 9 2 Cr-53 0 0 +20 9 2 Cr-54 0 0 material group in group out nuclide moment mean +252 9 1 1 H-1 P0 0.400211 +253 9 1 1 H-1 P1 0.249556 +254 9 1 1 H-1 P2 0.082049 +255 9 1 1 H-1 P3 0.001559 +256 9 1 1 O-16 P0 0.080042 +257 9 1 1 O-16 P1 -0.036179 +258 9 1 1 O-16 P2 -0.015492 +259 9 1 1 O-16 P3 0.035790 +260 9 1 1 B-10 P0 0.000000 +261 9 1 1 B-10 P1 0.000000 +262 9 1 1 B-10 P2 0.000000 +263 9 1 1 B-10 P3 0.000000 +264 9 1 1 B-11 P0 0.000000 +265 9 1 1 B-11 P1 0.000000 +266 9 1 1 B-11 P2 0.000000 +267 9 1 1 B-11 P3 0.000000 +268 9 1 1 Fe-54 P0 0.000000 +269 9 1 1 Fe-54 P1 0.000000 +270 9 1 1 Fe-54 P2 0.000000 +271 9 1 1 Fe-54 P3 0.000000 +272 9 1 1 Fe-56 P0 0.160084 +273 9 1 1 Fe-56 P1 -0.026133 +274 9 1 1 Fe-56 P2 -0.073149 +275 9 1 1 Fe-56 P3 0.037054 +276 9 1 1 Fe-57 P0 0.000000 +277 9 1 1 Fe-57 P1 0.000000 +278 9 1 1 Fe-57 P2 0.000000 +279 9 1 1 Fe-57 P3 0.000000 +280 9 1 1 Fe-58 P0 0.000000 +281 9 1 1 Fe-58 P1 0.000000 +282 9 1 1 Fe-58 P2 0.000000 +283 9 1 1 Fe-58 P3 0.000000 +284 9 1 1 Ni-58 P0 0.000000 +285 9 1 1 Ni-58 P1 0.000000 +286 9 1 1 Ni-58 P2 0.000000 +287 9 1 1 Ni-58 P3 0.000000 +288 9 1 1 Ni-60 P0 0.000000 +289 9 1 1 Ni-60 P1 0.000000 +290 9 1 1 Ni-60 P2 0.000000 +291 9 1 1 Ni-60 P3 0.000000 +292 9 1 1 Ni-61 P0 0.000000 +293 9 1 1 Ni-61 P1 0.000000 +294 9 1 1 Ni-61 P2 0.000000 +295 9 1 1 Ni-61 P3 0.000000 +296 9 1 1 Ni-62 P0 0.000000 +297 9 1 1 Ni-62 P1 0.000000 +298 9 1 1 Ni-62 P2 0.000000 +299 9 1 1 Ni-62 P3 0.000000 +300 9 1 1 Ni-64 P0 0.000000 +301 9 1 1 Ni-64 P1 0.000000 +302 9 1 1 Ni-64 P2 0.000000 +303 9 1 1 Ni-64 P3 0.000000 +304 9 1 1 Mn-55 P0 0.000000 +305 9 1 1 Mn-55 P1 0.000000 +306 9 1 1 Mn-55 P2 0.000000 +307 9 1 1 Mn-55 P3 0.000000 +308 9 1 1 Si-28 P0 0.000000 +309 9 1 1 Si-28 P1 0.000000 +310 9 1 1 Si-28 P2 0.000000 +311 9 1 1 Si-28 P3 0.000000 +312 9 1 1 Si-29 P0 0.000000 +313 9 1 1 Si-29 P1 0.000000 +314 9 1 1 Si-29 P2 0.000000 +315 9 1 1 Si-29 P3 0.000000 +316 9 1 1 Si-30 P0 0.000000 +317 9 1 1 Si-30 P1 0.000000 +318 9 1 1 Si-30 P2 0.000000 +319 9 1 1 Si-30 P3 0.000000 +320 9 1 1 Cr-50 P0 0.000000 +321 9 1 1 Cr-50 P1 0.000000 +322 9 1 1 Cr-50 P2 0.000000 +323 9 1 1 Cr-50 P3 0.000000 +324 9 1 1 Cr-52 P0 0.000000 +325 9 1 1 Cr-52 P1 0.000000 +326 9 1 1 Cr-52 P2 0.000000 +327 9 1 1 Cr-52 P3 0.000000 +328 9 1 1 Cr-53 P0 0.080042 +329 9 1 1 Cr-53 P1 -0.067401 +330 9 1 1 Cr-53 P2 0.045113 +331 9 1 1 Cr-53 P3 -0.018380 +332 9 1 1 Cr-54 P0 0.000000 +333 9 1 1 Cr-54 P1 0.000000 +334 9 1 1 Cr-54 P2 0.000000 +335 9 1 1 Cr-54 P3 0.000000 +168 9 1 2 H-1 P0 0.000000 +169 9 1 2 H-1 P1 0.000000 +170 9 1 2 H-1 P2 0.000000 +171 9 1 2 H-1 P3 0.000000 +172 9 1 2 O-16 P0 0.000000 +173 9 1 2 O-16 P1 0.000000 +174 9 1 2 O-16 P2 0.000000 +175 9 1 2 O-16 P3 0.000000 +176 9 1 2 B-10 P0 0.000000 +177 9 1 2 B-10 P1 0.000000 +178 9 1 2 B-10 P2 0.000000 +179 9 1 2 B-10 P3 0.000000 +180 9 1 2 B-11 P0 0.000000 +181 9 1 2 B-11 P1 0.000000 +182 9 1 2 B-11 P2 0.000000 +183 9 1 2 B-11 P3 0.000000 +184 9 1 2 Fe-54 P0 0.000000 +185 9 1 2 Fe-54 P1 0.000000 +186 9 1 2 Fe-54 P2 0.000000 +187 9 1 2 Fe-54 P3 0.000000 +188 9 1 2 Fe-56 P0 0.000000 +189 9 1 2 Fe-56 P1 0.000000 +190 9 1 2 Fe-56 P2 0.000000 +191 9 1 2 Fe-56 P3 0.000000 +192 9 1 2 Fe-57 P0 0.000000 +193 9 1 2 Fe-57 P1 0.000000 +194 9 1 2 Fe-57 P2 0.000000 +195 9 1 2 Fe-57 P3 0.000000 +196 9 1 2 Fe-58 P0 0.000000 +197 9 1 2 Fe-58 P1 0.000000 +198 9 1 2 Fe-58 P2 0.000000 +199 9 1 2 Fe-58 P3 0.000000 +200 9 1 2 Ni-58 P0 0.000000 +201 9 1 2 Ni-58 P1 0.000000 +202 9 1 2 Ni-58 P2 0.000000 +203 9 1 2 Ni-58 P3 0.000000 +204 9 1 2 Ni-60 P0 0.000000 +205 9 1 2 Ni-60 P1 0.000000 +206 9 1 2 Ni-60 P2 0.000000 +207 9 1 2 Ni-60 P3 0.000000 +208 9 1 2 Ni-61 P0 0.000000 +209 9 1 2 Ni-61 P1 0.000000 +210 9 1 2 Ni-61 P2 0.000000 +211 9 1 2 Ni-61 P3 0.000000 +212 9 1 2 Ni-62 P0 0.000000 +213 9 1 2 Ni-62 P1 0.000000 +214 9 1 2 Ni-62 P2 0.000000 +215 9 1 2 Ni-62 P3 0.000000 +216 9 1 2 Ni-64 P0 0.000000 +217 9 1 2 Ni-64 P1 0.000000 +218 9 1 2 Ni-64 P2 0.000000 +219 9 1 2 Ni-64 P3 0.000000 +220 9 1 2 Mn-55 P0 0.000000 +221 9 1 2 Mn-55 P1 0.000000 +222 9 1 2 Mn-55 P2 0.000000 +223 9 1 2 Mn-55 P3 0.000000 +224 9 1 2 Si-28 P0 0.000000 +225 9 1 2 Si-28 P1 0.000000 +226 9 1 2 Si-28 P2 0.000000 +227 9 1 2 Si-28 P3 0.000000 +228 9 1 2 Si-29 P0 0.000000 +229 9 1 2 Si-29 P1 0.000000 +230 9 1 2 Si-29 P2 0.000000 +231 9 1 2 Si-29 P3 0.000000 +232 9 1 2 Si-30 P0 0.000000 +233 9 1 2 Si-30 P1 0.000000 +234 9 1 2 Si-30 P2 0.000000 +235 9 1 2 Si-30 P3 0.000000 +236 9 1 2 Cr-50 P0 0.000000 +237 9 1 2 Cr-50 P1 0.000000 +238 9 1 2 Cr-50 P2 0.000000 +239 9 1 2 Cr-50 P3 0.000000 +240 9 1 2 Cr-52 P0 0.000000 +241 9 1 2 Cr-52 P1 0.000000 +242 9 1 2 Cr-52 P2 0.000000 +243 9 1 2 Cr-52 P3 0.000000 +244 9 1 2 Cr-53 P0 0.000000 +245 9 1 2 Cr-53 P1 0.000000 +246 9 1 2 Cr-53 P2 0.000000 +247 9 1 2 Cr-53 P3 0.000000 +248 9 1 2 Cr-54 P0 0.000000 +249 9 1 2 Cr-54 P1 0.000000 +250 9 1 2 Cr-54 P2 0.000000 +251 9 1 2 Cr-54 P3 0.000000 +84 9 2 1 H-1 P0 0.000000 +85 9 2 1 H-1 P1 0.000000 +86 9 2 1 H-1 P2 0.000000 +87 9 2 1 H-1 P3 0.000000 +88 9 2 1 O-16 P0 0.000000 +89 9 2 1 O-16 P1 0.000000 +90 9 2 1 O-16 P2 0.000000 +91 9 2 1 O-16 P3 0.000000 +92 9 2 1 B-10 P0 0.000000 +93 9 2 1 B-10 P1 0.000000 +94 9 2 1 B-10 P2 0.000000 +95 9 2 1 B-10 P3 0.000000 +96 9 2 1 B-11 P0 0.000000 +97 9 2 1 B-11 P1 0.000000 +98 9 2 1 B-11 P2 0.000000 +99 9 2 1 B-11 P3 0.000000 +100 9 2 1 Fe-54 P0 0.000000 +101 9 2 1 Fe-54 P1 0.000000 +102 9 2 1 Fe-54 P2 0.000000 +103 9 2 1 Fe-54 P3 0.000000 +104 9 2 1 Fe-56 P0 0.000000 +105 9 2 1 Fe-56 P1 0.000000 +106 9 2 1 Fe-56 P2 0.000000 +107 9 2 1 Fe-56 P3 0.000000 +108 9 2 1 Fe-57 P0 0.000000 +109 9 2 1 Fe-57 P1 0.000000 +110 9 2 1 Fe-57 P2 0.000000 +111 9 2 1 Fe-57 P3 0.000000 +112 9 2 1 Fe-58 P0 0.000000 +113 9 2 1 Fe-58 P1 0.000000 +114 9 2 1 Fe-58 P2 0.000000 +115 9 2 1 Fe-58 P3 0.000000 +116 9 2 1 Ni-58 P0 0.000000 +117 9 2 1 Ni-58 P1 0.000000 +118 9 2 1 Ni-58 P2 0.000000 +119 9 2 1 Ni-58 P3 0.000000 +120 9 2 1 Ni-60 P0 0.000000 +121 9 2 1 Ni-60 P1 0.000000 +122 9 2 1 Ni-60 P2 0.000000 +123 9 2 1 Ni-60 P3 0.000000 +124 9 2 1 Ni-61 P0 0.000000 +125 9 2 1 Ni-61 P1 0.000000 +126 9 2 1 Ni-61 P2 0.000000 +127 9 2 1 Ni-61 P3 0.000000 +128 9 2 1 Ni-62 P0 0.000000 +129 9 2 1 Ni-62 P1 0.000000 +130 9 2 1 Ni-62 P2 0.000000 +131 9 2 1 Ni-62 P3 0.000000 +132 9 2 1 Ni-64 P0 0.000000 +133 9 2 1 Ni-64 P1 0.000000 +134 9 2 1 Ni-64 P2 0.000000 +135 9 2 1 Ni-64 P3 0.000000 +136 9 2 1 Mn-55 P0 0.000000 +137 9 2 1 Mn-55 P1 0.000000 +138 9 2 1 Mn-55 P2 0.000000 +139 9 2 1 Mn-55 P3 0.000000 +140 9 2 1 Si-28 P0 0.000000 +141 9 2 1 Si-28 P1 0.000000 +142 9 2 1 Si-28 P2 0.000000 +143 9 2 1 Si-28 P3 0.000000 +144 9 2 1 Si-29 P0 0.000000 +145 9 2 1 Si-29 P1 0.000000 +146 9 2 1 Si-29 P2 0.000000 +147 9 2 1 Si-29 P3 0.000000 +148 9 2 1 Si-30 P0 0.000000 +149 9 2 1 Si-30 P1 0.000000 +150 9 2 1 Si-30 P2 0.000000 +151 9 2 1 Si-30 P3 0.000000 +152 9 2 1 Cr-50 P0 0.000000 +153 9 2 1 Cr-50 P1 0.000000 +154 9 2 1 Cr-50 P2 0.000000 +155 9 2 1 Cr-50 P3 0.000000 +156 9 2 1 Cr-52 P0 0.000000 +157 9 2 1 Cr-52 P1 0.000000 +158 9 2 1 Cr-52 P2 0.000000 +159 9 2 1 Cr-52 P3 0.000000 +160 9 2 1 Cr-53 P0 0.000000 +161 9 2 1 Cr-53 P1 0.000000 +162 9 2 1 Cr-53 P2 0.000000 +163 9 2 1 Cr-53 P3 0.000000 +164 9 2 1 Cr-54 P0 0.000000 +165 9 2 1 Cr-54 P1 0.000000 +166 9 2 1 Cr-54 P2 0.000000 +167 9 2 1 Cr-54 P3 0.000000 +0 9 2 2 H-1 P0 0.000000 +1 9 2 2 H-1 P1 0.000000 +2 9 2 2 H-1 P2 0.000000 +3 9 2 2 H-1 P3 0.000000 +4 9 2 2 O-16 P0 0.000000 +5 9 2 2 O-16 P1 0.000000 +6 9 2 2 O-16 P2 0.000000 +7 9 2 2 O-16 P3 0.000000 +8 9 2 2 B-10 P0 0.000000 +9 9 2 2 B-10 P1 0.000000 +10 9 2 2 B-10 P2 0.000000 +11 9 2 2 B-10 P3 0.000000 +12 9 2 2 B-11 P0 0.000000 +13 9 2 2 B-11 P1 0.000000 +14 9 2 2 B-11 P2 0.000000 +15 9 2 2 B-11 P3 0.000000 +16 9 2 2 Fe-54 P0 0.000000 +17 9 2 2 Fe-54 P1 0.000000 +18 9 2 2 Fe-54 P2 0.000000 +19 9 2 2 Fe-54 P3 0.000000 +20 9 2 2 Fe-56 P0 0.000000 +21 9 2 2 Fe-56 P1 0.000000 +22 9 2 2 Fe-56 P2 0.000000 +23 9 2 2 Fe-56 P3 0.000000 +24 9 2 2 Fe-57 P0 0.000000 +25 9 2 2 Fe-57 P1 0.000000 +26 9 2 2 Fe-57 P2 0.000000 +27 9 2 2 Fe-57 P3 0.000000 +28 9 2 2 Fe-58 P0 0.000000 +29 9 2 2 Fe-58 P1 0.000000 +30 9 2 2 Fe-58 P2 0.000000 +31 9 2 2 Fe-58 P3 0.000000 +32 9 2 2 Ni-58 P0 0.000000 +33 9 2 2 Ni-58 P1 0.000000 +34 9 2 2 Ni-58 P2 0.000000 +35 9 2 2 Ni-58 P3 0.000000 +36 9 2 2 Ni-60 P0 0.000000 +37 9 2 2 Ni-60 P1 0.000000 +38 9 2 2 Ni-60 P2 0.000000 +39 9 2 2 Ni-60 P3 0.000000 +40 9 2 2 Ni-61 P0 0.000000 +41 9 2 2 Ni-61 P1 0.000000 +42 9 2 2 Ni-61 P2 0.000000 +43 9 2 2 Ni-61 P3 0.000000 +44 9 2 2 Ni-62 P0 0.000000 +45 9 2 2 Ni-62 P1 0.000000 +46 9 2 2 Ni-62 P2 0.000000 +47 9 2 2 Ni-62 P3 0.000000 +48 9 2 2 Ni-64 P0 0.000000 +49 9 2 2 Ni-64 P1 0.000000 +50 9 2 2 Ni-64 P2 0.000000 +51 9 2 2 Ni-64 P3 0.000000 +52 9 2 2 Mn-55 P0 0.000000 +53 9 2 2 Mn-55 P1 0.000000 +54 9 2 2 Mn-55 P2 0.000000 +55 9 2 2 Mn-55 P3 0.000000 +56 9 2 2 Si-28 P0 0.000000 +57 9 2 2 Si-28 P1 0.000000 +58 9 2 2 Si-28 P2 0.000000 +59 9 2 2 Si-28 P3 0.000000 +60 9 2 2 Si-29 P0 0.000000 +61 9 2 2 Si-29 P1 0.000000 +62 9 2 2 Si-29 P2 0.000000 +63 9 2 2 Si-29 P3 0.000000 +64 9 2 2 Si-30 P0 0.000000 +65 9 2 2 Si-30 P1 0.000000 +66 9 2 2 Si-30 P2 0.000000 +67 9 2 2 Si-30 P3 0.000000 +68 9 2 2 Cr-50 P0 0.000000 +69 9 2 2 Cr-50 P1 0.000000 +70 9 2 2 Cr-50 P2 0.000000 +71 9 2 2 Cr-50 P3 0.000000 +72 9 2 2 Cr-52 P0 0.000000 +73 9 2 2 Cr-52 P1 0.000000 +74 9 2 2 Cr-52 P2 0.000000 +75 9 2 2 Cr-52 P3 0.000000 +76 9 2 2 Cr-53 P0 0.000000 +77 9 2 2 Cr-53 P1 0.000000 +78 9 2 2 Cr-53 P2 0.000000 +79 9 2 2 Cr-53 P3 0.000000 +80 9 2 2 Cr-54 P0 0.000000 +81 9 2 2 Cr-54 P1 0.000000 +82 9 2 2 Cr-54 P2 0.000000 +83 9 2 2 Cr-54 P3 0.000000 material group out nuclide mean std. dev. +21 9 1 H-1 0 0 +22 9 1 O-16 0 0 +23 9 1 B-10 0 0 +24 9 1 B-11 0 0 +25 9 1 Fe-54 0 0 +26 9 1 Fe-56 0 0 +27 9 1 Fe-57 0 0 +28 9 1 Fe-58 0 0 +29 9 1 Ni-58 0 0 +30 9 1 Ni-60 0 0 +31 9 1 Ni-61 0 0 +32 9 1 Ni-62 0 0 +33 9 1 Ni-64 0 0 +34 9 1 Mn-55 0 0 +35 9 1 Si-28 0 0 +36 9 1 Si-29 0 0 +37 9 1 Si-30 0 0 +38 9 1 Cr-50 0 0 +39 9 1 Cr-52 0 0 +40 9 1 Cr-53 0 0 +41 9 1 Cr-54 0 0 +0 9 2 H-1 0 0 +1 9 2 O-16 0 0 +2 9 2 B-10 0 0 +3 9 2 B-11 0 0 +4 9 2 Fe-54 0 0 +5 9 2 Fe-56 0 0 +6 9 2 Fe-57 0 0 +7 9 2 Fe-58 0 0 +8 9 2 Ni-58 0 0 +9 9 2 Ni-60 0 0 +10 9 2 Ni-61 0 0 +11 9 2 Ni-62 0 0 +12 9 2 Ni-64 0 0 +13 9 2 Mn-55 0 0 +14 9 2 Si-28 0 0 +15 9 2 Si-29 0 0 +16 9 2 Si-30 0 0 +17 9 2 Cr-50 0 0 +18 9 2 Cr-52 0 0 +19 9 2 Cr-53 0 0 +20 9 2 Cr-54 0 0 material group in nuclide mean std. dev. 21 10 1 H-1 0.123944 0.541390 22 10 1 O-16 0.000000 0.000000 23 10 1 B-10 0.000000 0.000000 @@ -1621,174 +3517,426 @@ 18 10 2 Cr-52 0.000000 0.000000 19 10 2 Cr-53 0.000000 0.000000 20 10 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 10 1 H-1 0.0 0.0 -22 10 1 O-16 0.0 0.0 -23 10 1 B-10 0.0 0.0 -24 10 1 B-11 0.0 0.0 -25 10 1 Fe-54 0.0 0.0 -26 10 1 Fe-56 0.0 0.0 -27 10 1 Fe-57 0.0 0.0 -28 10 1 Fe-58 0.0 0.0 -29 10 1 Ni-58 0.0 0.0 -30 10 1 Ni-60 0.0 0.0 -31 10 1 Ni-61 0.0 0.0 -32 10 1 Ni-62 0.0 0.0 -33 10 1 Ni-64 0.0 0.0 -34 10 1 Mn-55 0.0 0.0 -35 10 1 Si-28 0.0 0.0 -36 10 1 Si-29 0.0 0.0 -37 10 1 Si-30 0.0 0.0 -38 10 1 Cr-50 0.0 0.0 -39 10 1 Cr-52 0.0 0.0 -40 10 1 Cr-53 0.0 0.0 -41 10 1 Cr-54 0.0 0.0 -0 10 2 H-1 0.0 0.0 -1 10 2 O-16 0.0 0.0 -2 10 2 B-10 0.0 0.0 -3 10 2 B-11 0.0 0.0 -4 10 2 Fe-54 0.0 0.0 -5 10 2 Fe-56 0.0 0.0 -6 10 2 Fe-57 0.0 0.0 -7 10 2 Fe-58 0.0 0.0 -8 10 2 Ni-58 0.0 0.0 -9 10 2 Ni-60 0.0 0.0 -10 10 2 Ni-61 0.0 0.0 -11 10 2 Ni-62 0.0 0.0 -12 10 2 Ni-64 0.0 0.0 -13 10 2 Mn-55 0.0 0.0 -14 10 2 Si-28 0.0 0.0 -15 10 2 Si-29 0.0 0.0 -16 10 2 Si-30 0.0 0.0 -17 10 2 Cr-50 0.0 0.0 -18 10 2 Cr-52 0.0 0.0 -19 10 2 Cr-53 0.0 0.0 -20 10 2 Cr-54 0.0 0.0 material group in group out nuclide mean std. dev. -63 10 1 1 H-1 0.123944 0.541390 -64 10 1 1 O-16 0.000000 0.000000 -65 10 1 1 B-10 0.000000 0.000000 -66 10 1 1 B-11 0.000000 0.000000 -67 10 1 1 Fe-54 0.000000 0.000000 -68 10 1 1 Fe-56 0.000000 0.000000 -69 10 1 1 Fe-57 0.000000 0.000000 -70 10 1 1 Fe-58 0.000000 0.000000 -71 10 1 1 Ni-58 0.000000 0.000000 -72 10 1 1 Ni-60 0.000000 0.000000 -73 10 1 1 Ni-61 0.000000 0.000000 -74 10 1 1 Ni-62 0.000000 0.000000 -75 10 1 1 Ni-64 0.000000 0.000000 -76 10 1 1 Mn-55 0.000000 0.000000 -77 10 1 1 Si-28 0.000000 0.000000 -78 10 1 1 Si-29 0.000000 0.000000 -79 10 1 1 Si-30 0.000000 0.000000 -80 10 1 1 Cr-50 0.111571 0.138458 -81 10 1 1 Cr-52 0.000000 0.000000 -82 10 1 1 Cr-53 0.000000 0.000000 -83 10 1 1 Cr-54 0.000000 0.000000 -42 10 1 2 H-1 0.000000 0.000000 -43 10 1 2 O-16 0.000000 0.000000 -44 10 1 2 B-10 0.000000 0.000000 -45 10 1 2 B-11 0.000000 0.000000 -46 10 1 2 Fe-54 0.000000 0.000000 -47 10 1 2 Fe-56 0.000000 0.000000 -48 10 1 2 Fe-57 0.000000 0.000000 -49 10 1 2 Fe-58 0.000000 0.000000 -50 10 1 2 Ni-58 0.000000 0.000000 -51 10 1 2 Ni-60 0.000000 0.000000 -52 10 1 2 Ni-61 0.000000 0.000000 -53 10 1 2 Ni-62 0.000000 0.000000 -54 10 1 2 Ni-64 0.000000 0.000000 -55 10 1 2 Mn-55 0.000000 0.000000 -56 10 1 2 Si-28 0.000000 0.000000 -57 10 1 2 Si-29 0.000000 0.000000 -58 10 1 2 Si-30 0.000000 0.000000 -59 10 1 2 Cr-50 0.000000 0.000000 -60 10 1 2 Cr-52 0.000000 0.000000 -61 10 1 2 Cr-53 0.000000 0.000000 -62 10 1 2 Cr-54 0.000000 0.000000 -21 10 2 1 H-1 0.000000 0.000000 -22 10 2 1 O-16 0.000000 0.000000 -23 10 2 1 B-10 0.000000 0.000000 -24 10 2 1 B-11 0.000000 0.000000 -25 10 2 1 Fe-54 0.000000 0.000000 -26 10 2 1 Fe-56 0.000000 0.000000 -27 10 2 1 Fe-57 0.000000 0.000000 -28 10 2 1 Fe-58 0.000000 0.000000 -29 10 2 1 Ni-58 0.000000 0.000000 -30 10 2 1 Ni-60 0.000000 0.000000 -31 10 2 1 Ni-61 0.000000 0.000000 -32 10 2 1 Ni-62 0.000000 0.000000 -33 10 2 1 Ni-64 0.000000 0.000000 -34 10 2 1 Mn-55 0.000000 0.000000 -35 10 2 1 Si-28 0.000000 0.000000 -36 10 2 1 Si-29 0.000000 0.000000 -37 10 2 1 Si-30 0.000000 0.000000 -38 10 2 1 Cr-50 0.000000 0.000000 -39 10 2 1 Cr-52 0.000000 0.000000 -40 10 2 1 Cr-53 0.000000 0.000000 -41 10 2 1 Cr-54 0.000000 0.000000 -0 10 2 2 H-1 0.000000 0.000000 -1 10 2 2 O-16 0.000000 0.000000 -2 10 2 2 B-10 0.000000 0.000000 -3 10 2 2 B-11 0.000000 0.000000 -4 10 2 2 Fe-54 0.000000 0.000000 -5 10 2 2 Fe-56 0.000000 0.000000 -6 10 2 2 Fe-57 0.000000 0.000000 -7 10 2 2 Fe-58 0.000000 0.000000 -8 10 2 2 Ni-58 0.000000 0.000000 -9 10 2 2 Ni-60 0.000000 0.000000 -10 10 2 2 Ni-61 0.000000 0.000000 -11 10 2 2 Ni-62 0.000000 0.000000 -12 10 2 2 Ni-64 0.000000 0.000000 -13 10 2 2 Mn-55 0.000000 0.000000 -14 10 2 2 Si-28 0.000000 0.000000 -15 10 2 2 Si-29 0.000000 0.000000 -16 10 2 2 Si-30 0.000000 0.000000 -17 10 2 2 Cr-50 0.000000 0.000000 -18 10 2 2 Cr-52 0.000000 0.000000 -19 10 2 2 Cr-53 0.000000 0.000000 -20 10 2 2 Cr-54 0.000000 0.000000 material group out nuclide mean std. dev. -21 10 1 H-1 0.0 0.0 -22 10 1 O-16 0.0 0.0 -23 10 1 B-10 0.0 0.0 -24 10 1 B-11 0.0 0.0 -25 10 1 Fe-54 0.0 0.0 -26 10 1 Fe-56 0.0 0.0 -27 10 1 Fe-57 0.0 0.0 -28 10 1 Fe-58 0.0 0.0 -29 10 1 Ni-58 0.0 0.0 -30 10 1 Ni-60 0.0 0.0 -31 10 1 Ni-61 0.0 0.0 -32 10 1 Ni-62 0.0 0.0 -33 10 1 Ni-64 0.0 0.0 -34 10 1 Mn-55 0.0 0.0 -35 10 1 Si-28 0.0 0.0 -36 10 1 Si-29 0.0 0.0 -37 10 1 Si-30 0.0 0.0 -38 10 1 Cr-50 0.0 0.0 -39 10 1 Cr-52 0.0 0.0 -40 10 1 Cr-53 0.0 0.0 -41 10 1 Cr-54 0.0 0.0 -0 10 2 H-1 0.0 0.0 -1 10 2 O-16 0.0 0.0 -2 10 2 B-10 0.0 0.0 -3 10 2 B-11 0.0 0.0 -4 10 2 Fe-54 0.0 0.0 -5 10 2 Fe-56 0.0 0.0 -6 10 2 Fe-57 0.0 0.0 -7 10 2 Fe-58 0.0 0.0 -8 10 2 Ni-58 0.0 0.0 -9 10 2 Ni-60 0.0 0.0 -10 10 2 Ni-61 0.0 0.0 -11 10 2 Ni-62 0.0 0.0 -12 10 2 Ni-64 0.0 0.0 -13 10 2 Mn-55 0.0 0.0 -14 10 2 Si-28 0.0 0.0 -15 10 2 Si-29 0.0 0.0 -16 10 2 Si-30 0.0 0.0 -17 10 2 Cr-50 0.0 0.0 -18 10 2 Cr-52 0.0 0.0 -19 10 2 Cr-53 0.0 0.0 -20 10 2 Cr-54 0.0 0.0 material group in nuclide mean std. dev. +21 10 1 H-1 0 0 +22 10 1 O-16 0 0 +23 10 1 B-10 0 0 +24 10 1 B-11 0 0 +25 10 1 Fe-54 0 0 +26 10 1 Fe-56 0 0 +27 10 1 Fe-57 0 0 +28 10 1 Fe-58 0 0 +29 10 1 Ni-58 0 0 +30 10 1 Ni-60 0 0 +31 10 1 Ni-61 0 0 +32 10 1 Ni-62 0 0 +33 10 1 Ni-64 0 0 +34 10 1 Mn-55 0 0 +35 10 1 Si-28 0 0 +36 10 1 Si-29 0 0 +37 10 1 Si-30 0 0 +38 10 1 Cr-50 0 0 +39 10 1 Cr-52 0 0 +40 10 1 Cr-53 0 0 +41 10 1 Cr-54 0 0 +0 10 2 H-1 0 0 +1 10 2 O-16 0 0 +2 10 2 B-10 0 0 +3 10 2 B-11 0 0 +4 10 2 Fe-54 0 0 +5 10 2 Fe-56 0 0 +6 10 2 Fe-57 0 0 +7 10 2 Fe-58 0 0 +8 10 2 Ni-58 0 0 +9 10 2 Ni-60 0 0 +10 10 2 Ni-61 0 0 +11 10 2 Ni-62 0 0 +12 10 2 Ni-64 0 0 +13 10 2 Mn-55 0 0 +14 10 2 Si-28 0 0 +15 10 2 Si-29 0 0 +16 10 2 Si-30 0 0 +17 10 2 Cr-50 0 0 +18 10 2 Cr-52 0 0 +19 10 2 Cr-53 0 0 +20 10 2 Cr-54 0 0 material group in group out nuclide moment mean +252 10 1 1 H-1 P0 0.429436 +253 10 1 1 H-1 P1 0.305492 +254 10 1 1 H-1 P2 0.144235 +255 10 1 1 H-1 P3 0.045491 +256 10 1 1 O-16 P0 0.000000 +257 10 1 1 O-16 P1 0.000000 +258 10 1 1 O-16 P2 0.000000 +259 10 1 1 O-16 P3 0.000000 +260 10 1 1 B-10 P0 0.000000 +261 10 1 1 B-10 P1 0.000000 +262 10 1 1 B-10 P2 0.000000 +263 10 1 1 B-10 P3 0.000000 +264 10 1 1 B-11 P0 0.000000 +265 10 1 1 B-11 P1 0.000000 +266 10 1 1 B-11 P2 0.000000 +267 10 1 1 B-11 P3 0.000000 +268 10 1 1 Fe-54 P0 0.000000 +269 10 1 1 Fe-54 P1 0.000000 +270 10 1 1 Fe-54 P2 0.000000 +271 10 1 1 Fe-54 P3 0.000000 +272 10 1 1 Fe-56 P0 0.000000 +273 10 1 1 Fe-56 P1 0.000000 +274 10 1 1 Fe-56 P2 0.000000 +275 10 1 1 Fe-56 P3 0.000000 +276 10 1 1 Fe-57 P0 0.000000 +277 10 1 1 Fe-57 P1 0.000000 +278 10 1 1 Fe-57 P2 0.000000 +279 10 1 1 Fe-57 P3 0.000000 +280 10 1 1 Fe-58 P0 0.000000 +281 10 1 1 Fe-58 P1 0.000000 +282 10 1 1 Fe-58 P2 0.000000 +283 10 1 1 Fe-58 P3 0.000000 +284 10 1 1 Ni-58 P0 0.000000 +285 10 1 1 Ni-58 P1 0.000000 +286 10 1 1 Ni-58 P2 0.000000 +287 10 1 1 Ni-58 P3 0.000000 +288 10 1 1 Ni-60 P0 0.000000 +289 10 1 1 Ni-60 P1 0.000000 +290 10 1 1 Ni-60 P2 0.000000 +291 10 1 1 Ni-60 P3 0.000000 +292 10 1 1 Ni-61 P0 0.000000 +293 10 1 1 Ni-61 P1 0.000000 +294 10 1 1 Ni-61 P2 0.000000 +295 10 1 1 Ni-61 P3 0.000000 +296 10 1 1 Ni-62 P0 0.000000 +297 10 1 1 Ni-62 P1 0.000000 +298 10 1 1 Ni-62 P2 0.000000 +299 10 1 1 Ni-62 P3 0.000000 +300 10 1 1 Ni-64 P0 0.000000 +301 10 1 1 Ni-64 P1 0.000000 +302 10 1 1 Ni-64 P2 0.000000 +303 10 1 1 Ni-64 P3 0.000000 +304 10 1 1 Mn-55 P0 0.000000 +305 10 1 1 Mn-55 P1 0.000000 +306 10 1 1 Mn-55 P2 0.000000 +307 10 1 1 Mn-55 P3 0.000000 +308 10 1 1 Si-28 P0 0.000000 +309 10 1 1 Si-28 P1 0.000000 +310 10 1 1 Si-28 P2 0.000000 +311 10 1 1 Si-28 P3 0.000000 +312 10 1 1 Si-29 P0 0.000000 +313 10 1 1 Si-29 P1 0.000000 +314 10 1 1 Si-29 P2 0.000000 +315 10 1 1 Si-29 P3 0.000000 +316 10 1 1 Si-30 P0 0.000000 +317 10 1 1 Si-30 P1 0.000000 +318 10 1 1 Si-30 P2 0.000000 +319 10 1 1 Si-30 P3 0.000000 +320 10 1 1 Cr-50 P0 0.071573 +321 10 1 1 Cr-50 P1 -0.039998 +322 10 1 1 Cr-50 P2 -0.002257 +323 10 1 1 Cr-50 P3 0.028768 +324 10 1 1 Cr-52 P0 0.000000 +325 10 1 1 Cr-52 P1 0.000000 +326 10 1 1 Cr-52 P2 0.000000 +327 10 1 1 Cr-52 P3 0.000000 +328 10 1 1 Cr-53 P0 0.000000 +329 10 1 1 Cr-53 P1 0.000000 +330 10 1 1 Cr-53 P2 0.000000 +331 10 1 1 Cr-53 P3 0.000000 +332 10 1 1 Cr-54 P0 0.000000 +333 10 1 1 Cr-54 P1 0.000000 +334 10 1 1 Cr-54 P2 0.000000 +335 10 1 1 Cr-54 P3 0.000000 +168 10 1 2 H-1 P0 0.000000 +169 10 1 2 H-1 P1 0.000000 +170 10 1 2 H-1 P2 0.000000 +171 10 1 2 H-1 P3 0.000000 +172 10 1 2 O-16 P0 0.000000 +173 10 1 2 O-16 P1 0.000000 +174 10 1 2 O-16 P2 0.000000 +175 10 1 2 O-16 P3 0.000000 +176 10 1 2 B-10 P0 0.000000 +177 10 1 2 B-10 P1 0.000000 +178 10 1 2 B-10 P2 0.000000 +179 10 1 2 B-10 P3 0.000000 +180 10 1 2 B-11 P0 0.000000 +181 10 1 2 B-11 P1 0.000000 +182 10 1 2 B-11 P2 0.000000 +183 10 1 2 B-11 P3 0.000000 +184 10 1 2 Fe-54 P0 0.000000 +185 10 1 2 Fe-54 P1 0.000000 +186 10 1 2 Fe-54 P2 0.000000 +187 10 1 2 Fe-54 P3 0.000000 +188 10 1 2 Fe-56 P0 0.000000 +189 10 1 2 Fe-56 P1 0.000000 +190 10 1 2 Fe-56 P2 0.000000 +191 10 1 2 Fe-56 P3 0.000000 +192 10 1 2 Fe-57 P0 0.000000 +193 10 1 2 Fe-57 P1 0.000000 +194 10 1 2 Fe-57 P2 0.000000 +195 10 1 2 Fe-57 P3 0.000000 +196 10 1 2 Fe-58 P0 0.000000 +197 10 1 2 Fe-58 P1 0.000000 +198 10 1 2 Fe-58 P2 0.000000 +199 10 1 2 Fe-58 P3 0.000000 +200 10 1 2 Ni-58 P0 0.000000 +201 10 1 2 Ni-58 P1 0.000000 +202 10 1 2 Ni-58 P2 0.000000 +203 10 1 2 Ni-58 P3 0.000000 +204 10 1 2 Ni-60 P0 0.000000 +205 10 1 2 Ni-60 P1 0.000000 +206 10 1 2 Ni-60 P2 0.000000 +207 10 1 2 Ni-60 P3 0.000000 +208 10 1 2 Ni-61 P0 0.000000 +209 10 1 2 Ni-61 P1 0.000000 +210 10 1 2 Ni-61 P2 0.000000 +211 10 1 2 Ni-61 P3 0.000000 +212 10 1 2 Ni-62 P0 0.000000 +213 10 1 2 Ni-62 P1 0.000000 +214 10 1 2 Ni-62 P2 0.000000 +215 10 1 2 Ni-62 P3 0.000000 +216 10 1 2 Ni-64 P0 0.000000 +217 10 1 2 Ni-64 P1 0.000000 +218 10 1 2 Ni-64 P2 0.000000 +219 10 1 2 Ni-64 P3 0.000000 +220 10 1 2 Mn-55 P0 0.000000 +221 10 1 2 Mn-55 P1 0.000000 +222 10 1 2 Mn-55 P2 0.000000 +223 10 1 2 Mn-55 P3 0.000000 +224 10 1 2 Si-28 P0 0.000000 +225 10 1 2 Si-28 P1 0.000000 +226 10 1 2 Si-28 P2 0.000000 +227 10 1 2 Si-28 P3 0.000000 +228 10 1 2 Si-29 P0 0.000000 +229 10 1 2 Si-29 P1 0.000000 +230 10 1 2 Si-29 P2 0.000000 +231 10 1 2 Si-29 P3 0.000000 +232 10 1 2 Si-30 P0 0.000000 +233 10 1 2 Si-30 P1 0.000000 +234 10 1 2 Si-30 P2 0.000000 +235 10 1 2 Si-30 P3 0.000000 +236 10 1 2 Cr-50 P0 0.000000 +237 10 1 2 Cr-50 P1 0.000000 +238 10 1 2 Cr-50 P2 0.000000 +239 10 1 2 Cr-50 P3 0.000000 +240 10 1 2 Cr-52 P0 0.000000 +241 10 1 2 Cr-52 P1 0.000000 +242 10 1 2 Cr-52 P2 0.000000 +243 10 1 2 Cr-52 P3 0.000000 +244 10 1 2 Cr-53 P0 0.000000 +245 10 1 2 Cr-53 P1 0.000000 +246 10 1 2 Cr-53 P2 0.000000 +247 10 1 2 Cr-53 P3 0.000000 +248 10 1 2 Cr-54 P0 0.000000 +249 10 1 2 Cr-54 P1 0.000000 +250 10 1 2 Cr-54 P2 0.000000 +251 10 1 2 Cr-54 P3 0.000000 +84 10 2 1 H-1 P0 0.000000 +85 10 2 1 H-1 P1 0.000000 +86 10 2 1 H-1 P2 0.000000 +87 10 2 1 H-1 P3 0.000000 +88 10 2 1 O-16 P0 0.000000 +89 10 2 1 O-16 P1 0.000000 +90 10 2 1 O-16 P2 0.000000 +91 10 2 1 O-16 P3 0.000000 +92 10 2 1 B-10 P0 0.000000 +93 10 2 1 B-10 P1 0.000000 +94 10 2 1 B-10 P2 0.000000 +95 10 2 1 B-10 P3 0.000000 +96 10 2 1 B-11 P0 0.000000 +97 10 2 1 B-11 P1 0.000000 +98 10 2 1 B-11 P2 0.000000 +99 10 2 1 B-11 P3 0.000000 +100 10 2 1 Fe-54 P0 0.000000 +101 10 2 1 Fe-54 P1 0.000000 +102 10 2 1 Fe-54 P2 0.000000 +103 10 2 1 Fe-54 P3 0.000000 +104 10 2 1 Fe-56 P0 0.000000 +105 10 2 1 Fe-56 P1 0.000000 +106 10 2 1 Fe-56 P2 0.000000 +107 10 2 1 Fe-56 P3 0.000000 +108 10 2 1 Fe-57 P0 0.000000 +109 10 2 1 Fe-57 P1 0.000000 +110 10 2 1 Fe-57 P2 0.000000 +111 10 2 1 Fe-57 P3 0.000000 +112 10 2 1 Fe-58 P0 0.000000 +113 10 2 1 Fe-58 P1 0.000000 +114 10 2 1 Fe-58 P2 0.000000 +115 10 2 1 Fe-58 P3 0.000000 +116 10 2 1 Ni-58 P0 0.000000 +117 10 2 1 Ni-58 P1 0.000000 +118 10 2 1 Ni-58 P2 0.000000 +119 10 2 1 Ni-58 P3 0.000000 +120 10 2 1 Ni-60 P0 0.000000 +121 10 2 1 Ni-60 P1 0.000000 +122 10 2 1 Ni-60 P2 0.000000 +123 10 2 1 Ni-60 P3 0.000000 +124 10 2 1 Ni-61 P0 0.000000 +125 10 2 1 Ni-61 P1 0.000000 +126 10 2 1 Ni-61 P2 0.000000 +127 10 2 1 Ni-61 P3 0.000000 +128 10 2 1 Ni-62 P0 0.000000 +129 10 2 1 Ni-62 P1 0.000000 +130 10 2 1 Ni-62 P2 0.000000 +131 10 2 1 Ni-62 P3 0.000000 +132 10 2 1 Ni-64 P0 0.000000 +133 10 2 1 Ni-64 P1 0.000000 +134 10 2 1 Ni-64 P2 0.000000 +135 10 2 1 Ni-64 P3 0.000000 +136 10 2 1 Mn-55 P0 0.000000 +137 10 2 1 Mn-55 P1 0.000000 +138 10 2 1 Mn-55 P2 0.000000 +139 10 2 1 Mn-55 P3 0.000000 +140 10 2 1 Si-28 P0 0.000000 +141 10 2 1 Si-28 P1 0.000000 +142 10 2 1 Si-28 P2 0.000000 +143 10 2 1 Si-28 P3 0.000000 +144 10 2 1 Si-29 P0 0.000000 +145 10 2 1 Si-29 P1 0.000000 +146 10 2 1 Si-29 P2 0.000000 +147 10 2 1 Si-29 P3 0.000000 +148 10 2 1 Si-30 P0 0.000000 +149 10 2 1 Si-30 P1 0.000000 +150 10 2 1 Si-30 P2 0.000000 +151 10 2 1 Si-30 P3 0.000000 +152 10 2 1 Cr-50 P0 0.000000 +153 10 2 1 Cr-50 P1 0.000000 +154 10 2 1 Cr-50 P2 0.000000 +155 10 2 1 Cr-50 P3 0.000000 +156 10 2 1 Cr-52 P0 0.000000 +157 10 2 1 Cr-52 P1 0.000000 +158 10 2 1 Cr-52 P2 0.000000 +159 10 2 1 Cr-52 P3 0.000000 +160 10 2 1 Cr-53 P0 0.000000 +161 10 2 1 Cr-53 P1 0.000000 +162 10 2 1 Cr-53 P2 0.000000 +163 10 2 1 Cr-53 P3 0.000000 +164 10 2 1 Cr-54 P0 0.000000 +165 10 2 1 Cr-54 P1 0.000000 +166 10 2 1 Cr-54 P2 0.000000 +167 10 2 1 Cr-54 P3 0.000000 +0 10 2 2 H-1 P0 0.000000 +1 10 2 2 H-1 P1 0.000000 +2 10 2 2 H-1 P2 0.000000 +3 10 2 2 H-1 P3 0.000000 +4 10 2 2 O-16 P0 0.000000 +5 10 2 2 O-16 P1 0.000000 +6 10 2 2 O-16 P2 0.000000 +7 10 2 2 O-16 P3 0.000000 +8 10 2 2 B-10 P0 0.000000 +9 10 2 2 B-10 P1 0.000000 +10 10 2 2 B-10 P2 0.000000 +11 10 2 2 B-10 P3 0.000000 +12 10 2 2 B-11 P0 0.000000 +13 10 2 2 B-11 P1 0.000000 +14 10 2 2 B-11 P2 0.000000 +15 10 2 2 B-11 P3 0.000000 +16 10 2 2 Fe-54 P0 0.000000 +17 10 2 2 Fe-54 P1 0.000000 +18 10 2 2 Fe-54 P2 0.000000 +19 10 2 2 Fe-54 P3 0.000000 +20 10 2 2 Fe-56 P0 0.000000 +21 10 2 2 Fe-56 P1 0.000000 +22 10 2 2 Fe-56 P2 0.000000 +23 10 2 2 Fe-56 P3 0.000000 +24 10 2 2 Fe-57 P0 0.000000 +25 10 2 2 Fe-57 P1 0.000000 +26 10 2 2 Fe-57 P2 0.000000 +27 10 2 2 Fe-57 P3 0.000000 +28 10 2 2 Fe-58 P0 0.000000 +29 10 2 2 Fe-58 P1 0.000000 +30 10 2 2 Fe-58 P2 0.000000 +31 10 2 2 Fe-58 P3 0.000000 +32 10 2 2 Ni-58 P0 0.000000 +33 10 2 2 Ni-58 P1 0.000000 +34 10 2 2 Ni-58 P2 0.000000 +35 10 2 2 Ni-58 P3 0.000000 +36 10 2 2 Ni-60 P0 0.000000 +37 10 2 2 Ni-60 P1 0.000000 +38 10 2 2 Ni-60 P2 0.000000 +39 10 2 2 Ni-60 P3 0.000000 +40 10 2 2 Ni-61 P0 0.000000 +41 10 2 2 Ni-61 P1 0.000000 +42 10 2 2 Ni-61 P2 0.000000 +43 10 2 2 Ni-61 P3 0.000000 +44 10 2 2 Ni-62 P0 0.000000 +45 10 2 2 Ni-62 P1 0.000000 +46 10 2 2 Ni-62 P2 0.000000 +47 10 2 2 Ni-62 P3 0.000000 +48 10 2 2 Ni-64 P0 0.000000 +49 10 2 2 Ni-64 P1 0.000000 +50 10 2 2 Ni-64 P2 0.000000 +51 10 2 2 Ni-64 P3 0.000000 +52 10 2 2 Mn-55 P0 0.000000 +53 10 2 2 Mn-55 P1 0.000000 +54 10 2 2 Mn-55 P2 0.000000 +55 10 2 2 Mn-55 P3 0.000000 +56 10 2 2 Si-28 P0 0.000000 +57 10 2 2 Si-28 P1 0.000000 +58 10 2 2 Si-28 P2 0.000000 +59 10 2 2 Si-28 P3 0.000000 +60 10 2 2 Si-29 P0 0.000000 +61 10 2 2 Si-29 P1 0.000000 +62 10 2 2 Si-29 P2 0.000000 +63 10 2 2 Si-29 P3 0.000000 +64 10 2 2 Si-30 P0 0.000000 +65 10 2 2 Si-30 P1 0.000000 +66 10 2 2 Si-30 P2 0.000000 +67 10 2 2 Si-30 P3 0.000000 +68 10 2 2 Cr-50 P0 0.000000 +69 10 2 2 Cr-50 P1 0.000000 +70 10 2 2 Cr-50 P2 0.000000 +71 10 2 2 Cr-50 P3 0.000000 +72 10 2 2 Cr-52 P0 0.000000 +73 10 2 2 Cr-52 P1 0.000000 +74 10 2 2 Cr-52 P2 0.000000 +75 10 2 2 Cr-52 P3 0.000000 +76 10 2 2 Cr-53 P0 0.000000 +77 10 2 2 Cr-53 P1 0.000000 +78 10 2 2 Cr-53 P2 0.000000 +79 10 2 2 Cr-53 P3 0.000000 +80 10 2 2 Cr-54 P0 0.000000 +81 10 2 2 Cr-54 P1 0.000000 +82 10 2 2 Cr-54 P2 0.000000 +83 10 2 2 Cr-54 P3 0.000000 material group out nuclide mean std. dev. +21 10 1 H-1 0 0 +22 10 1 O-16 0 0 +23 10 1 B-10 0 0 +24 10 1 B-11 0 0 +25 10 1 Fe-54 0 0 +26 10 1 Fe-56 0 0 +27 10 1 Fe-57 0 0 +28 10 1 Fe-58 0 0 +29 10 1 Ni-58 0 0 +30 10 1 Ni-60 0 0 +31 10 1 Ni-61 0 0 +32 10 1 Ni-62 0 0 +33 10 1 Ni-64 0 0 +34 10 1 Mn-55 0 0 +35 10 1 Si-28 0 0 +36 10 1 Si-29 0 0 +37 10 1 Si-30 0 0 +38 10 1 Cr-50 0 0 +39 10 1 Cr-52 0 0 +40 10 1 Cr-53 0 0 +41 10 1 Cr-54 0 0 +0 10 2 H-1 0 0 +1 10 2 O-16 0 0 +2 10 2 B-10 0 0 +3 10 2 B-11 0 0 +4 10 2 Fe-54 0 0 +5 10 2 Fe-56 0 0 +6 10 2 Fe-57 0 0 +7 10 2 Fe-58 0 0 +8 10 2 Ni-58 0 0 +9 10 2 Ni-60 0 0 +10 10 2 Ni-61 0 0 +11 10 2 Ni-62 0 0 +12 10 2 Ni-64 0 0 +13 10 2 Mn-55 0 0 +14 10 2 Si-28 0 0 +15 10 2 Si-29 0 0 +16 10 2 Si-30 0 0 +17 10 2 Cr-50 0 0 +18 10 2 Cr-52 0 0 +19 10 2 Cr-53 0 0 +20 10 2 Cr-54 0 0 material group in nuclide mean std. dev. 9 11 1 H-1 0.131470 0.476035 10 11 1 O-16 0.028684 0.043000 11 11 1 B-10 0.000000 0.000000 @@ -1807,78 +3955,186 @@ 6 11 2 Zr-92 0.084226 0.103161 7 11 2 Zr-94 0.092039 0.125985 8 11 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 11 1 H-1 0.0 0.0 -10 11 1 O-16 0.0 0.0 -11 11 1 B-10 0.0 0.0 -12 11 1 B-11 0.0 0.0 -13 11 1 Zr-90 0.0 0.0 -14 11 1 Zr-91 0.0 0.0 -15 11 1 Zr-92 0.0 0.0 -16 11 1 Zr-94 0.0 0.0 -17 11 1 Zr-96 0.0 0.0 -0 11 2 H-1 0.0 0.0 -1 11 2 O-16 0.0 0.0 -2 11 2 B-10 0.0 0.0 -3 11 2 B-11 0.0 0.0 -4 11 2 Zr-90 0.0 0.0 -5 11 2 Zr-91 0.0 0.0 -6 11 2 Zr-92 0.0 0.0 -7 11 2 Zr-94 0.0 0.0 -8 11 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -27 11 1 1 H-1 0.099594 0.442578 -28 11 1 1 O-16 0.028684 0.043000 -29 11 1 1 B-10 0.000000 0.000000 -30 11 1 1 B-11 0.000000 0.000000 -31 11 1 1 Zr-90 0.021980 0.039963 -32 11 1 1 Zr-91 0.000000 0.000000 -33 11 1 1 Zr-92 0.000000 0.000000 -34 11 1 1 Zr-94 0.004191 0.087344 -35 11 1 1 Zr-96 0.000000 0.000000 -18 11 1 2 H-1 0.031875 0.045078 -19 11 1 2 O-16 0.000000 0.000000 -20 11 1 2 B-10 0.000000 0.000000 -21 11 1 2 B-11 0.000000 0.000000 -22 11 1 2 Zr-90 0.000000 0.000000 -23 11 1 2 Zr-91 0.000000 0.000000 -24 11 1 2 Zr-92 0.000000 0.000000 -25 11 1 2 Zr-94 0.000000 0.000000 -26 11 1 2 Zr-96 0.000000 0.000000 -9 11 2 1 H-1 0.000000 0.000000 -10 11 2 1 O-16 0.000000 0.000000 -11 11 2 1 B-10 0.000000 0.000000 -12 11 2 1 B-11 0.000000 0.000000 -13 11 2 1 Zr-90 0.000000 0.000000 -14 11 2 1 Zr-91 0.000000 0.000000 -15 11 2 1 Zr-92 0.000000 0.000000 -16 11 2 1 Zr-94 0.000000 0.000000 -17 11 2 1 Zr-96 0.000000 0.000000 -0 11 2 2 H-1 0.687243 1.239217 -1 11 2 2 O-16 0.000000 0.000000 -2 11 2 2 B-10 0.000000 0.000000 -3 11 2 2 B-11 0.000000 0.000000 -4 11 2 2 Zr-90 0.039576 0.105193 -5 11 2 2 Zr-91 0.000000 0.000000 -6 11 2 2 Zr-92 0.084226 0.103161 -7 11 2 2 Zr-94 0.092039 0.125985 -8 11 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -9 11 1 H-1 0.0 0.0 -10 11 1 O-16 0.0 0.0 -11 11 1 B-10 0.0 0.0 -12 11 1 B-11 0.0 0.0 -13 11 1 Zr-90 0.0 0.0 -14 11 1 Zr-91 0.0 0.0 -15 11 1 Zr-92 0.0 0.0 -16 11 1 Zr-94 0.0 0.0 -17 11 1 Zr-96 0.0 0.0 -0 11 2 H-1 0.0 0.0 -1 11 2 O-16 0.0 0.0 -2 11 2 B-10 0.0 0.0 -3 11 2 B-11 0.0 0.0 -4 11 2 Zr-90 0.0 0.0 -5 11 2 Zr-91 0.0 0.0 -6 11 2 Zr-92 0.0 0.0 -7 11 2 Zr-94 0.0 0.0 -8 11 2 Zr-96 0.0 0.0 material group in nuclide mean std. dev. +9 11 1 H-1 0 0 +10 11 1 O-16 0 0 +11 11 1 B-10 0 0 +12 11 1 B-11 0 0 +13 11 1 Zr-90 0 0 +14 11 1 Zr-91 0 0 +15 11 1 Zr-92 0 0 +16 11 1 Zr-94 0 0 +17 11 1 Zr-96 0 0 +0 11 2 H-1 0 0 +1 11 2 O-16 0 0 +2 11 2 B-10 0 0 +3 11 2 B-11 0 0 +4 11 2 Zr-90 0 0 +5 11 2 Zr-91 0 0 +6 11 2 Zr-92 0 0 +7 11 2 Zr-94 0 0 +8 11 2 Zr-96 0 0 material group in group out nuclide moment mean +108 11 1 1 H-1 P0 0.350627 +109 11 1 1 H-1 P1 0.251032 +110 11 1 1 H-1 P2 0.118434 +111 11 1 1 H-1 P3 0.029897 +112 11 1 1 O-16 P0 0.031875 +113 11 1 1 O-16 P1 0.003191 +114 11 1 1 O-16 P2 -0.015458 +115 11 1 1 O-16 P3 -0.004707 +116 11 1 1 B-10 P0 0.000000 +117 11 1 1 B-10 P1 0.000000 +118 11 1 1 B-10 P2 0.000000 +119 11 1 1 B-10 P3 0.000000 +120 11 1 1 B-11 P0 0.000000 +121 11 1 1 B-11 P1 0.000000 +122 11 1 1 B-11 P2 0.000000 +123 11 1 1 B-11 P3 0.000000 +124 11 1 1 Zr-90 P0 0.031875 +125 11 1 1 Zr-90 P1 0.009895 +126 11 1 1 Zr-90 P2 -0.011330 +127 11 1 1 Zr-90 P3 -0.012459 +128 11 1 1 Zr-91 P0 0.000000 +129 11 1 1 Zr-91 P1 0.000000 +130 11 1 1 Zr-91 P2 0.000000 +131 11 1 1 Zr-91 P3 0.000000 +132 11 1 1 Zr-92 P0 0.000000 +133 11 1 1 Zr-92 P1 0.000000 +134 11 1 1 Zr-92 P2 0.000000 +135 11 1 1 Zr-92 P3 0.000000 +136 11 1 1 Zr-94 P0 0.063750 +137 11 1 1 Zr-94 P1 0.059559 +138 11 1 1 Zr-94 P2 0.051729 +139 11 1 1 Zr-94 P3 0.041273 +140 11 1 1 Zr-96 P0 0.000000 +141 11 1 1 Zr-96 P1 0.000000 +142 11 1 1 Zr-96 P2 0.000000 +143 11 1 1 Zr-96 P3 0.000000 +72 11 1 2 H-1 P0 0.031875 +73 11 1 2 H-1 P1 0.008585 +74 11 1 2 H-1 P2 -0.012470 +75 11 1 2 H-1 P3 -0.011320 +76 11 1 2 O-16 P0 0.000000 +77 11 1 2 O-16 P1 0.000000 +78 11 1 2 O-16 P2 0.000000 +79 11 1 2 O-16 P3 0.000000 +80 11 1 2 B-10 P0 0.000000 +81 11 1 2 B-10 P1 0.000000 +82 11 1 2 B-10 P2 0.000000 +83 11 1 2 B-10 P3 0.000000 +84 11 1 2 B-11 P0 0.000000 +85 11 1 2 B-11 P1 0.000000 +86 11 1 2 B-11 P2 0.000000 +87 11 1 2 B-11 P3 0.000000 +88 11 1 2 Zr-90 P0 0.000000 +89 11 1 2 Zr-90 P1 0.000000 +90 11 1 2 Zr-90 P2 0.000000 +91 11 1 2 Zr-90 P3 0.000000 +92 11 1 2 Zr-91 P0 0.000000 +93 11 1 2 Zr-91 P1 0.000000 +94 11 1 2 Zr-91 P2 0.000000 +95 11 1 2 Zr-91 P3 0.000000 +96 11 1 2 Zr-92 P0 0.000000 +97 11 1 2 Zr-92 P1 0.000000 +98 11 1 2 Zr-92 P2 0.000000 +99 11 1 2 Zr-92 P3 0.000000 +100 11 1 2 Zr-94 P0 0.000000 +101 11 1 2 Zr-94 P1 0.000000 +102 11 1 2 Zr-94 P2 0.000000 +103 11 1 2 Zr-94 P3 0.000000 +104 11 1 2 Zr-96 P0 0.000000 +105 11 1 2 Zr-96 P1 0.000000 +106 11 1 2 Zr-96 P2 0.000000 +107 11 1 2 Zr-96 P3 0.000000 +36 11 2 1 H-1 P0 0.000000 +37 11 2 1 H-1 P1 0.000000 +38 11 2 1 H-1 P2 0.000000 +39 11 2 1 H-1 P3 0.000000 +40 11 2 1 O-16 P0 0.000000 +41 11 2 1 O-16 P1 0.000000 +42 11 2 1 O-16 P2 0.000000 +43 11 2 1 O-16 P3 0.000000 +44 11 2 1 B-10 P0 0.000000 +45 11 2 1 B-10 P1 0.000000 +46 11 2 1 B-10 P2 0.000000 +47 11 2 1 B-10 P3 0.000000 +48 11 2 1 B-11 P0 0.000000 +49 11 2 1 B-11 P1 0.000000 +50 11 2 1 B-11 P2 0.000000 +51 11 2 1 B-11 P3 0.000000 +52 11 2 1 Zr-90 P0 0.000000 +53 11 2 1 Zr-90 P1 0.000000 +54 11 2 1 Zr-90 P2 0.000000 +55 11 2 1 Zr-90 P3 0.000000 +56 11 2 1 Zr-91 P0 0.000000 +57 11 2 1 Zr-91 P1 0.000000 +58 11 2 1 Zr-91 P2 0.000000 +59 11 2 1 Zr-91 P3 0.000000 +60 11 2 1 Zr-92 P0 0.000000 +61 11 2 1 Zr-92 P1 0.000000 +62 11 2 1 Zr-92 P2 0.000000 +63 11 2 1 Zr-92 P3 0.000000 +64 11 2 1 Zr-94 P0 0.000000 +65 11 2 1 Zr-94 P1 0.000000 +66 11 2 1 Zr-94 P2 0.000000 +67 11 2 1 Zr-94 P3 0.000000 +68 11 2 1 Zr-96 P0 0.000000 +69 11 2 1 Zr-96 P1 0.000000 +70 11 2 1 Zr-96 P2 0.000000 +71 11 2 1 Zr-96 P3 0.000000 +0 11 2 2 H-1 P0 0.986741 +1 11 2 2 H-1 P1 0.287943 +2 11 2 2 H-1 P2 0.156802 +3 11 2 2 H-1 P3 0.037565 +4 11 2 2 O-16 P0 0.000000 +5 11 2 2 O-16 P1 0.000000 +6 11 2 2 O-16 P2 0.000000 +7 11 2 2 O-16 P3 0.000000 +8 11 2 2 B-10 P0 0.000000 +9 11 2 2 B-10 P1 0.000000 +10 11 2 2 B-10 P2 0.000000 +11 11 2 2 B-10 P3 0.000000 +12 11 2 2 B-11 P0 0.000000 +13 11 2 2 B-11 P1 0.000000 +14 11 2 2 B-11 P2 0.000000 +15 11 2 2 B-11 P3 0.000000 +16 11 2 2 Zr-90 P0 0.085804 +17 11 2 2 Zr-90 P1 0.046227 +18 11 2 2 Zr-90 P2 -0.005520 +19 11 2 2 Zr-90 P3 -0.035731 +20 11 2 2 Zr-91 P0 0.000000 +21 11 2 2 Zr-91 P1 0.000000 +22 11 2 2 Zr-91 P2 0.000000 +23 11 2 2 Zr-91 P3 0.000000 +24 11 2 2 Zr-92 P0 0.042902 +25 11 2 2 Zr-92 P1 -0.041324 +26 11 2 2 Zr-92 P2 0.038256 +27 11 2 2 Zr-92 P3 -0.033866 +28 11 2 2 Zr-94 P0 0.085804 +29 11 2 2 Zr-94 P1 -0.006235 +30 11 2 2 Zr-94 P2 0.028653 +31 11 2 2 Zr-94 P3 -0.016482 +32 11 2 2 Zr-96 P0 0.000000 +33 11 2 2 Zr-96 P1 0.000000 +34 11 2 2 Zr-96 P2 0.000000 +35 11 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. +9 11 1 H-1 0 0 +10 11 1 O-16 0 0 +11 11 1 B-10 0 0 +12 11 1 B-11 0 0 +13 11 1 Zr-90 0 0 +14 11 1 Zr-91 0 0 +15 11 1 Zr-92 0 0 +16 11 1 Zr-94 0 0 +17 11 1 Zr-96 0 0 +0 11 2 H-1 0 0 +1 11 2 O-16 0 0 +2 11 2 B-10 0 0 +3 11 2 B-11 0 0 +4 11 2 Zr-90 0 0 +5 11 2 Zr-91 0 0 +6 11 2 Zr-92 0 0 +7 11 2 Zr-94 0 0 +8 11 2 Zr-96 0 0 material group in nuclide mean std. dev. 9 12 1 H-1 0.098944 0.178543 10 12 1 O-16 0.013270 0.020403 11 12 1 B-10 0.000000 0.000000 @@ -1897,75 +4153,183 @@ 6 12 2 Zr-92 0.000000 0.000000 7 12 2 Zr-94 0.000000 0.000000 8 12 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 12 1 H-1 0.0 0.0 -10 12 1 O-16 0.0 0.0 -11 12 1 B-10 0.0 0.0 -12 12 1 B-11 0.0 0.0 -13 12 1 Zr-90 0.0 0.0 -14 12 1 Zr-91 0.0 0.0 -15 12 1 Zr-92 0.0 0.0 -16 12 1 Zr-94 0.0 0.0 -17 12 1 Zr-96 0.0 0.0 -0 12 2 H-1 0.0 0.0 -1 12 2 O-16 0.0 0.0 -2 12 2 B-10 0.0 0.0 -3 12 2 B-11 0.0 0.0 -4 12 2 Zr-90 0.0 0.0 -5 12 2 Zr-91 0.0 0.0 -6 12 2 Zr-92 0.0 0.0 -7 12 2 Zr-94 0.0 0.0 -8 12 2 Zr-96 0.0 0.0 material group in group out nuclide mean std. dev. -27 12 1 1 H-1 0.071704 0.167588 -28 12 1 1 O-16 0.013270 0.020403 -29 12 1 1 B-10 0.000000 0.000000 -30 12 1 1 B-11 0.000000 0.000000 -31 12 1 1 Zr-90 0.089997 0.075538 -32 12 1 1 Zr-91 0.000000 0.000000 -33 12 1 1 Zr-92 0.003501 0.017031 -34 12 1 1 Zr-94 0.004850 0.016327 -35 12 1 1 Zr-96 0.002730 0.017476 -18 12 1 2 H-1 0.027240 0.029555 -19 12 1 2 O-16 0.000000 0.000000 -20 12 1 2 B-10 0.000000 0.000000 -21 12 1 2 B-11 0.000000 0.000000 -22 12 1 2 Zr-90 0.000000 0.000000 -23 12 1 2 Zr-91 0.000000 0.000000 -24 12 1 2 Zr-92 0.000000 0.000000 -25 12 1 2 Zr-94 0.000000 0.000000 -26 12 1 2 Zr-96 0.000000 0.000000 -9 12 2 1 H-1 0.000000 0.000000 -10 12 2 1 O-16 0.000000 0.000000 -11 12 2 1 B-10 0.000000 0.000000 -12 12 2 1 B-11 0.000000 0.000000 -13 12 2 1 Zr-90 0.000000 0.000000 -14 12 2 1 Zr-91 0.000000 0.000000 -15 12 2 1 Zr-92 0.000000 0.000000 -16 12 2 1 Zr-94 0.000000 0.000000 -17 12 2 1 Zr-96 0.000000 0.000000 -0 12 2 2 H-1 1.244758 1.956675 -1 12 2 2 O-16 0.079159 0.104796 -2 12 2 2 B-10 0.000000 0.000000 -3 12 2 2 B-11 0.000000 0.000000 -4 12 2 2 Zr-90 0.000000 0.000000 -5 12 2 2 Zr-91 0.033201 0.040665 -6 12 2 2 Zr-92 0.000000 0.000000 -7 12 2 2 Zr-94 0.000000 0.000000 -8 12 2 2 Zr-96 0.000000 0.000000 material group out nuclide mean std. dev. -9 12 1 H-1 0.0 0.0 -10 12 1 O-16 0.0 0.0 -11 12 1 B-10 0.0 0.0 -12 12 1 B-11 0.0 0.0 -13 12 1 Zr-90 0.0 0.0 -14 12 1 Zr-91 0.0 0.0 -15 12 1 Zr-92 0.0 0.0 -16 12 1 Zr-94 0.0 0.0 -17 12 1 Zr-96 0.0 0.0 -0 12 2 H-1 0.0 0.0 -1 12 2 O-16 0.0 0.0 -2 12 2 B-10 0.0 0.0 -3 12 2 B-11 0.0 0.0 -4 12 2 Zr-90 0.0 0.0 -5 12 2 Zr-91 0.0 0.0 -6 12 2 Zr-92 0.0 0.0 -7 12 2 Zr-94 0.0 0.0 -8 12 2 Zr-96 0.0 0.0 \ No newline at end of file +9 12 1 H-1 0 0 +10 12 1 O-16 0 0 +11 12 1 B-10 0 0 +12 12 1 B-11 0 0 +13 12 1 Zr-90 0 0 +14 12 1 Zr-91 0 0 +15 12 1 Zr-92 0 0 +16 12 1 Zr-94 0 0 +17 12 1 Zr-96 0 0 +0 12 2 H-1 0 0 +1 12 2 O-16 0 0 +2 12 2 B-10 0 0 +3 12 2 B-11 0 0 +4 12 2 Zr-90 0 0 +5 12 2 Zr-91 0 0 +6 12 2 Zr-92 0 0 +7 12 2 Zr-94 0 0 +8 12 2 Zr-96 0 0 material group in group out nuclide moment mean +108 12 1 1 H-1 P0 0.245156 +109 12 1 1 H-1 P1 0.173452 +110 12 1 1 H-1 P2 0.092660 +111 12 1 1 H-1 P3 0.047419 +112 12 1 1 O-16 P0 0.027240 +113 12 1 1 O-16 P1 0.013970 +114 12 1 1 O-16 P2 0.000090 +115 12 1 1 O-16 P3 -0.004169 +116 12 1 1 B-10 P0 0.000000 +117 12 1 1 B-10 P1 0.000000 +118 12 1 1 B-10 P2 0.000000 +119 12 1 1 B-10 P3 0.000000 +120 12 1 1 B-11 P0 0.000000 +121 12 1 1 B-11 P1 0.000000 +122 12 1 1 B-11 P2 0.000000 +123 12 1 1 B-11 P3 0.000000 +124 12 1 1 Zr-90 P0 0.095339 +125 12 1 1 Zr-90 P1 0.005341 +126 12 1 1 Zr-90 P2 -0.014156 +127 12 1 1 Zr-90 P3 -0.008036 +128 12 1 1 Zr-91 P0 0.000000 +129 12 1 1 Zr-91 P1 0.000000 +130 12 1 1 Zr-91 P2 0.000000 +131 12 1 1 Zr-91 P3 0.000000 +132 12 1 1 Zr-92 P0 0.013620 +133 12 1 1 Zr-92 P1 0.010119 +134 12 1 1 Zr-92 P2 0.004467 +135 12 1 1 Zr-92 P3 -0.001214 +136 12 1 1 Zr-94 P0 0.013620 +137 12 1 1 Zr-94 P1 0.008770 +138 12 1 1 Zr-94 P2 0.001661 +139 12 1 1 Zr-94 P3 -0.004065 +140 12 1 1 Zr-96 P0 0.013620 +141 12 1 1 Zr-96 P1 0.010890 +142 12 1 1 Zr-96 P2 0.006250 +143 12 1 1 Zr-96 P3 0.001069 +72 12 1 2 H-1 P0 0.027240 +73 12 1 2 H-1 P1 -0.010088 +74 12 1 2 H-1 P2 -0.006946 +75 12 1 2 H-1 P3 0.009692 +76 12 1 2 O-16 P0 0.000000 +77 12 1 2 O-16 P1 0.000000 +78 12 1 2 O-16 P2 0.000000 +79 12 1 2 O-16 P3 0.000000 +80 12 1 2 B-10 P0 0.000000 +81 12 1 2 B-10 P1 0.000000 +82 12 1 2 B-10 P2 0.000000 +83 12 1 2 B-10 P3 0.000000 +84 12 1 2 B-11 P0 0.000000 +85 12 1 2 B-11 P1 0.000000 +86 12 1 2 B-11 P2 0.000000 +87 12 1 2 B-11 P3 0.000000 +88 12 1 2 Zr-90 P0 0.000000 +89 12 1 2 Zr-90 P1 0.000000 +90 12 1 2 Zr-90 P2 0.000000 +91 12 1 2 Zr-90 P3 0.000000 +92 12 1 2 Zr-91 P0 0.000000 +93 12 1 2 Zr-91 P1 0.000000 +94 12 1 2 Zr-91 P2 0.000000 +95 12 1 2 Zr-91 P3 0.000000 +96 12 1 2 Zr-92 P0 0.000000 +97 12 1 2 Zr-92 P1 0.000000 +98 12 1 2 Zr-92 P2 0.000000 +99 12 1 2 Zr-92 P3 0.000000 +100 12 1 2 Zr-94 P0 0.000000 +101 12 1 2 Zr-94 P1 0.000000 +102 12 1 2 Zr-94 P2 0.000000 +103 12 1 2 Zr-94 P3 0.000000 +104 12 1 2 Zr-96 P0 0.000000 +105 12 1 2 Zr-96 P1 0.000000 +106 12 1 2 Zr-96 P2 0.000000 +107 12 1 2 Zr-96 P3 0.000000 +36 12 2 1 H-1 P0 0.000000 +37 12 2 1 H-1 P1 0.000000 +38 12 2 1 H-1 P2 0.000000 +39 12 2 1 H-1 P3 0.000000 +40 12 2 1 O-16 P0 0.000000 +41 12 2 1 O-16 P1 0.000000 +42 12 2 1 O-16 P2 0.000000 +43 12 2 1 O-16 P3 0.000000 +44 12 2 1 B-10 P0 0.000000 +45 12 2 1 B-10 P1 0.000000 +46 12 2 1 B-10 P2 0.000000 +47 12 2 1 B-10 P3 0.000000 +48 12 2 1 B-11 P0 0.000000 +49 12 2 1 B-11 P1 0.000000 +50 12 2 1 B-11 P2 0.000000 +51 12 2 1 B-11 P3 0.000000 +52 12 2 1 Zr-90 P0 0.000000 +53 12 2 1 Zr-90 P1 0.000000 +54 12 2 1 Zr-90 P2 0.000000 +55 12 2 1 Zr-90 P3 0.000000 +56 12 2 1 Zr-91 P0 0.000000 +57 12 2 1 Zr-91 P1 0.000000 +58 12 2 1 Zr-91 P2 0.000000 +59 12 2 1 Zr-91 P3 0.000000 +60 12 2 1 Zr-92 P0 0.000000 +61 12 2 1 Zr-92 P1 0.000000 +62 12 2 1 Zr-92 P2 0.000000 +63 12 2 1 Zr-92 P3 0.000000 +64 12 2 1 Zr-94 P0 0.000000 +65 12 2 1 Zr-94 P1 0.000000 +66 12 2 1 Zr-94 P2 0.000000 +67 12 2 1 Zr-94 P3 0.000000 +68 12 2 1 Zr-96 P0 0.000000 +69 12 2 1 Zr-96 P1 0.000000 +70 12 2 1 Zr-96 P2 0.000000 +71 12 2 1 Zr-96 P3 0.000000 +0 12 2 2 H-1 P0 1.489686 +1 12 2 2 H-1 P1 0.257467 +2 12 2 2 H-1 P2 0.001678 +3 12 2 2 H-1 P3 0.044735 +4 12 2 2 O-16 P0 0.067713 +5 12 2 2 O-16 P1 -0.011446 +6 12 2 2 O-16 P2 -0.002500 +7 12 2 2 O-16 P3 0.007446 +8 12 2 2 B-10 P0 0.000000 +9 12 2 2 B-10 P1 0.000000 +10 12 2 2 B-10 P2 0.000000 +11 12 2 2 B-10 P3 0.000000 +12 12 2 2 B-11 P0 0.000000 +13 12 2 2 B-11 P1 0.000000 +14 12 2 2 B-11 P2 0.000000 +15 12 2 2 B-11 P3 0.000000 +16 12 2 2 Zr-90 P0 0.000000 +17 12 2 2 Zr-90 P1 0.000000 +18 12 2 2 Zr-90 P2 0.000000 +19 12 2 2 Zr-90 P3 0.000000 +20 12 2 2 Zr-91 P0 0.016928 +21 12 2 2 Zr-91 P1 -0.016273 +22 12 2 2 Zr-91 P2 0.015000 +23 12 2 2 Zr-91 P3 -0.013183 +24 12 2 2 Zr-92 P0 0.000000 +25 12 2 2 Zr-92 P1 0.000000 +26 12 2 2 Zr-92 P2 0.000000 +27 12 2 2 Zr-92 P3 0.000000 +28 12 2 2 Zr-94 P0 0.000000 +29 12 2 2 Zr-94 P1 0.000000 +30 12 2 2 Zr-94 P2 0.000000 +31 12 2 2 Zr-94 P3 0.000000 +32 12 2 2 Zr-96 P0 0.000000 +33 12 2 2 Zr-96 P1 0.000000 +34 12 2 2 Zr-96 P2 0.000000 +35 12 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. +9 12 1 H-1 0 0 +10 12 1 O-16 0 0 +11 12 1 B-10 0 0 +12 12 1 B-11 0 0 +13 12 1 Zr-90 0 0 +14 12 1 Zr-91 0 0 +15 12 1 Zr-92 0 0 +16 12 1 Zr-94 0 0 +17 12 1 Zr-96 0 0 +0 12 2 H-1 0 0 +1 12 2 O-16 0 0 +2 12 2 B-10 0 0 +3 12 2 B-11 0 0 +4 12 2 Zr-90 0 0 +5 12 2 Zr-91 0 0 +6 12 2 Zr-92 0 0 +7 12 2 Zr-94 0 0 +8 12 2 Zr-96 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py index 113f2aa41..e0a7c199a 100644 --- a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py +++ b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py @@ -28,6 +28,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.mgxs_types = ['transport', 'nu-fission', 'nu-scatter matrix', 'chi'] self.mgxs_lib.energy_groups = energy_groups + self.mgxs_lib.legendre_order = 3 self.mgxs_lib.domain_type = 'material' self.mgxs_lib.build_library() From 66b7979dfcad06293878ebf3398a553bb5ed5276 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Fri, 13 May 2016 17:27:03 -0400 Subject: [PATCH 129/147] Updated test results for MGXS --- openmc/mgxs/mgxs.py | 2 +- .../results_true.dat | 120 +- .../results_true.dat | 10 +- .../results_true.dat | 408 +- .../results_true.dat | 4336 +---------------- .../test_mgxs_library_nuclides.py | 2 +- 6 files changed, 272 insertions(+), 4606 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 182691283..c1255f609 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -2115,7 +2115,7 @@ class ScatterMatrixXS(MGXS): # Place the moment column before the mean column mean_index = df.columns.get_loc('mean') columns = df.columns.tolist() - df = df[columns[:mean_index] + ['moment'] + columns[mean_index:-2]] + df = df[columns[:mean_index] + ['moment'] + columns[mean_index:-1]] # Select rows corresponding to requested scattering moment if moment != 'all': diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index f176c3007..ffe6f2908 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -1,85 +1,85 @@ material group in nuclide mean std. dev. 0 1 1 total 0.412084 0.02359 material group in nuclide mean std. dev. -0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean -0 1 1 1 total P0 0.384780 -1 1 1 1 total P1 0.039277 -2 1 1 1 total P2 0.017574 -3 1 1 1 total P3 0.012203 material group out nuclide mean std. dev. +0 1 1 total 0.076425 0.003691 material group in group out nuclide moment mean std. dev. +0 1 1 1 total P0 0.384780 0.022253 +1 1 1 1 total P1 0.039277 0.004308 +2 1 1 1 total P2 0.017574 0.002402 +3 1 1 1 total P3 0.012203 0.002164 material group out nuclide mean std. dev. 0 1 1 total 1 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0 0 material group in group out nuclide moment mean -0 2 1 1 total P0 0.272369 -1 2 1 1 total P1 0.031107 -2 2 1 1 total P2 0.025999 -3 2 1 1 total P3 0.003219 material group out nuclide mean std. dev. +0 2 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 2 1 1 total P0 0.272369 0.006872 +1 2 1 1 total P1 0.031107 0.005483 +2 2 1 1 total P2 0.025999 0.006151 +3 2 1 1 total P3 0.003219 0.003312 material group out nuclide mean std. dev. 0 2 1 total 0 0 material group in nuclide mean std. dev. 0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0 0 material group in group out nuclide moment mean -0 3 1 1 total P0 0.794999 -1 3 1 1 total P1 0.401537 -2 3 1 1 total P2 0.143623 -3 3 1 1 total P3 0.001991 material group out nuclide mean std. dev. +0 3 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 3 1 1 total P0 0.794999 0.036548 +1 3 1 1 total P1 0.401537 0.016175 +2 3 1 1 total P2 0.143623 0.008719 +3 3 1 1 total P3 0.001991 0.004433 material group out nuclide mean std. dev. 0 3 1 total 0 0 material group in nuclide mean std. dev. 0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0 0 material group in group out nuclide moment mean -0 4 1 1 total P0 0.727311 -1 4 1 1 total P1 0.355839 -2 4 1 1 total P2 0.124483 -3 4 1 1 total P3 0.012168 material group out nuclide mean std. dev. +0 4 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 4 1 1 total P0 0.727311 0.080096 +1 4 1 1 total P1 0.355839 0.037901 +2 4 1 1 total P2 0.124483 0.015823 +3 4 1 1 total P3 0.012168 0.006224 material group out nuclide mean std. dev. 0 4 1 total 0 0 material group in nuclide mean std. dev. 0 5 1 total 0 0 material group in nuclide mean std. dev. -0 5 1 total 0 0 material group in group out nuclide moment mean -0 5 1 1 total P0 0 -1 5 1 1 total P1 0 -2 5 1 1 total P2 0 -3 5 1 1 total P3 0 material group out nuclide mean std. dev. +0 5 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 5 1 1 total P0 0 0 +1 5 1 1 total P1 0 0 +2 5 1 1 total P2 0 0 +3 5 1 1 total P3 0 0 material group out nuclide mean std. dev. 0 5 1 total 0 0 material group in nuclide mean std. dev. 0 6 1 total 0 0 material group in nuclide mean std. dev. -0 6 1 total 0 0 material group in group out nuclide moment mean -0 6 1 1 total P0 0 -1 6 1 1 total P1 0 -2 6 1 1 total P2 0 -3 6 1 1 total P3 0 material group out nuclide mean std. dev. +0 6 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 6 1 1 total P0 0 0 +1 6 1 1 total P1 0 0 +2 6 1 1 total P2 0 0 +3 6 1 1 total P3 0 0 material group out nuclide mean std. dev. 0 6 1 total 0 0 material group in nuclide mean std. dev. 0 7 1 total 0 0 material group in nuclide mean std. dev. -0 7 1 total 0 0 material group in group out nuclide moment mean -0 7 1 1 total P0 0 -1 7 1 1 total P1 0 -2 7 1 1 total P2 0 -3 7 1 1 total P3 0 material group out nuclide mean std. dev. +0 7 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 7 1 1 total P0 0 0 +1 7 1 1 total P1 0 0 +2 7 1 1 total P2 0 0 +3 7 1 1 total P3 0 0 material group out nuclide mean std. dev. 0 7 1 total 0 0 material group in nuclide mean std. dev. 0 8 1 total 0 0 material group in nuclide mean std. dev. -0 8 1 total 0 0 material group in group out nuclide moment mean -0 8 1 1 total P0 0 -1 8 1 1 total P1 0 -2 8 1 1 total P2 0 -3 8 1 1 total P3 0 material group out nuclide mean std. dev. +0 8 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 8 1 1 total P0 0 0 +1 8 1 1 total P1 0 0 +2 8 1 1 total P2 0 0 +3 8 1 1 total P3 0 0 material group out nuclide mean std. dev. 0 8 1 total 0 0 material group in nuclide mean std. dev. 0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0 0 material group in group out nuclide moment mean -0 9 1 1 total P0 0.720380 -1 9 1 1 total P1 0.119844 -2 9 1 1 total P2 0.038522 -3 9 1 1 total P3 0.056023 material group out nuclide mean std. dev. +0 9 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 9 1 1 total P0 0.720380 0.771015 +1 9 1 1 total P1 0.119844 0.184691 +2 9 1 1 total P2 0.038522 0.064485 +3 9 1 1 total P3 0.056023 0.050595 material group out nuclide mean std. dev. 0 9 1 total 0 0 material group in nuclide mean std. dev. 0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0 0 material group in group out nuclide moment mean -0 10 1 1 total P0 0.501009 -1 10 1 1 total P1 0.265494 -2 10 1 1 total P2 0.141979 -3 10 1 1 total P3 0.074258 material group out nuclide mean std. dev. +0 10 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 10 1 1 total P0 0.501009 0.708534 +1 10 1 1 total P1 0.265494 0.375465 +2 10 1 1 total P2 0.141979 0.200788 +3 10 1 1 total P3 0.074258 0.105017 material group out nuclide mean std. dev. 0 10 1 total 0 0 material group in nuclide mean std. dev. 0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0 0 material group in group out nuclide moment mean -0 11 1 1 total P0 0.804661 -1 11 1 1 total P1 0.312803 -2 11 1 1 total P2 0.168113 -3 11 1 1 total P3 0.003808 material group out nuclide mean std. dev. +0 11 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 11 1 1 total P0 0.804661 0.817658 +1 11 1 1 total P1 0.312803 0.315315 +2 11 1 1 total P2 0.168113 0.172935 +3 11 1 1 total P3 0.003808 0.037911 material group out nuclide mean std. dev. 0 11 1 total 0 0 material group in nuclide mean std. dev. 0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0 0 material group in group out nuclide moment mean -0 12 1 1 total P0 0.943429 -1 12 1 1 total P1 0.220164 -2 12 1 1 total P2 0.052884 -3 12 1 1 total P3 0.039939 material group out nuclide mean std. dev. +0 12 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 12 1 1 total P0 0.943429 0.856119 +1 12 1 1 total P1 0.220164 0.163180 +2 12 1 1 total P2 0.052884 0.042440 +3 12 1 1 total P3 0.039939 0.032867 material group out nuclide mean std. dev. 0 12 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index 318ec408a..ba9eaa71e 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,8 +1,8 @@ avg(distribcell) group in nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 -1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 -2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 -3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 avg(distribcell) group out nuclide mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 0.570131 +1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322 +2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504 +3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621 avg(distribcell) group out nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 9d6e35871..5e55a4c74 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -2,264 +2,264 @@ 1 1 1 total 0.372745 0.024269 0 1 2 total 0.861607 0.032349 material group in nuclide mean std. dev. 1 1 1 total 0.021789 0.001182 -0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean -12 1 1 1 total P0 0.381546 -13 1 1 1 total P1 0.044301 -14 1 1 1 total P2 0.020646 -15 1 1 1 total P3 0.013695 -8 1 1 2 total P0 0.001559 -9 1 1 2 total P1 -0.000597 -10 1 1 2 total P2 -0.000239 -11 1 1 2 total P3 0.000176 -4 1 2 1 total P0 0.000000 -5 1 2 1 total P1 0.000000 -6 1 2 1 total P2 0.000000 -7 1 2 1 total P3 0.000000 -0 1 2 2 total P0 0.403916 -1 1 2 2 total P1 -0.011310 -2 1 2 2 total P2 -0.014807 -3 1 2 2 total P3 -0.006855 material group out nuclide mean std. dev. +0 1 2 total 0.714077 0.040552 material group in group out nuclide moment mean std. dev. +12 1 1 1 total P0 0.381546 0.024033 +13 1 1 1 total P1 0.044301 0.004722 +14 1 1 1 total P2 0.020646 0.002539 +15 1 1 1 total P3 0.013695 0.002224 +8 1 1 2 total P0 0.001559 0.000510 +9 1 1 2 total P1 -0.000597 0.000225 +10 1 1 2 total P2 -0.000239 0.000222 +11 1 1 2 total P3 0.000176 0.000209 +4 1 2 1 total P0 0.000000 0.000000 +5 1 2 1 total P1 0.000000 0.000000 +6 1 2 1 total P2 0.000000 0.000000 +7 1 2 1 total P3 0.000000 0.000000 +0 1 2 2 total P0 0.403916 0.018966 +1 1 2 2 total P1 -0.011310 0.007839 +2 1 2 2 total P2 -0.014807 0.008629 +3 1 2 2 total P3 -0.006855 0.009047 material group out nuclide mean std. dev. 1 1 1 total 1 0.055333 0 1 2 total 0 0.000000 material group in nuclide mean std. dev. 1 2 1 total 0.237254 0.008184 0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. 1 2 1 total 0 0 -0 2 2 total 0 0 material group in group out nuclide moment mean -12 2 1 1 total P0 0.273115 -13 2 1 1 total P1 0.035861 -14 2 1 1 total P2 0.029704 -15 2 1 1 total P3 0.002249 -8 2 1 2 total P0 0.000000 -9 2 1 2 total P1 0.000000 -10 2 1 2 total P2 0.000000 -11 2 1 2 total P3 0.000000 -4 2 2 1 total P0 0.000000 -5 2 2 1 total P1 0.000000 -6 2 2 1 total P2 0.000000 -7 2 2 1 total P3 0.000000 -0 2 2 2 total P0 0.264051 -1 2 2 2 total P1 -0.021880 -2 2 2 2 total P2 -0.015295 -3 2 2 2 total P3 0.014034 material group out nuclide mean std. dev. +0 2 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 2 1 1 total P0 0.273115 0.006253 +13 2 1 1 total P1 0.035861 0.005878 +14 2 1 1 total P2 0.029704 0.006640 +15 2 1 1 total P3 0.002249 0.003376 +8 2 1 2 total P0 0.000000 0.000000 +9 2 1 2 total P1 0.000000 0.000000 +10 2 1 2 total P2 0.000000 0.000000 +11 2 1 2 total P3 0.000000 0.000000 +4 2 2 1 total P0 0.000000 0.000000 +5 2 2 1 total P1 0.000000 0.000000 +6 2 2 1 total P2 0.000000 0.000000 +7 2 2 1 total P3 0.000000 0.000000 +0 2 2 2 total P0 0.264051 0.045397 +1 2 2 2 total P1 -0.021880 0.012218 +2 2 2 2 total P2 -0.015295 0.010276 +3 2 2 2 total P3 0.014034 0.014318 material group out nuclide mean std. dev. 1 2 1 total 0 0 0 2 2 total 0 0 material group in nuclide mean std. dev. 1 3 1 total 0.286906 0.027401 0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. 1 3 1 total 0 0 -0 3 2 total 0 0 material group in group out nuclide moment mean -12 3 1 1 total P0 0.643346 -13 3 1 1 total P1 0.383409 -14 3 1 1 total P2 0.152185 -15 3 1 1 total P3 0.003037 -8 3 1 2 total P0 0.026187 -9 3 1 2 total P1 0.007362 -10 3 1 2 total P2 -0.002738 -11 3 1 2 total P3 -0.002720 -4 3 2 1 total P0 0.000000 -5 3 2 1 total P1 0.000000 -6 3 2 1 total P2 0.000000 -7 3 2 1 total P3 0.000000 -0 3 2 2 total P0 1.924214 -1 3 2 2 total P1 0.498431 -2 3 2 2 total P2 0.091205 -3 3 2 2 total P3 0.017054 material group out nuclide mean std. dev. +0 3 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 3 1 1 total P0 0.643346 0.028376 +13 3 1 1 total P1 0.383409 0.016447 +14 3 1 1 total P2 0.152185 0.009574 +15 3 1 1 total P3 0.003037 0.004648 +8 3 1 2 total P0 0.026187 0.001665 +9 3 1 2 total P1 0.007362 0.000934 +10 3 1 2 total P2 -0.002738 0.000756 +11 3 1 2 total P3 -0.002720 0.000558 +4 3 2 1 total P0 0.000000 0.000000 +5 3 2 1 total P1 0.000000 0.000000 +6 3 2 1 total P2 0.000000 0.000000 +7 3 2 1 total P3 0.000000 0.000000 +0 3 2 2 total P0 1.924214 0.284062 +1 3 2 2 total P1 0.498431 0.063421 +2 3 2 2 total P2 0.091205 0.013726 +3 3 2 2 total P3 0.017054 0.013916 material group out nuclide mean std. dev. 1 3 1 total 0 0 0 3 2 total 0 0 material group in nuclide mean std. dev. 1 4 1 total 0.242447 0.061031 0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. 1 4 1 total 0 0 -0 4 2 total 0 0 material group in group out nuclide moment mean -12 4 1 1 total P0 0.543941 -13 4 1 1 total P1 0.326011 -14 4 1 1 total P2 0.131133 -15 4 1 1 total P3 0.012105 -8 4 1 2 total P0 0.023662 -9 4 1 2 total P1 0.007526 -10 4 1 2 total P2 -0.002730 -11 4 1 2 total P3 -0.003140 -4 4 2 1 total P0 0.000000 -5 4 2 1 total P1 0.000000 -6 4 2 1 total P2 0.000000 -7 4 2 1 total P3 0.000000 -0 4 2 2 total P0 1.764648 -1 4 2 2 total P1 0.500695 -2 4 2 2 total P2 0.099026 -3 4 2 2 total P3 0.032975 material group out nuclide mean std. dev. +0 4 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 4 1 1 total P0 0.543941 0.065427 +13 4 1 1 total P1 0.326011 0.038602 +14 4 1 1 total P2 0.131133 0.017475 +15 4 1 1 total P3 0.012105 0.006073 +8 4 1 2 total P0 0.023662 0.003083 +9 4 1 2 total P1 0.007526 0.001301 +10 4 1 2 total P2 -0.002730 0.000841 +11 4 1 2 total P3 -0.003140 0.000578 +4 4 2 1 total P0 0.000000 0.000000 +5 4 2 1 total P1 0.000000 0.000000 +6 4 2 1 total P2 0.000000 0.000000 +7 4 2 1 total P3 0.000000 0.000000 +0 4 2 2 total P0 1.764648 0.416210 +1 4 2 2 total P1 0.500695 0.122178 +2 4 2 2 total P2 0.099026 0.038719 +3 4 2 2 total P3 0.032975 0.025103 material group out nuclide mean std. dev. 1 4 1 total 0 0 0 4 2 total 0 0 material group in nuclide mean std. dev. 1 5 1 total 0 0 0 5 2 total 0 0 material group in nuclide mean std. dev. 1 5 1 total 0 0 -0 5 2 total 0 0 material group in group out nuclide moment mean -12 5 1 1 total P0 0 -13 5 1 1 total P1 0 -14 5 1 1 total P2 0 -15 5 1 1 total P3 0 -8 5 1 2 total P0 0 -9 5 1 2 total P1 0 -10 5 1 2 total P2 0 -11 5 1 2 total P3 0 -4 5 2 1 total P0 0 -5 5 2 1 total P1 0 -6 5 2 1 total P2 0 -7 5 2 1 total P3 0 -0 5 2 2 total P0 0 -1 5 2 2 total P1 0 -2 5 2 2 total P2 0 -3 5 2 2 total P3 0 material group out nuclide mean std. dev. +0 5 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 5 1 1 total P0 0 0 +13 5 1 1 total P1 0 0 +14 5 1 1 total P2 0 0 +15 5 1 1 total P3 0 0 +8 5 1 2 total P0 0 0 +9 5 1 2 total P1 0 0 +10 5 1 2 total P2 0 0 +11 5 1 2 total P3 0 0 +4 5 2 1 total P0 0 0 +5 5 2 1 total P1 0 0 +6 5 2 1 total P2 0 0 +7 5 2 1 total P3 0 0 +0 5 2 2 total P0 0 0 +1 5 2 2 total P1 0 0 +2 5 2 2 total P2 0 0 +3 5 2 2 total P3 0 0 material group out nuclide mean std. dev. 1 5 1 total 0 0 0 5 2 total 0 0 material group in nuclide mean std. dev. 1 6 1 total 0 0 0 6 2 total 0 0 material group in nuclide mean std. dev. 1 6 1 total 0 0 -0 6 2 total 0 0 material group in group out nuclide moment mean -12 6 1 1 total P0 0 -13 6 1 1 total P1 0 -14 6 1 1 total P2 0 -15 6 1 1 total P3 0 -8 6 1 2 total P0 0 -9 6 1 2 total P1 0 -10 6 1 2 total P2 0 -11 6 1 2 total P3 0 -4 6 2 1 total P0 0 -5 6 2 1 total P1 0 -6 6 2 1 total P2 0 -7 6 2 1 total P3 0 -0 6 2 2 total P0 0 -1 6 2 2 total P1 0 -2 6 2 2 total P2 0 -3 6 2 2 total P3 0 material group out nuclide mean std. dev. +0 6 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 6 1 1 total P0 0 0 +13 6 1 1 total P1 0 0 +14 6 1 1 total P2 0 0 +15 6 1 1 total P3 0 0 +8 6 1 2 total P0 0 0 +9 6 1 2 total P1 0 0 +10 6 1 2 total P2 0 0 +11 6 1 2 total P3 0 0 +4 6 2 1 total P0 0 0 +5 6 2 1 total P1 0 0 +6 6 2 1 total P2 0 0 +7 6 2 1 total P3 0 0 +0 6 2 2 total P0 0 0 +1 6 2 2 total P1 0 0 +2 6 2 2 total P2 0 0 +3 6 2 2 total P3 0 0 material group out nuclide mean std. dev. 1 6 1 total 0 0 0 6 2 total 0 0 material group in nuclide mean std. dev. 1 7 1 total 0 0 0 7 2 total 0 0 material group in nuclide mean std. dev. 1 7 1 total 0 0 -0 7 2 total 0 0 material group in group out nuclide moment mean -12 7 1 1 total P0 0 -13 7 1 1 total P1 0 -14 7 1 1 total P2 0 -15 7 1 1 total P3 0 -8 7 1 2 total P0 0 -9 7 1 2 total P1 0 -10 7 1 2 total P2 0 -11 7 1 2 total P3 0 -4 7 2 1 total P0 0 -5 7 2 1 total P1 0 -6 7 2 1 total P2 0 -7 7 2 1 total P3 0 -0 7 2 2 total P0 0 -1 7 2 2 total P1 0 -2 7 2 2 total P2 0 -3 7 2 2 total P3 0 material group out nuclide mean std. dev. +0 7 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 7 1 1 total P0 0 0 +13 7 1 1 total P1 0 0 +14 7 1 1 total P2 0 0 +15 7 1 1 total P3 0 0 +8 7 1 2 total P0 0 0 +9 7 1 2 total P1 0 0 +10 7 1 2 total P2 0 0 +11 7 1 2 total P3 0 0 +4 7 2 1 total P0 0 0 +5 7 2 1 total P1 0 0 +6 7 2 1 total P2 0 0 +7 7 2 1 total P3 0 0 +0 7 2 2 total P0 0 0 +1 7 2 2 total P1 0 0 +2 7 2 2 total P2 0 0 +3 7 2 2 total P3 0 0 material group out nuclide mean std. dev. 1 7 1 total 0 0 0 7 2 total 0 0 material group in nuclide mean std. dev. 1 8 1 total 0 0 0 8 2 total 0 0 material group in nuclide mean std. dev. 1 8 1 total 0 0 -0 8 2 total 0 0 material group in group out nuclide moment mean -12 8 1 1 total P0 0 -13 8 1 1 total P1 0 -14 8 1 1 total P2 0 -15 8 1 1 total P3 0 -8 8 1 2 total P0 0 -9 8 1 2 total P1 0 -10 8 1 2 total P2 0 -11 8 1 2 total P3 0 -4 8 2 1 total P0 0 -5 8 2 1 total P1 0 -6 8 2 1 total P2 0 -7 8 2 1 total P3 0 -0 8 2 2 total P0 0 -1 8 2 2 total P1 0 -2 8 2 2 total P2 0 -3 8 2 2 total P3 0 material group out nuclide mean std. dev. +0 8 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 8 1 1 total P0 0 0 +13 8 1 1 total P1 0 0 +14 8 1 1 total P2 0 0 +15 8 1 1 total P3 0 0 +8 8 1 2 total P0 0 0 +9 8 1 2 total P1 0 0 +10 8 1 2 total P2 0 0 +11 8 1 2 total P3 0 0 +4 8 2 1 total P0 0 0 +5 8 2 1 total P1 0 0 +6 8 2 1 total P2 0 0 +7 8 2 1 total P3 0 0 +0 8 2 2 total P0 0 0 +1 8 2 2 total P1 0 0 +2 8 2 2 total P2 0 0 +3 8 2 2 total P3 0 0 material group out nuclide mean std. dev. 1 8 1 total 0 0 0 8 2 total 0 0 material group in nuclide mean std. dev. 1 9 1 total 0.600536 0.748875 0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. 1 9 1 total 0 0 -0 9 2 total 0 0 material group in group out nuclide moment mean -12 9 1 1 total P0 0.720380 -13 9 1 1 total P1 0.119844 -14 9 1 1 total P2 0.038522 -15 9 1 1 total P3 0.056023 -8 9 1 2 total P0 0.000000 -9 9 1 2 total P1 0.000000 -10 9 1 2 total P2 0.000000 -11 9 1 2 total P3 0.000000 -4 9 2 1 total P0 0.000000 -5 9 2 1 total P1 0.000000 -6 9 2 1 total P2 0.000000 -7 9 2 1 total P3 0.000000 -0 9 2 2 total P0 0.000000 -1 9 2 2 total P1 0.000000 -2 9 2 2 total P2 0.000000 -3 9 2 2 total P3 0.000000 material group out nuclide mean std. dev. +0 9 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 9 1 1 total P0 0.720380 0.771015 +13 9 1 1 total P1 0.119844 0.184691 +14 9 1 1 total P2 0.038522 0.064485 +15 9 1 1 total P3 0.056023 0.050595 +8 9 1 2 total P0 0.000000 0.000000 +9 9 1 2 total P1 0.000000 0.000000 +10 9 1 2 total P2 0.000000 0.000000 +11 9 1 2 total P3 0.000000 0.000000 +4 9 2 1 total P0 0.000000 0.000000 +5 9 2 1 total P1 0.000000 0.000000 +6 9 2 1 total P2 0.000000 0.000000 +7 9 2 1 total P3 0.000000 0.000000 +0 9 2 2 total P0 0.000000 0.000000 +1 9 2 2 total P1 0.000000 0.000000 +2 9 2 2 total P2 0.000000 0.000000 +3 9 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev. 1 9 1 total 0 0 0 9 2 total 0 0 material group in nuclide mean std. dev. 1 10 1 total 0.235515 0.613974 0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. 1 10 1 total 0 0 -0 10 2 total 0 0 material group in group out nuclide moment mean -12 10 1 1 total P0 0.501009 -13 10 1 1 total P1 0.265494 -14 10 1 1 total P2 0.141979 -15 10 1 1 total P3 0.074258 -8 10 1 2 total P0 0.000000 -9 10 1 2 total P1 0.000000 -10 10 1 2 total P2 0.000000 -11 10 1 2 total P3 0.000000 -4 10 2 1 total P0 0.000000 -5 10 2 1 total P1 0.000000 -6 10 2 1 total P2 0.000000 -7 10 2 1 total P3 0.000000 -0 10 2 2 total P0 0.000000 -1 10 2 2 total P1 0.000000 -2 10 2 2 total P2 0.000000 -3 10 2 2 total P3 0.000000 material group out nuclide mean std. dev. +0 10 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 10 1 1 total P0 0.501009 0.708534 +13 10 1 1 total P1 0.265494 0.375465 +14 10 1 1 total P2 0.141979 0.200788 +15 10 1 1 total P3 0.074258 0.105017 +8 10 1 2 total P0 0.000000 0.000000 +9 10 1 2 total P1 0.000000 0.000000 +10 10 1 2 total P2 0.000000 0.000000 +11 10 1 2 total P3 0.000000 0.000000 +4 10 2 1 total P0 0.000000 0.000000 +5 10 2 1 total P1 0.000000 0.000000 +6 10 2 1 total P2 0.000000 0.000000 +7 10 2 1 total P3 0.000000 0.000000 +0 10 2 2 total P0 0.000000 0.000000 +1 10 2 2 total P1 0.000000 0.000000 +2 10 2 2 total P2 0.000000 0.000000 +3 10 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev. 1 10 1 total 0 0 0 10 2 total 0 0 material group in nuclide mean std. dev. 1 11 1 total 0.186324 0.632129 0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. 1 11 1 total 0 0 -0 11 2 total 0 0 material group in group out nuclide moment mean -12 11 1 1 total P0 0.478128 -13 11 1 1 total P1 0.323679 -14 11 1 1 total P2 0.143375 -15 11 1 1 total P3 0.054003 -8 11 1 2 total P0 0.031875 -9 11 1 2 total P1 0.008585 -10 11 1 2 total P2 -0.012470 -11 11 1 2 total P3 -0.011320 -4 11 2 1 total P0 0.000000 -5 11 2 1 total P1 0.000000 -6 11 2 1 total P2 0.000000 -7 11 2 1 total P3 0.000000 -0 11 2 2 total P0 1.201250 -1 11 2 2 total P1 0.286611 -2 11 2 2 total P2 0.218191 -3 11 2 2 total P3 -0.048514 material group out nuclide mean std. dev. +0 11 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 11 1 1 total P0 0.478128 0.676174 +13 11 1 1 total P1 0.323679 0.457751 +14 11 1 1 total P2 0.143375 0.202763 +15 11 1 1 total P3 0.054003 0.076372 +8 11 1 2 total P0 0.031875 0.045078 +9 11 1 2 total P1 0.008585 0.012140 +10 11 1 2 total P2 -0.012470 0.017635 +11 11 1 2 total P3 -0.011320 0.016009 +4 11 2 1 total P0 0.000000 0.000000 +5 11 2 1 total P1 0.000000 0.000000 +6 11 2 1 total P2 0.000000 0.000000 +7 11 2 1 total P3 0.000000 0.000000 +0 11 2 2 total P0 1.201250 1.698824 +1 11 2 2 total P1 0.286611 0.405329 +2 11 2 2 total P2 0.218191 0.308569 +3 11 2 2 total P3 -0.048514 0.068609 material group out nuclide mean std. dev. 1 11 1 total 0 0 0 11 2 total 0 0 material group in nuclide mean std. dev. 1 12 1 total 0.213292 0.271444 0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. 1 12 1 total 0 0 -0 12 2 total 0 0 material group in group out nuclide moment mean -12 12 1 1 total P0 0.408594 -13 12 1 1 total P1 0.222541 -14 12 1 1 total P2 0.090972 -15 12 1 1 total P3 0.031004 -8 12 1 2 total P0 0.027240 -9 12 1 2 total P1 -0.010088 -10 12 1 2 total P2 -0.006946 -11 12 1 2 total P3 0.009692 -4 12 2 1 total P0 0.000000 -5 12 2 1 total P1 0.000000 -6 12 2 1 total P2 0.000000 -7 12 2 1 total P3 0.000000 -0 12 2 2 total P0 1.574328 -1 12 2 2 total P1 0.229748 -2 12 2 2 total P2 0.014178 -3 12 2 2 total P3 0.038997 material group out nuclide mean std. dev. +0 12 2 total 0 0 material group in group out nuclide moment mean std. dev. +12 12 1 1 total P0 0.408594 0.278123 +13 12 1 1 total P1 0.222541 0.145776 +14 12 1 1 total P2 0.090972 0.069626 +15 12 1 1 total P3 0.031004 0.035981 +8 12 1 2 total P0 0.027240 0.029555 +9 12 1 2 total P1 -0.010088 0.010945 +10 12 1 2 total P2 -0.006946 0.007537 +11 12 1 2 total P3 0.009692 0.010516 +4 12 2 1 total P0 0.000000 0.000000 +5 12 2 1 total P1 0.000000 0.000000 +6 12 2 1 total P2 0.000000 0.000000 +7 12 2 1 total P3 0.000000 0.000000 +0 12 2 2 total P0 1.574328 2.226436 +1 12 2 2 total P1 0.229748 0.324913 +2 12 2 2 total P2 0.014178 0.020051 +3 12 2 2 total P3 0.038997 0.055150 material group out nuclide mean std. dev. 1 12 1 total 0 0 0 12 2 total 0 0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index 20d2d8d5a..1fcfe4aef 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -1,4335 +1 @@ - material group in nuclide mean std. dev. -34 1 1 U-234 0.000173 0.000173 -35 1 1 U-235 0.010677 0.001889 -36 1 1 U-236 0.002390 0.001055 -37 1 1 U-238 0.213680 0.013272 -38 1 1 Np-237 0.000000 0.000000 -39 1 1 Pu-238 0.000000 0.000000 -40 1 1 Pu-239 0.002911 0.000639 -41 1 1 Pu-240 0.004426 0.000806 -42 1 1 Pu-241 0.000690 0.000387 -43 1 1 Pu-242 0.000000 0.000000 -44 1 1 Am-241 0.000173 0.000173 -45 1 1 Am-242m 0.000000 0.000000 -46 1 1 Am-243 0.000000 0.000000 -47 1 1 Cm-242 0.000000 0.000000 -48 1 1 Cm-243 0.000000 0.000000 -49 1 1 Cm-244 0.000000 0.000000 -50 1 1 Cm-245 0.000000 0.000000 -51 1 1 Mo-95 0.000000 0.000000 -52 1 1 Tc-99 0.000173 0.000173 -53 1 1 Ru-101 0.000238 0.000254 -54 1 1 Ru-103 0.000002 0.000243 -55 1 1 Ag-109 0.000000 0.000000 -56 1 1 Xe-135 0.000000 0.000000 -57 1 1 Cs-133 0.000347 0.000213 -58 1 1 Nd-143 0.000447 0.000292 -59 1 1 Nd-145 0.000564 0.000294 -60 1 1 Sm-147 0.000000 0.000000 -61 1 1 Sm-149 0.000000 0.000000 -62 1 1 Sm-150 0.000472 0.000239 -63 1 1 Sm-151 0.000000 0.000000 -64 1 1 Sm-152 0.000492 0.000352 -65 1 1 Eu-153 0.000173 0.000173 -66 1 1 Gd-155 0.000000 0.000000 -67 1 1 O-16 0.134715 0.009801 -0 1 2 U-234 0.000000 0.000000 -1 1 2 U-235 0.199907 0.007776 -2 1 2 U-236 0.001501 0.002037 -3 1 2 U-238 0.255355 0.029743 -4 1 2 Np-237 0.000000 0.000000 -5 1 2 Pu-238 0.000000 0.000000 -6 1 2 Pu-239 0.160378 0.011366 -7 1 2 Pu-240 0.007920 0.003710 -8 1 2 Pu-241 0.017820 0.003733 -9 1 2 Pu-242 0.000000 0.000000 -10 1 2 Am-241 0.000000 0.000000 -11 1 2 Am-242m 0.000000 0.000000 -12 1 2 Am-243 0.000000 0.000000 -13 1 2 Cm-242 0.000000 0.000000 -14 1 2 Cm-243 0.000000 0.000000 -15 1 2 Cm-244 0.000000 0.000000 -16 1 2 Cm-245 0.000000 0.000000 -17 1 2 Mo-95 0.000000 0.000000 -18 1 2 Tc-99 0.000000 0.000000 -19 1 2 Ru-101 0.000000 0.000000 -20 1 2 Ru-103 0.000000 0.000000 -21 1 2 Ag-109 0.000000 0.000000 -22 1 2 Xe-135 0.013860 0.003976 -23 1 2 Cs-133 0.000000 0.000000 -24 1 2 Nd-143 0.003960 0.002427 -25 1 2 Nd-145 0.000000 0.000000 -26 1 2 Sm-147 0.000000 0.000000 -27 1 2 Sm-149 0.001980 0.001981 -28 1 2 Sm-150 0.000000 0.000000 -29 1 2 Sm-151 0.001980 0.001981 -30 1 2 Sm-152 0.000000 0.000000 -31 1 2 Eu-153 0.000000 0.000000 -32 1 2 Gd-155 0.000000 0.000000 -33 1 2 O-16 0.196946 0.014729 material group in nuclide mean std. dev. -34 1 1 U-234 7.274440e-06 4.419477e-07 -35 1 1 U-235 9.587803e-03 5.936922e-04 -36 1 1 U-236 7.566099e-05 7.523935e-06 -37 1 1 U-238 7.178367e-03 6.505680e-04 -38 1 1 Np-237 1.315682e-05 8.036501e-07 -39 1 1 Pu-238 7.746151e-06 3.992835e-07 -40 1 1 Pu-239 3.805294e-03 3.637600e-04 -41 1 1 Pu-240 6.941319e-05 4.729737e-06 -42 1 1 Pu-241 1.033844e-03 9.083913e-05 -43 1 1 Pu-242 5.995332e-06 3.821721e-07 -44 1 1 Am-241 1.148585e-06 8.271648e-08 -45 1 1 Am-242m 1.100215e-06 6.159956e-08 -46 1 1 Am-243 8.323826e-07 5.841792e-08 -47 1 1 Cm-242 5.088970e-07 5.258007e-08 -48 1 1 Cm-243 2.245435e-07 1.459025e-08 -49 1 1 Cm-244 2.993206e-07 2.746129e-08 -50 1 1 Cm-245 3.063611e-07 3.057751e-08 -51 1 1 Mo-95 0.000000e+00 0.000000e+00 -52 1 1 Tc-99 0.000000e+00 0.000000e+00 -53 1 1 Ru-101 0.000000e+00 0.000000e+00 -54 1 1 Ru-103 0.000000e+00 0.000000e+00 -55 1 1 Ag-109 0.000000e+00 0.000000e+00 -56 1 1 Xe-135 0.000000e+00 0.000000e+00 -57 1 1 Cs-133 0.000000e+00 0.000000e+00 -58 1 1 Nd-143 0.000000e+00 0.000000e+00 -59 1 1 Nd-145 0.000000e+00 0.000000e+00 -60 1 1 Sm-147 0.000000e+00 0.000000e+00 -61 1 1 Sm-149 0.000000e+00 0.000000e+00 -62 1 1 Sm-150 0.000000e+00 0.000000e+00 -63 1 1 Sm-151 0.000000e+00 0.000000e+00 -64 1 1 Sm-152 0.000000e+00 0.000000e+00 -65 1 1 Eu-153 0.000000e+00 0.000000e+00 -66 1 1 Gd-155 0.000000e+00 0.000000e+00 -67 1 1 O-16 0.000000e+00 0.000000e+00 -0 1 2 U-234 4.408576e-07 2.828309e-08 -1 1 2 U-235 3.768094e-01 2.445671e-02 -2 1 2 U-236 6.097538e-06 3.733038e-07 -3 1 2 U-238 5.353074e-07 3.310544e-08 -4 1 2 Np-237 2.702971e-07 2.098939e-08 -5 1 2 Pu-238 3.463109e-05 2.638394e-06 -6 1 2 Pu-239 2.889643e-01 1.376004e-02 -7 1 2 Pu-240 4.533642e-06 2.544289e-07 -8 1 2 Pu-241 4.809366e-02 2.778345e-03 -9 1 2 Pu-242 8.715325e-08 5.460893e-09 -10 1 2 Am-241 4.611736e-06 2.155039e-07 -11 1 2 Am-242m 1.428047e-04 8.436437e-06 -12 1 2 Am-243 7.883895e-08 4.734503e-09 -13 1 2 Cm-242 9.731025e-07 6.143750e-08 -14 1 2 Cm-243 1.825830e-06 1.074849e-07 -15 1 2 Cm-244 1.581823e-07 9.938064e-09 -16 1 2 Cm-245 1.213386e-05 8.812019e-07 -17 1 2 Mo-95 0.000000e+00 0.000000e+00 -18 1 2 Tc-99 0.000000e+00 0.000000e+00 -19 1 2 Ru-101 0.000000e+00 0.000000e+00 -20 1 2 Ru-103 0.000000e+00 0.000000e+00 -21 1 2 Ag-109 0.000000e+00 0.000000e+00 -22 1 2 Xe-135 0.000000e+00 0.000000e+00 -23 1 2 Cs-133 0.000000e+00 0.000000e+00 -24 1 2 Nd-143 0.000000e+00 0.000000e+00 -25 1 2 Nd-145 0.000000e+00 0.000000e+00 -26 1 2 Sm-147 0.000000e+00 0.000000e+00 -27 1 2 Sm-149 0.000000e+00 0.000000e+00 -28 1 2 Sm-150 0.000000e+00 0.000000e+00 -29 1 2 Sm-151 0.000000e+00 0.000000e+00 -30 1 2 Sm-152 0.000000e+00 0.000000e+00 -31 1 2 Eu-153 0.000000e+00 0.000000e+00 -32 1 2 Gd-155 0.000000e+00 0.000000e+00 -33 1 2 O-16 0.000000e+00 0.000000e+00 material group in group out nuclide moment mean -408 1 1 1 U-234 P0 0.000000 -409 1 1 1 U-234 P1 0.000000 -410 1 1 1 U-234 P2 0.000000 -411 1 1 1 U-234 P3 0.000000 -412 1 1 1 U-235 P0 0.003812 -413 1 1 1 U-235 P1 0.000586 -414 1 1 1 U-235 P2 0.000071 -415 1 1 1 U-235 P3 0.000277 -416 1 1 1 U-236 P0 0.001733 -417 1 1 1 U-236 P1 0.000035 -418 1 1 1 U-236 P2 -0.000183 -419 1 1 1 U-236 P3 -0.000087 -420 1 1 1 U-238 P0 0.224908 -421 1 1 1 U-238 P1 0.030440 -422 1 1 1 U-238 P2 0.014265 -423 1 1 1 U-238 P3 0.007698 -424 1 1 1 Np-237 P0 0.000000 -425 1 1 1 Np-237 P1 0.000000 -426 1 1 1 Np-237 P2 0.000000 -427 1 1 1 Np-237 P3 0.000000 -428 1 1 1 Pu-238 P0 0.000000 -429 1 1 1 Pu-238 P1 0.000000 -430 1 1 1 Pu-238 P2 0.000000 -431 1 1 1 Pu-238 P3 0.000000 -432 1 1 1 Pu-239 P0 0.001040 -433 1 1 1 Pu-239 P1 0.000034 -434 1 1 1 Pu-239 P2 0.000090 -435 1 1 1 Pu-239 P3 0.000110 -436 1 1 1 Pu-240 P0 0.001040 -437 1 1 1 Pu-240 P1 -0.000268 -438 1 1 1 Pu-240 P2 -0.000137 -439 1 1 1 Pu-240 P3 0.000132 -440 1 1 1 Pu-241 P0 0.000173 -441 1 1 1 Pu-241 P1 -0.000170 -442 1 1 1 Pu-241 P2 0.000165 -443 1 1 1 Pu-241 P3 -0.000156 -444 1 1 1 Pu-242 P0 0.000000 -445 1 1 1 Pu-242 P1 0.000000 -446 1 1 1 Pu-242 P2 0.000000 -447 1 1 1 Pu-242 P3 0.000000 -448 1 1 1 Am-241 P0 0.000000 -449 1 1 1 Am-241 P1 0.000000 -450 1 1 1 Am-241 P2 0.000000 -451 1 1 1 Am-241 P3 0.000000 -452 1 1 1 Am-242m P0 0.000000 -453 1 1 1 Am-242m P1 0.000000 -454 1 1 1 Am-242m P2 0.000000 -455 1 1 1 Am-242m P3 0.000000 -456 1 1 1 Am-243 P0 0.000000 -457 1 1 1 Am-243 P1 0.000000 -458 1 1 1 Am-243 P2 0.000000 -459 1 1 1 Am-243 P3 0.000000 -460 1 1 1 Cm-242 P0 0.000000 -461 1 1 1 Cm-242 P1 0.000000 -462 1 1 1 Cm-242 P2 0.000000 -463 1 1 1 Cm-242 P3 0.000000 -464 1 1 1 Cm-243 P0 0.000000 -465 1 1 1 Cm-243 P1 0.000000 -466 1 1 1 Cm-243 P2 0.000000 -467 1 1 1 Cm-243 P3 0.000000 -468 1 1 1 Cm-244 P0 0.000000 -469 1 1 1 Cm-244 P1 0.000000 -470 1 1 1 Cm-244 P2 0.000000 -471 1 1 1 Cm-244 P3 0.000000 -472 1 1 1 Cm-245 P0 0.000000 -473 1 1 1 Cm-245 P1 0.000000 -474 1 1 1 Cm-245 P2 0.000000 -475 1 1 1 Cm-245 P3 0.000000 -476 1 1 1 Mo-95 P0 0.000000 -477 1 1 1 Mo-95 P1 0.000000 -478 1 1 1 Mo-95 P2 0.000000 -479 1 1 1 Mo-95 P3 0.000000 -480 1 1 1 Tc-99 P0 0.000000 -481 1 1 1 Tc-99 P1 0.000000 -482 1 1 1 Tc-99 P2 0.000000 -483 1 1 1 Tc-99 P3 0.000000 -484 1 1 1 Ru-101 P0 0.000347 -485 1 1 1 Ru-101 P1 0.000109 -486 1 1 1 Ru-101 P2 -0.000020 -487 1 1 1 Ru-101 P3 0.000023 -488 1 1 1 Ru-103 P0 0.000173 -489 1 1 1 Ru-103 P1 0.000171 -490 1 1 1 Ru-103 P2 0.000167 -491 1 1 1 Ru-103 P3 0.000160 -492 1 1 1 Ag-109 P0 0.000000 -493 1 1 1 Ag-109 P1 0.000000 -494 1 1 1 Ag-109 P2 0.000000 -495 1 1 1 Ag-109 P3 0.000000 -496 1 1 1 Xe-135 P0 0.000000 -497 1 1 1 Xe-135 P1 0.000000 -498 1 1 1 Xe-135 P2 0.000000 -499 1 1 1 Xe-135 P3 0.000000 -500 1 1 1 Cs-133 P0 0.000000 -501 1 1 1 Cs-133 P1 0.000000 -502 1 1 1 Cs-133 P2 0.000000 -503 1 1 1 Cs-133 P3 0.000000 -504 1 1 1 Nd-143 P0 0.000520 -505 1 1 1 Nd-143 P1 0.000073 -506 1 1 1 Nd-143 P2 0.000023 -507 1 1 1 Nd-143 P3 -0.000103 -508 1 1 1 Nd-145 P0 0.000520 -509 1 1 1 Nd-145 P1 -0.000044 -510 1 1 1 Nd-145 P2 0.000026 -511 1 1 1 Nd-145 P3 0.000126 -512 1 1 1 Sm-147 P0 0.000000 -513 1 1 1 Sm-147 P1 0.000000 -514 1 1 1 Sm-147 P2 0.000000 -515 1 1 1 Sm-147 P3 0.000000 -516 1 1 1 Sm-149 P0 0.000000 -517 1 1 1 Sm-149 P1 0.000000 -518 1 1 1 Sm-149 P2 0.000000 -519 1 1 1 Sm-149 P3 0.000000 -520 1 1 1 Sm-150 P0 0.000347 -521 1 1 1 Sm-150 P1 0.000048 -522 1 1 1 Sm-150 P2 -0.000090 -523 1 1 1 Sm-150 P3 -0.000019 -524 1 1 1 Sm-151 P0 0.000000 -525 1 1 1 Sm-151 P1 0.000000 -526 1 1 1 Sm-151 P2 0.000000 -527 1 1 1 Sm-151 P3 0.000000 -528 1 1 1 Sm-152 P0 0.000693 -529 1 1 1 Sm-152 P1 0.000201 -530 1 1 1 Sm-152 P2 -0.000044 -531 1 1 1 Sm-152 P3 0.000138 -532 1 1 1 Eu-153 P0 0.000000 -533 1 1 1 Eu-153 P1 0.000000 -534 1 1 1 Eu-153 P2 0.000000 -535 1 1 1 Eu-153 P3 0.000000 -536 1 1 1 Gd-155 P0 0.000000 -537 1 1 1 Gd-155 P1 0.000000 -538 1 1 1 Gd-155 P2 0.000000 -539 1 1 1 Gd-155 P3 0.000000 -540 1 1 1 O-16 P0 0.146242 -541 1 1 1 O-16 P1 0.013087 -542 1 1 1 O-16 P2 0.006314 -543 1 1 1 O-16 P3 0.005397 -272 1 1 2 U-234 P0 0.000000 -273 1 1 2 U-234 P1 0.000000 -274 1 1 2 U-234 P2 0.000000 -275 1 1 2 U-234 P3 0.000000 -276 1 1 2 U-235 P0 0.000000 -277 1 1 2 U-235 P1 0.000000 -278 1 1 2 U-235 P2 0.000000 -279 1 1 2 U-235 P3 0.000000 -280 1 1 2 U-236 P0 0.000000 -281 1 1 2 U-236 P1 0.000000 -282 1 1 2 U-236 P2 0.000000 -283 1 1 2 U-236 P3 0.000000 -284 1 1 2 U-238 P0 0.000173 -285 1 1 2 U-238 P1 -0.000038 -286 1 1 2 U-238 P2 -0.000074 -287 1 1 2 U-238 P3 0.000052 -288 1 1 2 Np-237 P0 0.000000 -289 1 1 2 Np-237 P1 0.000000 -290 1 1 2 Np-237 P2 0.000000 -291 1 1 2 Np-237 P3 0.000000 -292 1 1 2 Pu-238 P0 0.000000 -293 1 1 2 Pu-238 P1 0.000000 -294 1 1 2 Pu-238 P2 0.000000 -295 1 1 2 Pu-238 P3 0.000000 -296 1 1 2 Pu-239 P0 0.000000 -297 1 1 2 Pu-239 P1 0.000000 -298 1 1 2 Pu-239 P2 0.000000 -299 1 1 2 Pu-239 P3 0.000000 -300 1 1 2 Pu-240 P0 0.000000 -301 1 1 2 Pu-240 P1 0.000000 -302 1 1 2 Pu-240 P2 0.000000 -303 1 1 2 Pu-240 P3 0.000000 -304 1 1 2 Pu-241 P0 0.000000 -305 1 1 2 Pu-241 P1 0.000000 -306 1 1 2 Pu-241 P2 0.000000 -307 1 1 2 Pu-241 P3 0.000000 -308 1 1 2 Pu-242 P0 0.000000 -309 1 1 2 Pu-242 P1 0.000000 -310 1 1 2 Pu-242 P2 0.000000 -311 1 1 2 Pu-242 P3 0.000000 -312 1 1 2 Am-241 P0 0.000000 -313 1 1 2 Am-241 P1 0.000000 -314 1 1 2 Am-241 P2 0.000000 -315 1 1 2 Am-241 P3 0.000000 -316 1 1 2 Am-242m P0 0.000000 -317 1 1 2 Am-242m P1 0.000000 -318 1 1 2 Am-242m P2 0.000000 -319 1 1 2 Am-242m P3 0.000000 -320 1 1 2 Am-243 P0 0.000000 -321 1 1 2 Am-243 P1 0.000000 -322 1 1 2 Am-243 P2 0.000000 -323 1 1 2 Am-243 P3 0.000000 -324 1 1 2 Cm-242 P0 0.000000 -325 1 1 2 Cm-242 P1 0.000000 -326 1 1 2 Cm-242 P2 0.000000 -327 1 1 2 Cm-242 P3 0.000000 -328 1 1 2 Cm-243 P0 0.000000 -329 1 1 2 Cm-243 P1 0.000000 -330 1 1 2 Cm-243 P2 0.000000 -331 1 1 2 Cm-243 P3 0.000000 -332 1 1 2 Cm-244 P0 0.000000 -333 1 1 2 Cm-244 P1 0.000000 -334 1 1 2 Cm-244 P2 0.000000 -335 1 1 2 Cm-244 P3 0.000000 -336 1 1 2 Cm-245 P0 0.000000 -337 1 1 2 Cm-245 P1 0.000000 -338 1 1 2 Cm-245 P2 0.000000 -339 1 1 2 Cm-245 P3 0.000000 -340 1 1 2 Mo-95 P0 0.000000 -341 1 1 2 Mo-95 P1 0.000000 -342 1 1 2 Mo-95 P2 0.000000 -343 1 1 2 Mo-95 P3 0.000000 -344 1 1 2 Tc-99 P0 0.000000 -345 1 1 2 Tc-99 P1 0.000000 -346 1 1 2 Tc-99 P2 0.000000 -347 1 1 2 Tc-99 P3 0.000000 -348 1 1 2 Ru-101 P0 0.000000 -349 1 1 2 Ru-101 P1 0.000000 -350 1 1 2 Ru-101 P2 0.000000 -351 1 1 2 Ru-101 P3 0.000000 -352 1 1 2 Ru-103 P0 0.000000 -353 1 1 2 Ru-103 P1 0.000000 -354 1 1 2 Ru-103 P2 0.000000 -355 1 1 2 Ru-103 P3 0.000000 -356 1 1 2 Ag-109 P0 0.000000 -357 1 1 2 Ag-109 P1 0.000000 -358 1 1 2 Ag-109 P2 0.000000 -359 1 1 2 Ag-109 P3 0.000000 -360 1 1 2 Xe-135 P0 0.000000 -361 1 1 2 Xe-135 P1 0.000000 -362 1 1 2 Xe-135 P2 0.000000 -363 1 1 2 Xe-135 P3 0.000000 -364 1 1 2 Cs-133 P0 0.000000 -365 1 1 2 Cs-133 P1 0.000000 -366 1 1 2 Cs-133 P2 0.000000 -367 1 1 2 Cs-133 P3 0.000000 -368 1 1 2 Nd-143 P0 0.000000 -369 1 1 2 Nd-143 P1 0.000000 -370 1 1 2 Nd-143 P2 0.000000 -371 1 1 2 Nd-143 P3 0.000000 -372 1 1 2 Nd-145 P0 0.000000 -373 1 1 2 Nd-145 P1 0.000000 -374 1 1 2 Nd-145 P2 0.000000 -375 1 1 2 Nd-145 P3 0.000000 -376 1 1 2 Sm-147 P0 0.000000 -377 1 1 2 Sm-147 P1 0.000000 -378 1 1 2 Sm-147 P2 0.000000 -379 1 1 2 Sm-147 P3 0.000000 -380 1 1 2 Sm-149 P0 0.000000 -381 1 1 2 Sm-149 P1 0.000000 -382 1 1 2 Sm-149 P2 0.000000 -383 1 1 2 Sm-149 P3 0.000000 -384 1 1 2 Sm-150 P0 0.000000 -385 1 1 2 Sm-150 P1 0.000000 -386 1 1 2 Sm-150 P2 0.000000 -387 1 1 2 Sm-150 P3 0.000000 -388 1 1 2 Sm-151 P0 0.000000 -389 1 1 2 Sm-151 P1 0.000000 -390 1 1 2 Sm-151 P2 0.000000 -391 1 1 2 Sm-151 P3 0.000000 -392 1 1 2 Sm-152 P0 0.000000 -393 1 1 2 Sm-152 P1 0.000000 -394 1 1 2 Sm-152 P2 0.000000 -395 1 1 2 Sm-152 P3 0.000000 -396 1 1 2 Eu-153 P0 0.000000 -397 1 1 2 Eu-153 P1 0.000000 -398 1 1 2 Eu-153 P2 0.000000 -399 1 1 2 Eu-153 P3 0.000000 -400 1 1 2 Gd-155 P0 0.000000 -401 1 1 2 Gd-155 P1 0.000000 -402 1 1 2 Gd-155 P2 0.000000 -403 1 1 2 Gd-155 P3 0.000000 -404 1 1 2 O-16 P0 0.001386 -405 1 1 2 O-16 P1 -0.000559 -406 1 1 2 O-16 P2 -0.000165 -407 1 1 2 O-16 P3 0.000123 -136 1 2 1 U-234 P0 0.000000 -137 1 2 1 U-234 P1 0.000000 -138 1 2 1 U-234 P2 0.000000 -139 1 2 1 U-234 P3 0.000000 -140 1 2 1 U-235 P0 0.000000 -141 1 2 1 U-235 P1 0.000000 -142 1 2 1 U-235 P2 0.000000 -143 1 2 1 U-235 P3 0.000000 -144 1 2 1 U-236 P0 0.000000 -145 1 2 1 U-236 P1 0.000000 -146 1 2 1 U-236 P2 0.000000 -147 1 2 1 U-236 P3 0.000000 -148 1 2 1 U-238 P0 0.000000 -149 1 2 1 U-238 P1 0.000000 -150 1 2 1 U-238 P2 0.000000 -151 1 2 1 U-238 P3 0.000000 -152 1 2 1 Np-237 P0 0.000000 -153 1 2 1 Np-237 P1 0.000000 -154 1 2 1 Np-237 P2 0.000000 -155 1 2 1 Np-237 P3 0.000000 -156 1 2 1 Pu-238 P0 0.000000 -157 1 2 1 Pu-238 P1 0.000000 -158 1 2 1 Pu-238 P2 0.000000 -159 1 2 1 Pu-238 P3 0.000000 -160 1 2 1 Pu-239 P0 0.000000 -161 1 2 1 Pu-239 P1 0.000000 -162 1 2 1 Pu-239 P2 0.000000 -163 1 2 1 Pu-239 P3 0.000000 -164 1 2 1 Pu-240 P0 0.000000 -165 1 2 1 Pu-240 P1 0.000000 -166 1 2 1 Pu-240 P2 0.000000 -167 1 2 1 Pu-240 P3 0.000000 -168 1 2 1 Pu-241 P0 0.000000 -169 1 2 1 Pu-241 P1 0.000000 -170 1 2 1 Pu-241 P2 0.000000 -171 1 2 1 Pu-241 P3 0.000000 -172 1 2 1 Pu-242 P0 0.000000 -173 1 2 1 Pu-242 P1 0.000000 -174 1 2 1 Pu-242 P2 0.000000 -175 1 2 1 Pu-242 P3 0.000000 -176 1 2 1 Am-241 P0 0.000000 -177 1 2 1 Am-241 P1 0.000000 -178 1 2 1 Am-241 P2 0.000000 -179 1 2 1 Am-241 P3 0.000000 -180 1 2 1 Am-242m P0 0.000000 -181 1 2 1 Am-242m P1 0.000000 -182 1 2 1 Am-242m P2 0.000000 -183 1 2 1 Am-242m P3 0.000000 -184 1 2 1 Am-243 P0 0.000000 -185 1 2 1 Am-243 P1 0.000000 -186 1 2 1 Am-243 P2 0.000000 -187 1 2 1 Am-243 P3 0.000000 -188 1 2 1 Cm-242 P0 0.000000 -189 1 2 1 Cm-242 P1 0.000000 -190 1 2 1 Cm-242 P2 0.000000 -191 1 2 1 Cm-242 P3 0.000000 -192 1 2 1 Cm-243 P0 0.000000 -193 1 2 1 Cm-243 P1 0.000000 -194 1 2 1 Cm-243 P2 0.000000 -195 1 2 1 Cm-243 P3 0.000000 -196 1 2 1 Cm-244 P0 0.000000 -197 1 2 1 Cm-244 P1 0.000000 -198 1 2 1 Cm-244 P2 0.000000 -199 1 2 1 Cm-244 P3 0.000000 -200 1 2 1 Cm-245 P0 0.000000 -201 1 2 1 Cm-245 P1 0.000000 -202 1 2 1 Cm-245 P2 0.000000 -203 1 2 1 Cm-245 P3 0.000000 -204 1 2 1 Mo-95 P0 0.000000 -205 1 2 1 Mo-95 P1 0.000000 -206 1 2 1 Mo-95 P2 0.000000 -207 1 2 1 Mo-95 P3 0.000000 -208 1 2 1 Tc-99 P0 0.000000 -209 1 2 1 Tc-99 P1 0.000000 -210 1 2 1 Tc-99 P2 0.000000 -211 1 2 1 Tc-99 P3 0.000000 -212 1 2 1 Ru-101 P0 0.000000 -213 1 2 1 Ru-101 P1 0.000000 -214 1 2 1 Ru-101 P2 0.000000 -215 1 2 1 Ru-101 P3 0.000000 -216 1 2 1 Ru-103 P0 0.000000 -217 1 2 1 Ru-103 P1 0.000000 -218 1 2 1 Ru-103 P2 0.000000 -219 1 2 1 Ru-103 P3 0.000000 -220 1 2 1 Ag-109 P0 0.000000 -221 1 2 1 Ag-109 P1 0.000000 -222 1 2 1 Ag-109 P2 0.000000 -223 1 2 1 Ag-109 P3 0.000000 -224 1 2 1 Xe-135 P0 0.000000 -225 1 2 1 Xe-135 P1 0.000000 -226 1 2 1 Xe-135 P2 0.000000 -227 1 2 1 Xe-135 P3 0.000000 -228 1 2 1 Cs-133 P0 0.000000 -229 1 2 1 Cs-133 P1 0.000000 -230 1 2 1 Cs-133 P2 0.000000 -231 1 2 1 Cs-133 P3 0.000000 -232 1 2 1 Nd-143 P0 0.000000 -233 1 2 1 Nd-143 P1 0.000000 -234 1 2 1 Nd-143 P2 0.000000 -235 1 2 1 Nd-143 P3 0.000000 -236 1 2 1 Nd-145 P0 0.000000 -237 1 2 1 Nd-145 P1 0.000000 -238 1 2 1 Nd-145 P2 0.000000 -239 1 2 1 Nd-145 P3 0.000000 -240 1 2 1 Sm-147 P0 0.000000 -241 1 2 1 Sm-147 P1 0.000000 -242 1 2 1 Sm-147 P2 0.000000 -243 1 2 1 Sm-147 P3 0.000000 -244 1 2 1 Sm-149 P0 0.000000 -245 1 2 1 Sm-149 P1 0.000000 -246 1 2 1 Sm-149 P2 0.000000 -247 1 2 1 Sm-149 P3 0.000000 -248 1 2 1 Sm-150 P0 0.000000 -249 1 2 1 Sm-150 P1 0.000000 -250 1 2 1 Sm-150 P2 0.000000 -251 1 2 1 Sm-150 P3 0.000000 -252 1 2 1 Sm-151 P0 0.000000 -253 1 2 1 Sm-151 P1 0.000000 -254 1 2 1 Sm-151 P2 0.000000 -255 1 2 1 Sm-151 P3 0.000000 -256 1 2 1 Sm-152 P0 0.000000 -257 1 2 1 Sm-152 P1 0.000000 -258 1 2 1 Sm-152 P2 0.000000 -259 1 2 1 Sm-152 P3 0.000000 -260 1 2 1 Eu-153 P0 0.000000 -261 1 2 1 Eu-153 P1 0.000000 -262 1 2 1 Eu-153 P2 0.000000 -263 1 2 1 Eu-153 P3 0.000000 -264 1 2 1 Gd-155 P0 0.000000 -265 1 2 1 Gd-155 P1 0.000000 -266 1 2 1 Gd-155 P2 0.000000 -267 1 2 1 Gd-155 P3 0.000000 -268 1 2 1 O-16 P0 0.000000 -269 1 2 1 O-16 P1 0.000000 -270 1 2 1 O-16 P2 0.000000 -271 1 2 1 O-16 P3 0.000000 -0 1 2 2 U-234 P0 0.000000 -1 1 2 2 U-234 P1 0.000000 -2 1 2 2 U-234 P2 0.000000 -3 1 2 2 U-234 P3 0.000000 -4 1 2 2 U-235 P0 0.003960 -5 1 2 2 U-235 P1 0.000071 -6 1 2 2 U-235 P2 0.001232 -7 1 2 2 U-235 P3 0.000182 -8 1 2 2 U-236 P0 0.001980 -9 1 2 2 U-236 P1 0.000479 -10 1 2 2 U-236 P2 -0.000816 -11 1 2 2 U-236 P3 -0.000648 -12 1 2 2 U-238 P0 0.205918 -13 1 2 2 U-238 P1 -0.013364 -14 1 2 2 U-238 P2 -0.010941 -15 1 2 2 U-238 P3 0.000772 -16 1 2 2 Np-237 P0 0.000000 -17 1 2 2 Np-237 P1 0.000000 -18 1 2 2 Np-237 P2 0.000000 -19 1 2 2 Np-237 P3 0.000000 -20 1 2 2 Pu-238 P0 0.000000 -21 1 2 2 Pu-238 P1 0.000000 -22 1 2 2 Pu-238 P2 0.000000 -23 1 2 2 Pu-238 P3 0.000000 -24 1 2 2 Pu-239 P0 0.000000 -25 1 2 2 Pu-239 P1 0.000000 -26 1 2 2 Pu-239 P2 0.000000 -27 1 2 2 Pu-239 P3 0.000000 -28 1 2 2 Pu-240 P0 0.000000 -29 1 2 2 Pu-240 P1 0.000000 -30 1 2 2 Pu-240 P2 0.000000 -31 1 2 2 Pu-240 P3 0.000000 -32 1 2 2 Pu-241 P0 0.000000 -33 1 2 2 Pu-241 P1 0.000000 -34 1 2 2 Pu-241 P2 0.000000 -35 1 2 2 Pu-241 P3 0.000000 -36 1 2 2 Pu-242 P0 0.000000 -37 1 2 2 Pu-242 P1 0.000000 -38 1 2 2 Pu-242 P2 0.000000 -39 1 2 2 Pu-242 P3 0.000000 -40 1 2 2 Am-241 P0 0.000000 -41 1 2 2 Am-241 P1 0.000000 -42 1 2 2 Am-241 P2 0.000000 -43 1 2 2 Am-241 P3 0.000000 -44 1 2 2 Am-242m P0 0.000000 -45 1 2 2 Am-242m P1 0.000000 -46 1 2 2 Am-242m P2 0.000000 -47 1 2 2 Am-242m P3 0.000000 -48 1 2 2 Am-243 P0 0.000000 -49 1 2 2 Am-243 P1 0.000000 -50 1 2 2 Am-243 P2 0.000000 -51 1 2 2 Am-243 P3 0.000000 -52 1 2 2 Cm-242 P0 0.000000 -53 1 2 2 Cm-242 P1 0.000000 -54 1 2 2 Cm-242 P2 0.000000 -55 1 2 2 Cm-242 P3 0.000000 -56 1 2 2 Cm-243 P0 0.000000 -57 1 2 2 Cm-243 P1 0.000000 -58 1 2 2 Cm-243 P2 0.000000 -59 1 2 2 Cm-243 P3 0.000000 -60 1 2 2 Cm-244 P0 0.000000 -61 1 2 2 Cm-244 P1 0.000000 -62 1 2 2 Cm-244 P2 0.000000 -63 1 2 2 Cm-244 P3 0.000000 -64 1 2 2 Cm-245 P0 0.000000 -65 1 2 2 Cm-245 P1 0.000000 -66 1 2 2 Cm-245 P2 0.000000 -67 1 2 2 Cm-245 P3 0.000000 -68 1 2 2 Mo-95 P0 0.000000 -69 1 2 2 Mo-95 P1 0.000000 -70 1 2 2 Mo-95 P2 0.000000 -71 1 2 2 Mo-95 P3 0.000000 -72 1 2 2 Tc-99 P0 0.000000 -73 1 2 2 Tc-99 P1 0.000000 -74 1 2 2 Tc-99 P2 0.000000 -75 1 2 2 Tc-99 P3 0.000000 -76 1 2 2 Ru-101 P0 0.000000 -77 1 2 2 Ru-101 P1 0.000000 -78 1 2 2 Ru-101 P2 0.000000 -79 1 2 2 Ru-101 P3 0.000000 -80 1 2 2 Ru-103 P0 0.000000 -81 1 2 2 Ru-103 P1 0.000000 -82 1 2 2 Ru-103 P2 0.000000 -83 1 2 2 Ru-103 P3 0.000000 -84 1 2 2 Ag-109 P0 0.000000 -85 1 2 2 Ag-109 P1 0.000000 -86 1 2 2 Ag-109 P2 0.000000 -87 1 2 2 Ag-109 P3 0.000000 -88 1 2 2 Xe-135 P0 0.000000 -89 1 2 2 Xe-135 P1 0.000000 -90 1 2 2 Xe-135 P2 0.000000 -91 1 2 2 Xe-135 P3 0.000000 -92 1 2 2 Cs-133 P0 0.000000 -93 1 2 2 Cs-133 P1 0.000000 -94 1 2 2 Cs-133 P2 0.000000 -95 1 2 2 Cs-133 P3 0.000000 -96 1 2 2 Nd-143 P0 0.000000 -97 1 2 2 Nd-143 P1 0.000000 -98 1 2 2 Nd-143 P2 0.000000 -99 1 2 2 Nd-143 P3 0.000000 -100 1 2 2 Nd-145 P0 0.000000 -101 1 2 2 Nd-145 P1 0.000000 -102 1 2 2 Nd-145 P2 0.000000 -103 1 2 2 Nd-145 P3 0.000000 -104 1 2 2 Sm-147 P0 0.000000 -105 1 2 2 Sm-147 P1 0.000000 -106 1 2 2 Sm-147 P2 0.000000 -107 1 2 2 Sm-147 P3 0.000000 -108 1 2 2 Sm-149 P0 0.000000 -109 1 2 2 Sm-149 P1 0.000000 -110 1 2 2 Sm-149 P2 0.000000 -111 1 2 2 Sm-149 P3 0.000000 -112 1 2 2 Sm-150 P0 0.000000 -113 1 2 2 Sm-150 P1 0.000000 -114 1 2 2 Sm-150 P2 0.000000 -115 1 2 2 Sm-150 P3 0.000000 -116 1 2 2 Sm-151 P0 0.000000 -117 1 2 2 Sm-151 P1 0.000000 -118 1 2 2 Sm-151 P2 0.000000 -119 1 2 2 Sm-151 P3 0.000000 -120 1 2 2 Sm-152 P0 0.000000 -121 1 2 2 Sm-152 P1 0.000000 -122 1 2 2 Sm-152 P2 0.000000 -123 1 2 2 Sm-152 P3 0.000000 -124 1 2 2 Eu-153 P0 0.000000 -125 1 2 2 Eu-153 P1 0.000000 -126 1 2 2 Eu-153 P2 0.000000 -127 1 2 2 Eu-153 P3 0.000000 -128 1 2 2 Gd-155 P0 0.000000 -129 1 2 2 Gd-155 P1 0.000000 -130 1 2 2 Gd-155 P2 0.000000 -131 1 2 2 Gd-155 P3 0.000000 -132 1 2 2 O-16 P0 0.192058 -133 1 2 2 O-16 P1 0.001504 -134 1 2 2 O-16 P2 -0.004281 -135 1 2 2 O-16 P3 -0.007160 material group out nuclide mean std. dev. -34 1 1 U-234 0 0.000000 -35 1 1 U-235 1 0.066362 -36 1 1 U-236 0 0.000000 -37 1 1 U-238 1 0.093082 -38 1 1 Np-237 0 0.000000 -39 1 1 Pu-238 0 0.000000 -40 1 1 Pu-239 1 0.104567 -41 1 1 Pu-240 0 0.000000 -42 1 1 Pu-241 1 0.263696 -43 1 1 Pu-242 0 0.000000 -44 1 1 Am-241 0 0.000000 -45 1 1 Am-242m 0 0.000000 -46 1 1 Am-243 0 0.000000 -47 1 1 Cm-242 0 0.000000 -48 1 1 Cm-243 0 0.000000 -49 1 1 Cm-244 0 0.000000 -50 1 1 Cm-245 0 0.000000 -51 1 1 Mo-95 0 0.000000 -52 1 1 Tc-99 0 0.000000 -53 1 1 Ru-101 0 0.000000 -54 1 1 Ru-103 0 0.000000 -55 1 1 Ag-109 0 0.000000 -56 1 1 Xe-135 0 0.000000 -57 1 1 Cs-133 0 0.000000 -58 1 1 Nd-143 0 0.000000 -59 1 1 Nd-145 0 0.000000 -60 1 1 Sm-147 0 0.000000 -61 1 1 Sm-149 0 0.000000 -62 1 1 Sm-150 0 0.000000 -63 1 1 Sm-151 0 0.000000 -64 1 1 Sm-152 0 0.000000 -65 1 1 Eu-153 0 0.000000 -66 1 1 Gd-155 0 0.000000 -67 1 1 O-16 0 0.000000 -0 1 2 U-234 0 0.000000 -1 1 2 U-235 0 0.000000 -2 1 2 U-236 0 0.000000 -3 1 2 U-238 0 0.000000 -4 1 2 Np-237 0 0.000000 -5 1 2 Pu-238 0 0.000000 -6 1 2 Pu-239 0 0.000000 -7 1 2 Pu-240 0 0.000000 -8 1 2 Pu-241 0 0.000000 -9 1 2 Pu-242 0 0.000000 -10 1 2 Am-241 0 0.000000 -11 1 2 Am-242m 0 0.000000 -12 1 2 Am-243 0 0.000000 -13 1 2 Cm-242 0 0.000000 -14 1 2 Cm-243 0 0.000000 -15 1 2 Cm-244 0 0.000000 -16 1 2 Cm-245 0 0.000000 -17 1 2 Mo-95 0 0.000000 -18 1 2 Tc-99 0 0.000000 -19 1 2 Ru-101 0 0.000000 -20 1 2 Ru-103 0 0.000000 -21 1 2 Ag-109 0 0.000000 -22 1 2 Xe-135 0 0.000000 -23 1 2 Cs-133 0 0.000000 -24 1 2 Nd-143 0 0.000000 -25 1 2 Nd-145 0 0.000000 -26 1 2 Sm-147 0 0.000000 -27 1 2 Sm-149 0 0.000000 -28 1 2 Sm-150 0 0.000000 -29 1 2 Sm-151 0 0.000000 -30 1 2 Sm-152 0 0.000000 -31 1 2 Eu-153 0 0.000000 -32 1 2 Gd-155 0 0.000000 -33 1 2 O-16 0 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0.104734 0.008915 -6 2 1 Zr-91 0.036155 0.003735 -7 2 1 Zr-92 0.042422 0.003029 -8 2 1 Zr-94 0.046148 0.006251 -9 2 1 Zr-96 0.007794 0.001536 -0 2 2 Zr-90 0.121688 0.034934 -1 2 2 Zr-91 0.061792 0.024317 -2 2 2 Zr-92 0.041633 0.016323 -3 2 2 Zr-94 0.060818 0.021483 -4 2 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -5 2 1 Zr-90 0 0 -6 2 1 Zr-91 0 0 -7 2 1 Zr-92 0 0 -8 2 1 Zr-94 0 0 -9 2 1 Zr-96 0 0 -0 2 2 Zr-90 0 0 -1 2 2 Zr-91 0 0 -2 2 2 Zr-92 0 0 -3 2 2 Zr-94 0 0 -4 2 2 Zr-96 0 0 material group in group out nuclide moment mean -60 2 1 1 Zr-90 P0 0.122030 -61 2 1 1 Zr-90 P1 0.017296 -62 2 1 1 Zr-90 P2 0.020437 -63 2 1 1 Zr-90 P3 -0.000350 -64 2 1 1 Zr-91 P0 0.037548 -65 2 1 1 Zr-91 P1 0.001393 -66 2 1 1 Zr-91 P2 -0.000553 -67 2 1 1 Zr-91 P3 0.001719 -68 2 1 1 Zr-92 P0 0.047829 -69 2 1 1 Zr-92 P1 0.005406 -70 2 1 1 Zr-92 P2 0.004793 -71 2 1 1 Zr-92 P3 0.001907 -72 2 1 1 Zr-94 P0 0.058110 -73 2 1 1 Zr-94 P1 0.011962 -74 2 1 1 Zr-94 P2 0.006220 -75 2 1 1 Zr-94 P3 -0.000627 -76 2 1 1 Zr-96 P0 0.007599 -77 2 1 1 Zr-96 P1 -0.000196 -78 2 1 1 Zr-96 P2 -0.001193 -79 2 1 1 Zr-96 P3 -0.000401 -40 2 1 2 Zr-90 P0 0.000000 -41 2 1 2 Zr-90 P1 0.000000 -42 2 1 2 Zr-90 P2 0.000000 -43 2 1 2 Zr-90 P3 0.000000 -44 2 1 2 Zr-91 P0 0.000000 -45 2 1 2 Zr-91 P1 0.000000 -46 2 1 2 Zr-91 P2 0.000000 -47 2 1 2 Zr-91 P3 0.000000 -48 2 1 2 Zr-92 P0 0.000000 -49 2 1 2 Zr-92 P1 0.000000 -50 2 1 2 Zr-92 P2 0.000000 -51 2 1 2 Zr-92 P3 0.000000 -52 2 1 2 Zr-94 P0 0.000000 -53 2 1 2 Zr-94 P1 0.000000 -54 2 1 2 Zr-94 P2 0.000000 -55 2 1 2 Zr-94 P3 0.000000 -56 2 1 2 Zr-96 P0 0.000000 -57 2 1 2 Zr-96 P1 0.000000 -58 2 1 2 Zr-96 P2 0.000000 -59 2 1 2 Zr-96 P3 0.000000 -20 2 2 1 Zr-90 P0 0.000000 -21 2 2 1 Zr-90 P1 0.000000 -22 2 2 1 Zr-90 P2 0.000000 -23 2 2 1 Zr-90 P3 0.000000 -24 2 2 1 Zr-91 P0 0.000000 -25 2 2 1 Zr-91 P1 0.000000 -26 2 2 1 Zr-91 P2 0.000000 -27 2 2 1 Zr-91 P3 0.000000 -28 2 2 1 Zr-92 P0 0.000000 -29 2 2 1 Zr-92 P1 0.000000 -30 2 2 1 Zr-92 P2 0.000000 -31 2 2 1 Zr-92 P3 0.000000 -32 2 2 1 Zr-94 P0 0.000000 -33 2 2 1 Zr-94 P1 0.000000 -34 2 2 1 Zr-94 P2 0.000000 -35 2 2 1 Zr-94 P3 0.000000 -36 2 2 1 Zr-96 P0 0.000000 -37 2 2 1 Zr-96 P1 0.000000 -38 2 2 1 Zr-96 P2 0.000000 -39 2 2 1 Zr-96 P3 0.000000 -0 2 2 2 Zr-90 P0 0.119570 -1 2 2 2 Zr-90 P1 -0.002117 -2 2 2 2 Zr-90 P2 -0.015144 -3 2 2 2 Zr-90 P3 0.000965 -4 2 2 2 Zr-91 P0 0.054803 -5 2 2 2 Zr-91 P1 -0.006989 -6 2 2 2 Zr-91 P2 -0.010542 -7 2 2 2 Zr-91 P3 -0.001260 -8 2 2 2 Zr-92 P0 0.034875 -9 2 2 2 Zr-92 P1 -0.006759 -10 2 2 2 Zr-92 P2 0.008972 -11 2 2 2 Zr-92 P3 0.009834 -12 2 2 2 Zr-94 P0 0.054803 -13 2 2 2 Zr-94 P1 -0.006015 -14 2 2 2 Zr-94 P2 0.001420 -15 2 2 2 Zr-94 P3 0.004494 -16 2 2 2 Zr-96 P0 0.000000 -17 2 2 2 Zr-96 P1 0.000000 -18 2 2 2 Zr-96 P2 0.000000 -19 2 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. -5 2 1 Zr-90 0 0 -6 2 1 Zr-91 0 0 -7 2 1 Zr-92 0 0 -8 2 1 Zr-94 0 0 -9 2 1 Zr-96 0 0 -0 2 2 Zr-90 0 0 -1 2 2 Zr-91 0 0 -2 2 2 Zr-92 0 0 -3 2 2 Zr-94 0 0 -4 2 2 Zr-96 0 0 material group in nuclide mean std. dev. -4 3 1 H-1 0.207103 0.023028 -5 3 1 O-16 0.079282 0.005197 -6 3 1 B-10 0.000521 0.000244 -7 3 1 B-11 0.000000 0.000000 -0 3 2 H-1 1.283344 0.250946 -1 3 2 O-16 0.085363 0.014001 -2 3 2 B-10 0.049249 0.008232 -3 3 2 B-11 0.000195 0.001527 material group in nuclide mean std. dev. -4 3 1 H-1 0 0 -5 3 1 O-16 0 0 -6 3 1 B-10 0 0 -7 3 1 B-11 0 0 -0 3 2 H-1 0 0 -1 3 2 O-16 0 0 -2 3 2 B-10 0 0 -3 3 2 B-11 0 0 material group in group out nuclide moment mean -48 3 1 1 H-1 P0 0.560615 -49 3 1 1 H-1 P1 0.379309 -50 3 1 1 H-1 P2 0.149073 -51 3 1 1 H-1 P3 0.005293 -52 3 1 1 O-16 P0 0.082731 -53 3 1 1 O-16 P1 0.004100 -54 3 1 1 O-16 P2 0.003113 -55 3 1 1 O-16 P3 -0.002256 -56 3 1 1 B-10 P0 0.000000 -57 3 1 1 B-10 P1 0.000000 -58 3 1 1 B-10 P2 0.000000 -59 3 1 1 B-10 P3 0.000000 -60 3 1 1 B-11 P0 0.000000 -61 3 1 1 B-11 P1 0.000000 -62 3 1 1 B-11 P2 0.000000 -63 3 1 1 B-11 P3 0.000000 -32 3 1 2 H-1 P0 0.025666 -33 3 1 2 H-1 P1 0.007631 -34 3 1 2 H-1 P2 -0.002692 -35 3 1 2 H-1 P3 -0.002928 -36 3 1 2 O-16 P0 0.000521 -37 3 1 2 O-16 P1 -0.000268 -38 3 1 2 O-16 P2 -0.000046 -39 3 1 2 O-16 P3 0.000208 -40 3 1 2 B-10 P0 0.000000 -41 3 1 2 B-10 P1 0.000000 -42 3 1 2 B-10 P2 0.000000 -43 3 1 2 B-10 P3 0.000000 -44 3 1 2 B-11 P0 0.000000 -45 3 1 2 B-11 P1 0.000000 -46 3 1 2 B-11 P2 0.000000 -47 3 1 2 B-11 P3 0.000000 -16 3 2 1 H-1 P0 0.000000 -17 3 2 1 H-1 P1 0.000000 -18 3 2 1 H-1 P2 0.000000 -19 3 2 1 H-1 P3 0.000000 -20 3 2 1 O-16 P0 0.000000 -21 3 2 1 O-16 P1 0.000000 -22 3 2 1 O-16 P2 0.000000 -23 3 2 1 O-16 P3 0.000000 -24 3 2 1 B-10 P0 0.000000 -25 3 2 1 B-10 P1 0.000000 -26 3 2 1 B-10 P2 0.000000 -27 3 2 1 B-10 P3 0.000000 -28 3 2 1 B-11 P0 0.000000 -29 3 2 1 B-11 P1 0.000000 -30 3 2 1 B-11 P2 0.000000 -31 3 2 1 B-11 P3 0.000000 -0 3 2 2 H-1 P0 1.840960 -1 3 2 2 H-1 P1 0.498320 -2 3 2 2 H-1 P2 0.083870 -3 3 2 2 H-1 P3 0.013597 -4 3 2 2 O-16 P0 0.082081 -5 3 2 2 O-16 P1 -0.000867 -6 3 2 2 O-16 P2 0.006697 -7 3 2 2 O-16 P3 0.003223 -8 3 2 2 B-10 P0 0.000000 -9 3 2 2 B-10 P1 0.000000 -10 3 2 2 B-10 P2 0.000000 -11 3 2 2 B-10 P3 0.000000 -12 3 2 2 B-11 P0 0.001173 -13 3 2 2 B-11 P1 0.000978 -14 3 2 2 B-11 P2 0.000637 -15 3 2 2 B-11 P3 0.000234 material group out nuclide mean std. dev. -4 3 1 H-1 0 0 -5 3 1 O-16 0 0 -6 3 1 B-10 0 0 -7 3 1 B-11 0 0 -0 3 2 H-1 0 0 -1 3 2 O-16 0 0 -2 3 2 B-10 0 0 -3 3 2 B-11 0 0 material group in nuclide mean std. dev. -4 4 1 H-1 0.175242 0.053715 -5 4 1 O-16 0.066545 0.010083 -6 4 1 B-10 0.000570 0.000352 -7 4 1 B-11 0.000089 0.000346 -0 4 2 H-1 1.142895 0.365140 -1 4 2 O-16 0.085141 0.028073 -2 4 2 B-10 0.025923 0.007276 -3 4 2 B-11 0.000000 0.000000 material group in nuclide mean std. dev. -4 4 1 H-1 0 0 -5 4 1 O-16 0 0 -6 4 1 B-10 0 0 -7 4 1 B-11 0 0 -0 4 2 H-1 0 0 -1 4 2 O-16 0 0 -2 4 2 B-10 0 0 -3 4 2 B-11 0 0 material group in group out nuclide moment mean -48 4 1 1 H-1 P0 0.468964 -49 4 1 1 H-1 P1 0.317668 -50 4 1 1 H-1 P2 0.127157 -51 4 1 1 H-1 P3 0.009844 -52 4 1 1 O-16 P0 0.074692 -53 4 1 1 O-16 P1 0.008147 -54 4 1 1 O-16 P2 0.003915 -55 4 1 1 O-16 P3 0.002322 -56 4 1 1 B-10 P0 0.000000 -57 4 1 1 B-10 P1 0.000000 -58 4 1 1 B-10 P2 0.000000 -59 4 1 1 B-10 P3 0.000000 -60 4 1 1 B-11 P0 0.000285 -61 4 1 1 B-11 P1 0.000196 -62 4 1 1 B-11 P2 0.000060 -63 4 1 1 B-11 P3 -0.000062 -32 4 1 2 H-1 P0 0.023662 -33 4 1 2 H-1 P1 0.007526 -34 4 1 2 H-1 P2 -0.002730 -35 4 1 2 H-1 P3 -0.003140 -36 4 1 2 O-16 P0 0.000000 -37 4 1 2 O-16 P1 0.000000 -38 4 1 2 O-16 P2 0.000000 -39 4 1 2 O-16 P3 0.000000 -40 4 1 2 B-10 P0 0.000000 -41 4 1 2 B-10 P1 0.000000 -42 4 1 2 B-10 P2 0.000000 -43 4 1 2 B-10 P3 0.000000 -44 4 1 2 B-11 P0 0.000000 -45 4 1 2 B-11 P1 0.000000 -46 4 1 2 B-11 P2 0.000000 -47 4 1 2 B-11 P3 0.000000 -16 4 2 1 H-1 P0 0.000000 -17 4 2 1 H-1 P1 0.000000 -18 4 2 1 H-1 P2 0.000000 -19 4 2 1 H-1 P3 0.000000 -20 4 2 1 O-16 P0 0.000000 -21 4 2 1 O-16 P1 0.000000 -22 4 2 1 O-16 P2 0.000000 -23 4 2 1 O-16 P3 0.000000 -24 4 2 1 B-10 P0 0.000000 -25 4 2 1 B-10 P1 0.000000 -26 4 2 1 B-10 P2 0.000000 -27 4 2 1 B-10 P3 0.000000 -28 4 2 1 B-11 P0 0.000000 -29 4 2 1 B-11 P1 0.000000 -30 4 2 1 B-11 P2 0.000000 -31 4 2 1 B-11 P3 0.000000 -0 4 2 2 H-1 P0 1.672065 -1 4 2 2 H-1 P1 0.493252 -2 4 2 2 H-1 P2 0.104511 -3 4 2 2 H-1 P3 0.039078 -4 4 2 2 O-16 P0 0.092584 -5 4 2 2 O-16 P1 0.007443 -6 4 2 2 O-16 P2 -0.005485 -7 4 2 2 O-16 P3 -0.006103 -8 4 2 2 B-10 P0 0.000000 -9 4 2 2 B-10 P1 0.000000 -10 4 2 2 B-10 P2 0.000000 -11 4 2 2 B-10 P3 0.000000 -12 4 2 2 B-11 P0 0.000000 -13 4 2 2 B-11 P1 0.000000 -14 4 2 2 B-11 P2 0.000000 -15 4 2 2 B-11 P3 0.000000 material group out nuclide mean std. dev. -4 4 1 H-1 0 0 -5 4 1 O-16 0 0 -6 4 1 B-10 0 0 -7 4 1 B-11 0 0 -0 4 2 H-1 0 0 -1 4 2 O-16 0 0 -2 4 2 B-10 0 0 -3 4 2 B-11 0 0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in group out nuclide moment mean -324 5 1 1 Fe-54 P0 0 -325 5 1 1 Fe-54 P1 0 -326 5 1 1 Fe-54 P2 0 -327 5 1 1 Fe-54 P3 0 -328 5 1 1 Fe-56 P0 0 -329 5 1 1 Fe-56 P1 0 -330 5 1 1 Fe-56 P2 0 -331 5 1 1 Fe-56 P3 0 -332 5 1 1 Fe-57 P0 0 -333 5 1 1 Fe-57 P1 0 -334 5 1 1 Fe-57 P2 0 -335 5 1 1 Fe-57 P3 0 -336 5 1 1 Fe-58 P0 0 -337 5 1 1 Fe-58 P1 0 -338 5 1 1 Fe-58 P2 0 -339 5 1 1 Fe-58 P3 0 -340 5 1 1 Ni-58 P0 0 -341 5 1 1 Ni-58 P1 0 -342 5 1 1 Ni-58 P2 0 -343 5 1 1 Ni-58 P3 0 -344 5 1 1 Ni-60 P0 0 -345 5 1 1 Ni-60 P1 0 -346 5 1 1 Ni-60 P2 0 -347 5 1 1 Ni-60 P3 0 -348 5 1 1 Ni-61 P0 0 -349 5 1 1 Ni-61 P1 0 -350 5 1 1 Ni-61 P2 0 -351 5 1 1 Ni-61 P3 0 -352 5 1 1 Ni-62 P0 0 -353 5 1 1 Ni-62 P1 0 -354 5 1 1 Ni-62 P2 0 -355 5 1 1 Ni-62 P3 0 -356 5 1 1 Ni-64 P0 0 -357 5 1 1 Ni-64 P1 0 -358 5 1 1 Ni-64 P2 0 -359 5 1 1 Ni-64 P3 0 -360 5 1 1 Mn-55 P0 0 -361 5 1 1 Mn-55 P1 0 -362 5 1 1 Mn-55 P2 0 -363 5 1 1 Mn-55 P3 0 -364 5 1 1 Mo-92 P0 0 -365 5 1 1 Mo-92 P1 0 -366 5 1 1 Mo-92 P2 0 -367 5 1 1 Mo-92 P3 0 -368 5 1 1 Mo-94 P0 0 -369 5 1 1 Mo-94 P1 0 -370 5 1 1 Mo-94 P2 0 -371 5 1 1 Mo-94 P3 0 -372 5 1 1 Mo-95 P0 0 -373 5 1 1 Mo-95 P1 0 -374 5 1 1 Mo-95 P2 0 -375 5 1 1 Mo-95 P3 0 -376 5 1 1 Mo-96 P0 0 -377 5 1 1 Mo-96 P1 0 -378 5 1 1 Mo-96 P2 0 -379 5 1 1 Mo-96 P3 0 -380 5 1 1 Mo-97 P0 0 -381 5 1 1 Mo-97 P1 0 -382 5 1 1 Mo-97 P2 0 -383 5 1 1 Mo-97 P3 0 -384 5 1 1 Mo-98 P0 0 -385 5 1 1 Mo-98 P1 0 -386 5 1 1 Mo-98 P2 0 -387 5 1 1 Mo-98 P3 0 -388 5 1 1 Mo-100 P0 0 -389 5 1 1 Mo-100 P1 0 -390 5 1 1 Mo-100 P2 0 -391 5 1 1 Mo-100 P3 0 -392 5 1 1 Si-28 P0 0 -393 5 1 1 Si-28 P1 0 -394 5 1 1 Si-28 P2 0 -395 5 1 1 Si-28 P3 0 -396 5 1 1 Si-29 P0 0 -397 5 1 1 Si-29 P1 0 -398 5 1 1 Si-29 P2 0 -399 5 1 1 Si-29 P3 0 -400 5 1 1 Si-30 P0 0 -401 5 1 1 Si-30 P1 0 -402 5 1 1 Si-30 P2 0 -403 5 1 1 Si-30 P3 0 -404 5 1 1 Cr-50 P0 0 -405 5 1 1 Cr-50 P1 0 -406 5 1 1 Cr-50 P2 0 -407 5 1 1 Cr-50 P3 0 -408 5 1 1 Cr-52 P0 0 -409 5 1 1 Cr-52 P1 0 -410 5 1 1 Cr-52 P2 0 -411 5 1 1 Cr-52 P3 0 -412 5 1 1 Cr-53 P0 0 -413 5 1 1 Cr-53 P1 0 -414 5 1 1 Cr-53 P2 0 -415 5 1 1 Cr-53 P3 0 -416 5 1 1 Cr-54 P0 0 -417 5 1 1 Cr-54 P1 0 -418 5 1 1 Cr-54 P2 0 -419 5 1 1 Cr-54 P3 0 -420 5 1 1 C-Nat P0 0 -421 5 1 1 C-Nat P1 0 -422 5 1 1 C-Nat P2 0 -423 5 1 1 C-Nat P3 0 -424 5 1 1 Cu-63 P0 0 -425 5 1 1 Cu-63 P1 0 -426 5 1 1 Cu-63 P2 0 -427 5 1 1 Cu-63 P3 0 -428 5 1 1 Cu-65 P0 0 -429 5 1 1 Cu-65 P1 0 -430 5 1 1 Cu-65 P2 0 -431 5 1 1 Cu-65 P3 0 -216 5 1 2 Fe-54 P0 0 -217 5 1 2 Fe-54 P1 0 -218 5 1 2 Fe-54 P2 0 -219 5 1 2 Fe-54 P3 0 -220 5 1 2 Fe-56 P0 0 -221 5 1 2 Fe-56 P1 0 -222 5 1 2 Fe-56 P2 0 -223 5 1 2 Fe-56 P3 0 -224 5 1 2 Fe-57 P0 0 -225 5 1 2 Fe-57 P1 0 -226 5 1 2 Fe-57 P2 0 -227 5 1 2 Fe-57 P3 0 -228 5 1 2 Fe-58 P0 0 -229 5 1 2 Fe-58 P1 0 -230 5 1 2 Fe-58 P2 0 -231 5 1 2 Fe-58 P3 0 -232 5 1 2 Ni-58 P0 0 -233 5 1 2 Ni-58 P1 0 -234 5 1 2 Ni-58 P2 0 -235 5 1 2 Ni-58 P3 0 -236 5 1 2 Ni-60 P0 0 -237 5 1 2 Ni-60 P1 0 -238 5 1 2 Ni-60 P2 0 -239 5 1 2 Ni-60 P3 0 -240 5 1 2 Ni-61 P0 0 -241 5 1 2 Ni-61 P1 0 -242 5 1 2 Ni-61 P2 0 -243 5 1 2 Ni-61 P3 0 -244 5 1 2 Ni-62 P0 0 -245 5 1 2 Ni-62 P1 0 -246 5 1 2 Ni-62 P2 0 -247 5 1 2 Ni-62 P3 0 -248 5 1 2 Ni-64 P0 0 -249 5 1 2 Ni-64 P1 0 -250 5 1 2 Ni-64 P2 0 -251 5 1 2 Ni-64 P3 0 -252 5 1 2 Mn-55 P0 0 -253 5 1 2 Mn-55 P1 0 -254 5 1 2 Mn-55 P2 0 -255 5 1 2 Mn-55 P3 0 -256 5 1 2 Mo-92 P0 0 -257 5 1 2 Mo-92 P1 0 -258 5 1 2 Mo-92 P2 0 -259 5 1 2 Mo-92 P3 0 -260 5 1 2 Mo-94 P0 0 -261 5 1 2 Mo-94 P1 0 -262 5 1 2 Mo-94 P2 0 -263 5 1 2 Mo-94 P3 0 -264 5 1 2 Mo-95 P0 0 -265 5 1 2 Mo-95 P1 0 -266 5 1 2 Mo-95 P2 0 -267 5 1 2 Mo-95 P3 0 -268 5 1 2 Mo-96 P0 0 -269 5 1 2 Mo-96 P1 0 -270 5 1 2 Mo-96 P2 0 -271 5 1 2 Mo-96 P3 0 -272 5 1 2 Mo-97 P0 0 -273 5 1 2 Mo-97 P1 0 -274 5 1 2 Mo-97 P2 0 -275 5 1 2 Mo-97 P3 0 -276 5 1 2 Mo-98 P0 0 -277 5 1 2 Mo-98 P1 0 -278 5 1 2 Mo-98 P2 0 -279 5 1 2 Mo-98 P3 0 -280 5 1 2 Mo-100 P0 0 -281 5 1 2 Mo-100 P1 0 -282 5 1 2 Mo-100 P2 0 -283 5 1 2 Mo-100 P3 0 -284 5 1 2 Si-28 P0 0 -285 5 1 2 Si-28 P1 0 -286 5 1 2 Si-28 P2 0 -287 5 1 2 Si-28 P3 0 -288 5 1 2 Si-29 P0 0 -289 5 1 2 Si-29 P1 0 -290 5 1 2 Si-29 P2 0 -291 5 1 2 Si-29 P3 0 -292 5 1 2 Si-30 P0 0 -293 5 1 2 Si-30 P1 0 -294 5 1 2 Si-30 P2 0 -295 5 1 2 Si-30 P3 0 -296 5 1 2 Cr-50 P0 0 -297 5 1 2 Cr-50 P1 0 -298 5 1 2 Cr-50 P2 0 -299 5 1 2 Cr-50 P3 0 -300 5 1 2 Cr-52 P0 0 -301 5 1 2 Cr-52 P1 0 -302 5 1 2 Cr-52 P2 0 -303 5 1 2 Cr-52 P3 0 -304 5 1 2 Cr-53 P0 0 -305 5 1 2 Cr-53 P1 0 -306 5 1 2 Cr-53 P2 0 -307 5 1 2 Cr-53 P3 0 -308 5 1 2 Cr-54 P0 0 -309 5 1 2 Cr-54 P1 0 -310 5 1 2 Cr-54 P2 0 -311 5 1 2 Cr-54 P3 0 -312 5 1 2 C-Nat P0 0 -313 5 1 2 C-Nat P1 0 -314 5 1 2 C-Nat P2 0 -315 5 1 2 C-Nat P3 0 -316 5 1 2 Cu-63 P0 0 -317 5 1 2 Cu-63 P1 0 -318 5 1 2 Cu-63 P2 0 -319 5 1 2 Cu-63 P3 0 -320 5 1 2 Cu-65 P0 0 -321 5 1 2 Cu-65 P1 0 -322 5 1 2 Cu-65 P2 0 -323 5 1 2 Cu-65 P3 0 -108 5 2 1 Fe-54 P0 0 -109 5 2 1 Fe-54 P1 0 -110 5 2 1 Fe-54 P2 0 -111 5 2 1 Fe-54 P3 0 -112 5 2 1 Fe-56 P0 0 -113 5 2 1 Fe-56 P1 0 -114 5 2 1 Fe-56 P2 0 -115 5 2 1 Fe-56 P3 0 -116 5 2 1 Fe-57 P0 0 -117 5 2 1 Fe-57 P1 0 -118 5 2 1 Fe-57 P2 0 -119 5 2 1 Fe-57 P3 0 -120 5 2 1 Fe-58 P0 0 -121 5 2 1 Fe-58 P1 0 -122 5 2 1 Fe-58 P2 0 -123 5 2 1 Fe-58 P3 0 -124 5 2 1 Ni-58 P0 0 -125 5 2 1 Ni-58 P1 0 -126 5 2 1 Ni-58 P2 0 -127 5 2 1 Ni-58 P3 0 -128 5 2 1 Ni-60 P0 0 -129 5 2 1 Ni-60 P1 0 -130 5 2 1 Ni-60 P2 0 -131 5 2 1 Ni-60 P3 0 -132 5 2 1 Ni-61 P0 0 -133 5 2 1 Ni-61 P1 0 -134 5 2 1 Ni-61 P2 0 -135 5 2 1 Ni-61 P3 0 -136 5 2 1 Ni-62 P0 0 -137 5 2 1 Ni-62 P1 0 -138 5 2 1 Ni-62 P2 0 -139 5 2 1 Ni-62 P3 0 -140 5 2 1 Ni-64 P0 0 -141 5 2 1 Ni-64 P1 0 -142 5 2 1 Ni-64 P2 0 -143 5 2 1 Ni-64 P3 0 -144 5 2 1 Mn-55 P0 0 -145 5 2 1 Mn-55 P1 0 -146 5 2 1 Mn-55 P2 0 -147 5 2 1 Mn-55 P3 0 -148 5 2 1 Mo-92 P0 0 -149 5 2 1 Mo-92 P1 0 -150 5 2 1 Mo-92 P2 0 -151 5 2 1 Mo-92 P3 0 -152 5 2 1 Mo-94 P0 0 -153 5 2 1 Mo-94 P1 0 -154 5 2 1 Mo-94 P2 0 -155 5 2 1 Mo-94 P3 0 -156 5 2 1 Mo-95 P0 0 -157 5 2 1 Mo-95 P1 0 -158 5 2 1 Mo-95 P2 0 -159 5 2 1 Mo-95 P3 0 -160 5 2 1 Mo-96 P0 0 -161 5 2 1 Mo-96 P1 0 -162 5 2 1 Mo-96 P2 0 -163 5 2 1 Mo-96 P3 0 -164 5 2 1 Mo-97 P0 0 -165 5 2 1 Mo-97 P1 0 -166 5 2 1 Mo-97 P2 0 -167 5 2 1 Mo-97 P3 0 -168 5 2 1 Mo-98 P0 0 -169 5 2 1 Mo-98 P1 0 -170 5 2 1 Mo-98 P2 0 -171 5 2 1 Mo-98 P3 0 -172 5 2 1 Mo-100 P0 0 -173 5 2 1 Mo-100 P1 0 -174 5 2 1 Mo-100 P2 0 -175 5 2 1 Mo-100 P3 0 -176 5 2 1 Si-28 P0 0 -177 5 2 1 Si-28 P1 0 -178 5 2 1 Si-28 P2 0 -179 5 2 1 Si-28 P3 0 -180 5 2 1 Si-29 P0 0 -181 5 2 1 Si-29 P1 0 -182 5 2 1 Si-29 P2 0 -183 5 2 1 Si-29 P3 0 -184 5 2 1 Si-30 P0 0 -185 5 2 1 Si-30 P1 0 -186 5 2 1 Si-30 P2 0 -187 5 2 1 Si-30 P3 0 -188 5 2 1 Cr-50 P0 0 -189 5 2 1 Cr-50 P1 0 -190 5 2 1 Cr-50 P2 0 -191 5 2 1 Cr-50 P3 0 -192 5 2 1 Cr-52 P0 0 -193 5 2 1 Cr-52 P1 0 -194 5 2 1 Cr-52 P2 0 -195 5 2 1 Cr-52 P3 0 -196 5 2 1 Cr-53 P0 0 -197 5 2 1 Cr-53 P1 0 -198 5 2 1 Cr-53 P2 0 -199 5 2 1 Cr-53 P3 0 -200 5 2 1 Cr-54 P0 0 -201 5 2 1 Cr-54 P1 0 -202 5 2 1 Cr-54 P2 0 -203 5 2 1 Cr-54 P3 0 -204 5 2 1 C-Nat P0 0 -205 5 2 1 C-Nat P1 0 -206 5 2 1 C-Nat P2 0 -207 5 2 1 C-Nat P3 0 -208 5 2 1 Cu-63 P0 0 -209 5 2 1 Cu-63 P1 0 -210 5 2 1 Cu-63 P2 0 -211 5 2 1 Cu-63 P3 0 -212 5 2 1 Cu-65 P0 0 -213 5 2 1 Cu-65 P1 0 -214 5 2 1 Cu-65 P2 0 -215 5 2 1 Cu-65 P3 0 -0 5 2 2 Fe-54 P0 0 -1 5 2 2 Fe-54 P1 0 -2 5 2 2 Fe-54 P2 0 -3 5 2 2 Fe-54 P3 0 -4 5 2 2 Fe-56 P0 0 -5 5 2 2 Fe-56 P1 0 -6 5 2 2 Fe-56 P2 0 -7 5 2 2 Fe-56 P3 0 -8 5 2 2 Fe-57 P0 0 -9 5 2 2 Fe-57 P1 0 -10 5 2 2 Fe-57 P2 0 -11 5 2 2 Fe-57 P3 0 -12 5 2 2 Fe-58 P0 0 -13 5 2 2 Fe-58 P1 0 -14 5 2 2 Fe-58 P2 0 -15 5 2 2 Fe-58 P3 0 -16 5 2 2 Ni-58 P0 0 -17 5 2 2 Ni-58 P1 0 -18 5 2 2 Ni-58 P2 0 -19 5 2 2 Ni-58 P3 0 -20 5 2 2 Ni-60 P0 0 -21 5 2 2 Ni-60 P1 0 -22 5 2 2 Ni-60 P2 0 -23 5 2 2 Ni-60 P3 0 -24 5 2 2 Ni-61 P0 0 -25 5 2 2 Ni-61 P1 0 -26 5 2 2 Ni-61 P2 0 -27 5 2 2 Ni-61 P3 0 -28 5 2 2 Ni-62 P0 0 -29 5 2 2 Ni-62 P1 0 -30 5 2 2 Ni-62 P2 0 -31 5 2 2 Ni-62 P3 0 -32 5 2 2 Ni-64 P0 0 -33 5 2 2 Ni-64 P1 0 -34 5 2 2 Ni-64 P2 0 -35 5 2 2 Ni-64 P3 0 -36 5 2 2 Mn-55 P0 0 -37 5 2 2 Mn-55 P1 0 -38 5 2 2 Mn-55 P2 0 -39 5 2 2 Mn-55 P3 0 -40 5 2 2 Mo-92 P0 0 -41 5 2 2 Mo-92 P1 0 -42 5 2 2 Mo-92 P2 0 -43 5 2 2 Mo-92 P3 0 -44 5 2 2 Mo-94 P0 0 -45 5 2 2 Mo-94 P1 0 -46 5 2 2 Mo-94 P2 0 -47 5 2 2 Mo-94 P3 0 -48 5 2 2 Mo-95 P0 0 -49 5 2 2 Mo-95 P1 0 -50 5 2 2 Mo-95 P2 0 -51 5 2 2 Mo-95 P3 0 -52 5 2 2 Mo-96 P0 0 -53 5 2 2 Mo-96 P1 0 -54 5 2 2 Mo-96 P2 0 -55 5 2 2 Mo-96 P3 0 -56 5 2 2 Mo-97 P0 0 -57 5 2 2 Mo-97 P1 0 -58 5 2 2 Mo-97 P2 0 -59 5 2 2 Mo-97 P3 0 -60 5 2 2 Mo-98 P0 0 -61 5 2 2 Mo-98 P1 0 -62 5 2 2 Mo-98 P2 0 -63 5 2 2 Mo-98 P3 0 -64 5 2 2 Mo-100 P0 0 -65 5 2 2 Mo-100 P1 0 -66 5 2 2 Mo-100 P2 0 -67 5 2 2 Mo-100 P3 0 -68 5 2 2 Si-28 P0 0 -69 5 2 2 Si-28 P1 0 -70 5 2 2 Si-28 P2 0 -71 5 2 2 Si-28 P3 0 -72 5 2 2 Si-29 P0 0 -73 5 2 2 Si-29 P1 0 -74 5 2 2 Si-29 P2 0 -75 5 2 2 Si-29 P3 0 -76 5 2 2 Si-30 P0 0 -77 5 2 2 Si-30 P1 0 -78 5 2 2 Si-30 P2 0 -79 5 2 2 Si-30 P3 0 -80 5 2 2 Cr-50 P0 0 -81 5 2 2 Cr-50 P1 0 -82 5 2 2 Cr-50 P2 0 -83 5 2 2 Cr-50 P3 0 -84 5 2 2 Cr-52 P0 0 -85 5 2 2 Cr-52 P1 0 -86 5 2 2 Cr-52 P2 0 -87 5 2 2 Cr-52 P3 0 -88 5 2 2 Cr-53 P0 0 -89 5 2 2 Cr-53 P1 0 -90 5 2 2 Cr-53 P2 0 -91 5 2 2 Cr-53 P3 0 -92 5 2 2 Cr-54 P0 0 -93 5 2 2 Cr-54 P1 0 -94 5 2 2 Cr-54 P2 0 -95 5 2 2 Cr-54 P3 0 -96 5 2 2 C-Nat P0 0 -97 5 2 2 C-Nat P1 0 -98 5 2 2 C-Nat P2 0 -99 5 2 2 C-Nat P3 0 -100 5 2 2 Cu-63 P0 0 -101 5 2 2 Cu-63 P1 0 -102 5 2 2 Cu-63 P2 0 -103 5 2 2 Cu-63 P3 0 -104 5 2 2 Cu-65 P0 0 -105 5 2 2 Cu-65 P1 0 -106 5 2 2 Cu-65 P2 0 -107 5 2 2 Cu-65 P3 0 material group out nuclide mean std. dev. -27 5 1 Fe-54 0 0 -28 5 1 Fe-56 0 0 -29 5 1 Fe-57 0 0 -30 5 1 Fe-58 0 0 -31 5 1 Ni-58 0 0 -32 5 1 Ni-60 0 0 -33 5 1 Ni-61 0 0 -34 5 1 Ni-62 0 0 -35 5 1 Ni-64 0 0 -36 5 1 Mn-55 0 0 -37 5 1 Mo-92 0 0 -38 5 1 Mo-94 0 0 -39 5 1 Mo-95 0 0 -40 5 1 Mo-96 0 0 -41 5 1 Mo-97 0 0 -42 5 1 Mo-98 0 0 -43 5 1 Mo-100 0 0 -44 5 1 Si-28 0 0 -45 5 1 Si-29 0 0 -46 5 1 Si-30 0 0 -47 5 1 Cr-50 0 0 -48 5 1 Cr-52 0 0 -49 5 1 Cr-53 0 0 -50 5 1 Cr-54 0 0 -51 5 1 C-Nat 0 0 -52 5 1 Cu-63 0 0 -53 5 1 Cu-65 0 0 -0 5 2 Fe-54 0 0 -1 5 2 Fe-56 0 0 -2 5 2 Fe-57 0 0 -3 5 2 Fe-58 0 0 -4 5 2 Ni-58 0 0 -5 5 2 Ni-60 0 0 -6 5 2 Ni-61 0 0 -7 5 2 Ni-62 0 0 -8 5 2 Ni-64 0 0 -9 5 2 Mn-55 0 0 -10 5 2 Mo-92 0 0 -11 5 2 Mo-94 0 0 -12 5 2 Mo-95 0 0 -13 5 2 Mo-96 0 0 -14 5 2 Mo-97 0 0 -15 5 2 Mo-98 0 0 -16 5 2 Mo-100 0 0 -17 5 2 Si-28 0 0 -18 5 2 Si-29 0 0 -19 5 2 Si-30 0 0 -20 5 2 Cr-50 0 0 -21 5 2 Cr-52 0 0 -22 5 2 Cr-53 0 0 -23 5 2 Cr-54 0 0 -24 5 2 C-Nat 0 0 -25 5 2 Cu-63 0 0 -26 5 2 Cu-65 0 0 material group in nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in group out nuclide moment mean -252 6 1 1 H-1 P0 0 -253 6 1 1 H-1 P1 0 -254 6 1 1 H-1 P2 0 -255 6 1 1 H-1 P3 0 -256 6 1 1 O-16 P0 0 -257 6 1 1 O-16 P1 0 -258 6 1 1 O-16 P2 0 -259 6 1 1 O-16 P3 0 -260 6 1 1 B-10 P0 0 -261 6 1 1 B-10 P1 0 -262 6 1 1 B-10 P2 0 -263 6 1 1 B-10 P3 0 -264 6 1 1 B-11 P0 0 -265 6 1 1 B-11 P1 0 -266 6 1 1 B-11 P2 0 -267 6 1 1 B-11 P3 0 -268 6 1 1 Fe-54 P0 0 -269 6 1 1 Fe-54 P1 0 -270 6 1 1 Fe-54 P2 0 -271 6 1 1 Fe-54 P3 0 -272 6 1 1 Fe-56 P0 0 -273 6 1 1 Fe-56 P1 0 -274 6 1 1 Fe-56 P2 0 -275 6 1 1 Fe-56 P3 0 -276 6 1 1 Fe-57 P0 0 -277 6 1 1 Fe-57 P1 0 -278 6 1 1 Fe-57 P2 0 -279 6 1 1 Fe-57 P3 0 -280 6 1 1 Fe-58 P0 0 -281 6 1 1 Fe-58 P1 0 -282 6 1 1 Fe-58 P2 0 -283 6 1 1 Fe-58 P3 0 -284 6 1 1 Ni-58 P0 0 -285 6 1 1 Ni-58 P1 0 -286 6 1 1 Ni-58 P2 0 -287 6 1 1 Ni-58 P3 0 -288 6 1 1 Ni-60 P0 0 -289 6 1 1 Ni-60 P1 0 -290 6 1 1 Ni-60 P2 0 -291 6 1 1 Ni-60 P3 0 -292 6 1 1 Ni-61 P0 0 -293 6 1 1 Ni-61 P1 0 -294 6 1 1 Ni-61 P2 0 -295 6 1 1 Ni-61 P3 0 -296 6 1 1 Ni-62 P0 0 -297 6 1 1 Ni-62 P1 0 -298 6 1 1 Ni-62 P2 0 -299 6 1 1 Ni-62 P3 0 -300 6 1 1 Ni-64 P0 0 -301 6 1 1 Ni-64 P1 0 -302 6 1 1 Ni-64 P2 0 -303 6 1 1 Ni-64 P3 0 -304 6 1 1 Mn-55 P0 0 -305 6 1 1 Mn-55 P1 0 -306 6 1 1 Mn-55 P2 0 -307 6 1 1 Mn-55 P3 0 -308 6 1 1 Si-28 P0 0 -309 6 1 1 Si-28 P1 0 -310 6 1 1 Si-28 P2 0 -311 6 1 1 Si-28 P3 0 -312 6 1 1 Si-29 P0 0 -313 6 1 1 Si-29 P1 0 -314 6 1 1 Si-29 P2 0 -315 6 1 1 Si-29 P3 0 -316 6 1 1 Si-30 P0 0 -317 6 1 1 Si-30 P1 0 -318 6 1 1 Si-30 P2 0 -319 6 1 1 Si-30 P3 0 -320 6 1 1 Cr-50 P0 0 -321 6 1 1 Cr-50 P1 0 -322 6 1 1 Cr-50 P2 0 -323 6 1 1 Cr-50 P3 0 -324 6 1 1 Cr-52 P0 0 -325 6 1 1 Cr-52 P1 0 -326 6 1 1 Cr-52 P2 0 -327 6 1 1 Cr-52 P3 0 -328 6 1 1 Cr-53 P0 0 -329 6 1 1 Cr-53 P1 0 -330 6 1 1 Cr-53 P2 0 -331 6 1 1 Cr-53 P3 0 -332 6 1 1 Cr-54 P0 0 -333 6 1 1 Cr-54 P1 0 -334 6 1 1 Cr-54 P2 0 -335 6 1 1 Cr-54 P3 0 -168 6 1 2 H-1 P0 0 -169 6 1 2 H-1 P1 0 -170 6 1 2 H-1 P2 0 -171 6 1 2 H-1 P3 0 -172 6 1 2 O-16 P0 0 -173 6 1 2 O-16 P1 0 -174 6 1 2 O-16 P2 0 -175 6 1 2 O-16 P3 0 -176 6 1 2 B-10 P0 0 -177 6 1 2 B-10 P1 0 -178 6 1 2 B-10 P2 0 -179 6 1 2 B-10 P3 0 -180 6 1 2 B-11 P0 0 -181 6 1 2 B-11 P1 0 -182 6 1 2 B-11 P2 0 -183 6 1 2 B-11 P3 0 -184 6 1 2 Fe-54 P0 0 -185 6 1 2 Fe-54 P1 0 -186 6 1 2 Fe-54 P2 0 -187 6 1 2 Fe-54 P3 0 -188 6 1 2 Fe-56 P0 0 -189 6 1 2 Fe-56 P1 0 -190 6 1 2 Fe-56 P2 0 -191 6 1 2 Fe-56 P3 0 -192 6 1 2 Fe-57 P0 0 -193 6 1 2 Fe-57 P1 0 -194 6 1 2 Fe-57 P2 0 -195 6 1 2 Fe-57 P3 0 -196 6 1 2 Fe-58 P0 0 -197 6 1 2 Fe-58 P1 0 -198 6 1 2 Fe-58 P2 0 -199 6 1 2 Fe-58 P3 0 -200 6 1 2 Ni-58 P0 0 -201 6 1 2 Ni-58 P1 0 -202 6 1 2 Ni-58 P2 0 -203 6 1 2 Ni-58 P3 0 -204 6 1 2 Ni-60 P0 0 -205 6 1 2 Ni-60 P1 0 -206 6 1 2 Ni-60 P2 0 -207 6 1 2 Ni-60 P3 0 -208 6 1 2 Ni-61 P0 0 -209 6 1 2 Ni-61 P1 0 -210 6 1 2 Ni-61 P2 0 -211 6 1 2 Ni-61 P3 0 -212 6 1 2 Ni-62 P0 0 -213 6 1 2 Ni-62 P1 0 -214 6 1 2 Ni-62 P2 0 -215 6 1 2 Ni-62 P3 0 -216 6 1 2 Ni-64 P0 0 -217 6 1 2 Ni-64 P1 0 -218 6 1 2 Ni-64 P2 0 -219 6 1 2 Ni-64 P3 0 -220 6 1 2 Mn-55 P0 0 -221 6 1 2 Mn-55 P1 0 -222 6 1 2 Mn-55 P2 0 -223 6 1 2 Mn-55 P3 0 -224 6 1 2 Si-28 P0 0 -225 6 1 2 Si-28 P1 0 -226 6 1 2 Si-28 P2 0 -227 6 1 2 Si-28 P3 0 -228 6 1 2 Si-29 P0 0 -229 6 1 2 Si-29 P1 0 -230 6 1 2 Si-29 P2 0 -231 6 1 2 Si-29 P3 0 -232 6 1 2 Si-30 P0 0 -233 6 1 2 Si-30 P1 0 -234 6 1 2 Si-30 P2 0 -235 6 1 2 Si-30 P3 0 -236 6 1 2 Cr-50 P0 0 -237 6 1 2 Cr-50 P1 0 -238 6 1 2 Cr-50 P2 0 -239 6 1 2 Cr-50 P3 0 -240 6 1 2 Cr-52 P0 0 -241 6 1 2 Cr-52 P1 0 -242 6 1 2 Cr-52 P2 0 -243 6 1 2 Cr-52 P3 0 -244 6 1 2 Cr-53 P0 0 -245 6 1 2 Cr-53 P1 0 -246 6 1 2 Cr-53 P2 0 -247 6 1 2 Cr-53 P3 0 -248 6 1 2 Cr-54 P0 0 -249 6 1 2 Cr-54 P1 0 -250 6 1 2 Cr-54 P2 0 -251 6 1 2 Cr-54 P3 0 -84 6 2 1 H-1 P0 0 -85 6 2 1 H-1 P1 0 -86 6 2 1 H-1 P2 0 -87 6 2 1 H-1 P3 0 -88 6 2 1 O-16 P0 0 -89 6 2 1 O-16 P1 0 -90 6 2 1 O-16 P2 0 -91 6 2 1 O-16 P3 0 -92 6 2 1 B-10 P0 0 -93 6 2 1 B-10 P1 0 -94 6 2 1 B-10 P2 0 -95 6 2 1 B-10 P3 0 -96 6 2 1 B-11 P0 0 -97 6 2 1 B-11 P1 0 -98 6 2 1 B-11 P2 0 -99 6 2 1 B-11 P3 0 -100 6 2 1 Fe-54 P0 0 -101 6 2 1 Fe-54 P1 0 -102 6 2 1 Fe-54 P2 0 -103 6 2 1 Fe-54 P3 0 -104 6 2 1 Fe-56 P0 0 -105 6 2 1 Fe-56 P1 0 -106 6 2 1 Fe-56 P2 0 -107 6 2 1 Fe-56 P3 0 -108 6 2 1 Fe-57 P0 0 -109 6 2 1 Fe-57 P1 0 -110 6 2 1 Fe-57 P2 0 -111 6 2 1 Fe-57 P3 0 -112 6 2 1 Fe-58 P0 0 -113 6 2 1 Fe-58 P1 0 -114 6 2 1 Fe-58 P2 0 -115 6 2 1 Fe-58 P3 0 -116 6 2 1 Ni-58 P0 0 -117 6 2 1 Ni-58 P1 0 -118 6 2 1 Ni-58 P2 0 -119 6 2 1 Ni-58 P3 0 -120 6 2 1 Ni-60 P0 0 -121 6 2 1 Ni-60 P1 0 -122 6 2 1 Ni-60 P2 0 -123 6 2 1 Ni-60 P3 0 -124 6 2 1 Ni-61 P0 0 -125 6 2 1 Ni-61 P1 0 -126 6 2 1 Ni-61 P2 0 -127 6 2 1 Ni-61 P3 0 -128 6 2 1 Ni-62 P0 0 -129 6 2 1 Ni-62 P1 0 -130 6 2 1 Ni-62 P2 0 -131 6 2 1 Ni-62 P3 0 -132 6 2 1 Ni-64 P0 0 -133 6 2 1 Ni-64 P1 0 -134 6 2 1 Ni-64 P2 0 -135 6 2 1 Ni-64 P3 0 -136 6 2 1 Mn-55 P0 0 -137 6 2 1 Mn-55 P1 0 -138 6 2 1 Mn-55 P2 0 -139 6 2 1 Mn-55 P3 0 -140 6 2 1 Si-28 P0 0 -141 6 2 1 Si-28 P1 0 -142 6 2 1 Si-28 P2 0 -143 6 2 1 Si-28 P3 0 -144 6 2 1 Si-29 P0 0 -145 6 2 1 Si-29 P1 0 -146 6 2 1 Si-29 P2 0 -147 6 2 1 Si-29 P3 0 -148 6 2 1 Si-30 P0 0 -149 6 2 1 Si-30 P1 0 -150 6 2 1 Si-30 P2 0 -151 6 2 1 Si-30 P3 0 -152 6 2 1 Cr-50 P0 0 -153 6 2 1 Cr-50 P1 0 -154 6 2 1 Cr-50 P2 0 -155 6 2 1 Cr-50 P3 0 -156 6 2 1 Cr-52 P0 0 -157 6 2 1 Cr-52 P1 0 -158 6 2 1 Cr-52 P2 0 -159 6 2 1 Cr-52 P3 0 -160 6 2 1 Cr-53 P0 0 -161 6 2 1 Cr-53 P1 0 -162 6 2 1 Cr-53 P2 0 -163 6 2 1 Cr-53 P3 0 -164 6 2 1 Cr-54 P0 0 -165 6 2 1 Cr-54 P1 0 -166 6 2 1 Cr-54 P2 0 -167 6 2 1 Cr-54 P3 0 -0 6 2 2 H-1 P0 0 -1 6 2 2 H-1 P1 0 -2 6 2 2 H-1 P2 0 -3 6 2 2 H-1 P3 0 -4 6 2 2 O-16 P0 0 -5 6 2 2 O-16 P1 0 -6 6 2 2 O-16 P2 0 -7 6 2 2 O-16 P3 0 -8 6 2 2 B-10 P0 0 -9 6 2 2 B-10 P1 0 -10 6 2 2 B-10 P2 0 -11 6 2 2 B-10 P3 0 -12 6 2 2 B-11 P0 0 -13 6 2 2 B-11 P1 0 -14 6 2 2 B-11 P2 0 -15 6 2 2 B-11 P3 0 -16 6 2 2 Fe-54 P0 0 -17 6 2 2 Fe-54 P1 0 -18 6 2 2 Fe-54 P2 0 -19 6 2 2 Fe-54 P3 0 -20 6 2 2 Fe-56 P0 0 -21 6 2 2 Fe-56 P1 0 -22 6 2 2 Fe-56 P2 0 -23 6 2 2 Fe-56 P3 0 -24 6 2 2 Fe-57 P0 0 -25 6 2 2 Fe-57 P1 0 -26 6 2 2 Fe-57 P2 0 -27 6 2 2 Fe-57 P3 0 -28 6 2 2 Fe-58 P0 0 -29 6 2 2 Fe-58 P1 0 -30 6 2 2 Fe-58 P2 0 -31 6 2 2 Fe-58 P3 0 -32 6 2 2 Ni-58 P0 0 -33 6 2 2 Ni-58 P1 0 -34 6 2 2 Ni-58 P2 0 -35 6 2 2 Ni-58 P3 0 -36 6 2 2 Ni-60 P0 0 -37 6 2 2 Ni-60 P1 0 -38 6 2 2 Ni-60 P2 0 -39 6 2 2 Ni-60 P3 0 -40 6 2 2 Ni-61 P0 0 -41 6 2 2 Ni-61 P1 0 -42 6 2 2 Ni-61 P2 0 -43 6 2 2 Ni-61 P3 0 -44 6 2 2 Ni-62 P0 0 -45 6 2 2 Ni-62 P1 0 -46 6 2 2 Ni-62 P2 0 -47 6 2 2 Ni-62 P3 0 -48 6 2 2 Ni-64 P0 0 -49 6 2 2 Ni-64 P1 0 -50 6 2 2 Ni-64 P2 0 -51 6 2 2 Ni-64 P3 0 -52 6 2 2 Mn-55 P0 0 -53 6 2 2 Mn-55 P1 0 -54 6 2 2 Mn-55 P2 0 -55 6 2 2 Mn-55 P3 0 -56 6 2 2 Si-28 P0 0 -57 6 2 2 Si-28 P1 0 -58 6 2 2 Si-28 P2 0 -59 6 2 2 Si-28 P3 0 -60 6 2 2 Si-29 P0 0 -61 6 2 2 Si-29 P1 0 -62 6 2 2 Si-29 P2 0 -63 6 2 2 Si-29 P3 0 -64 6 2 2 Si-30 P0 0 -65 6 2 2 Si-30 P1 0 -66 6 2 2 Si-30 P2 0 -67 6 2 2 Si-30 P3 0 -68 6 2 2 Cr-50 P0 0 -69 6 2 2 Cr-50 P1 0 -70 6 2 2 Cr-50 P2 0 -71 6 2 2 Cr-50 P3 0 -72 6 2 2 Cr-52 P0 0 -73 6 2 2 Cr-52 P1 0 -74 6 2 2 Cr-52 P2 0 -75 6 2 2 Cr-52 P3 0 -76 6 2 2 Cr-53 P0 0 -77 6 2 2 Cr-53 P1 0 -78 6 2 2 Cr-53 P2 0 -79 6 2 2 Cr-53 P3 0 -80 6 2 2 Cr-54 P0 0 -81 6 2 2 Cr-54 P1 0 -82 6 2 2 Cr-54 P2 0 -83 6 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. -21 6 1 H-1 0 0 -22 6 1 O-16 0 0 -23 6 1 B-10 0 0 -24 6 1 B-11 0 0 -25 6 1 Fe-54 0 0 -26 6 1 Fe-56 0 0 -27 6 1 Fe-57 0 0 -28 6 1 Fe-58 0 0 -29 6 1 Ni-58 0 0 -30 6 1 Ni-60 0 0 -31 6 1 Ni-61 0 0 -32 6 1 Ni-62 0 0 -33 6 1 Ni-64 0 0 -34 6 1 Mn-55 0 0 -35 6 1 Si-28 0 0 -36 6 1 Si-29 0 0 -37 6 1 Si-30 0 0 -38 6 1 Cr-50 0 0 -39 6 1 Cr-52 0 0 -40 6 1 Cr-53 0 0 -41 6 1 Cr-54 0 0 -0 6 2 H-1 0 0 -1 6 2 O-16 0 0 -2 6 2 B-10 0 0 -3 6 2 B-11 0 0 -4 6 2 Fe-54 0 0 -5 6 2 Fe-56 0 0 -6 6 2 Fe-57 0 0 -7 6 2 Fe-58 0 0 -8 6 2 Ni-58 0 0 -9 6 2 Ni-60 0 0 -10 6 2 Ni-61 0 0 -11 6 2 Ni-62 0 0 -12 6 2 Ni-64 0 0 -13 6 2 Mn-55 0 0 -14 6 2 Si-28 0 0 -15 6 2 Si-29 0 0 -16 6 2 Si-30 0 0 -17 6 2 Cr-50 0 0 -18 6 2 Cr-52 0 0 -19 6 2 Cr-53 0 0 -20 6 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in group out nuclide moment mean -252 7 1 1 H-1 P0 0 -253 7 1 1 H-1 P1 0 -254 7 1 1 H-1 P2 0 -255 7 1 1 H-1 P3 0 -256 7 1 1 O-16 P0 0 -257 7 1 1 O-16 P1 0 -258 7 1 1 O-16 P2 0 -259 7 1 1 O-16 P3 0 -260 7 1 1 B-10 P0 0 -261 7 1 1 B-10 P1 0 -262 7 1 1 B-10 P2 0 -263 7 1 1 B-10 P3 0 -264 7 1 1 B-11 P0 0 -265 7 1 1 B-11 P1 0 -266 7 1 1 B-11 P2 0 -267 7 1 1 B-11 P3 0 -268 7 1 1 Fe-54 P0 0 -269 7 1 1 Fe-54 P1 0 -270 7 1 1 Fe-54 P2 0 -271 7 1 1 Fe-54 P3 0 -272 7 1 1 Fe-56 P0 0 -273 7 1 1 Fe-56 P1 0 -274 7 1 1 Fe-56 P2 0 -275 7 1 1 Fe-56 P3 0 -276 7 1 1 Fe-57 P0 0 -277 7 1 1 Fe-57 P1 0 -278 7 1 1 Fe-57 P2 0 -279 7 1 1 Fe-57 P3 0 -280 7 1 1 Fe-58 P0 0 -281 7 1 1 Fe-58 P1 0 -282 7 1 1 Fe-58 P2 0 -283 7 1 1 Fe-58 P3 0 -284 7 1 1 Ni-58 P0 0 -285 7 1 1 Ni-58 P1 0 -286 7 1 1 Ni-58 P2 0 -287 7 1 1 Ni-58 P3 0 -288 7 1 1 Ni-60 P0 0 -289 7 1 1 Ni-60 P1 0 -290 7 1 1 Ni-60 P2 0 -291 7 1 1 Ni-60 P3 0 -292 7 1 1 Ni-61 P0 0 -293 7 1 1 Ni-61 P1 0 -294 7 1 1 Ni-61 P2 0 -295 7 1 1 Ni-61 P3 0 -296 7 1 1 Ni-62 P0 0 -297 7 1 1 Ni-62 P1 0 -298 7 1 1 Ni-62 P2 0 -299 7 1 1 Ni-62 P3 0 -300 7 1 1 Ni-64 P0 0 -301 7 1 1 Ni-64 P1 0 -302 7 1 1 Ni-64 P2 0 -303 7 1 1 Ni-64 P3 0 -304 7 1 1 Mn-55 P0 0 -305 7 1 1 Mn-55 P1 0 -306 7 1 1 Mn-55 P2 0 -307 7 1 1 Mn-55 P3 0 -308 7 1 1 Si-28 P0 0 -309 7 1 1 Si-28 P1 0 -310 7 1 1 Si-28 P2 0 -311 7 1 1 Si-28 P3 0 -312 7 1 1 Si-29 P0 0 -313 7 1 1 Si-29 P1 0 -314 7 1 1 Si-29 P2 0 -315 7 1 1 Si-29 P3 0 -316 7 1 1 Si-30 P0 0 -317 7 1 1 Si-30 P1 0 -318 7 1 1 Si-30 P2 0 -319 7 1 1 Si-30 P3 0 -320 7 1 1 Cr-50 P0 0 -321 7 1 1 Cr-50 P1 0 -322 7 1 1 Cr-50 P2 0 -323 7 1 1 Cr-50 P3 0 -324 7 1 1 Cr-52 P0 0 -325 7 1 1 Cr-52 P1 0 -326 7 1 1 Cr-52 P2 0 -327 7 1 1 Cr-52 P3 0 -328 7 1 1 Cr-53 P0 0 -329 7 1 1 Cr-53 P1 0 -330 7 1 1 Cr-53 P2 0 -331 7 1 1 Cr-53 P3 0 -332 7 1 1 Cr-54 P0 0 -333 7 1 1 Cr-54 P1 0 -334 7 1 1 Cr-54 P2 0 -335 7 1 1 Cr-54 P3 0 -168 7 1 2 H-1 P0 0 -169 7 1 2 H-1 P1 0 -170 7 1 2 H-1 P2 0 -171 7 1 2 H-1 P3 0 -172 7 1 2 O-16 P0 0 -173 7 1 2 O-16 P1 0 -174 7 1 2 O-16 P2 0 -175 7 1 2 O-16 P3 0 -176 7 1 2 B-10 P0 0 -177 7 1 2 B-10 P1 0 -178 7 1 2 B-10 P2 0 -179 7 1 2 B-10 P3 0 -180 7 1 2 B-11 P0 0 -181 7 1 2 B-11 P1 0 -182 7 1 2 B-11 P2 0 -183 7 1 2 B-11 P3 0 -184 7 1 2 Fe-54 P0 0 -185 7 1 2 Fe-54 P1 0 -186 7 1 2 Fe-54 P2 0 -187 7 1 2 Fe-54 P3 0 -188 7 1 2 Fe-56 P0 0 -189 7 1 2 Fe-56 P1 0 -190 7 1 2 Fe-56 P2 0 -191 7 1 2 Fe-56 P3 0 -192 7 1 2 Fe-57 P0 0 -193 7 1 2 Fe-57 P1 0 -194 7 1 2 Fe-57 P2 0 -195 7 1 2 Fe-57 P3 0 -196 7 1 2 Fe-58 P0 0 -197 7 1 2 Fe-58 P1 0 -198 7 1 2 Fe-58 P2 0 -199 7 1 2 Fe-58 P3 0 -200 7 1 2 Ni-58 P0 0 -201 7 1 2 Ni-58 P1 0 -202 7 1 2 Ni-58 P2 0 -203 7 1 2 Ni-58 P3 0 -204 7 1 2 Ni-60 P0 0 -205 7 1 2 Ni-60 P1 0 -206 7 1 2 Ni-60 P2 0 -207 7 1 2 Ni-60 P3 0 -208 7 1 2 Ni-61 P0 0 -209 7 1 2 Ni-61 P1 0 -210 7 1 2 Ni-61 P2 0 -211 7 1 2 Ni-61 P3 0 -212 7 1 2 Ni-62 P0 0 -213 7 1 2 Ni-62 P1 0 -214 7 1 2 Ni-62 P2 0 -215 7 1 2 Ni-62 P3 0 -216 7 1 2 Ni-64 P0 0 -217 7 1 2 Ni-64 P1 0 -218 7 1 2 Ni-64 P2 0 -219 7 1 2 Ni-64 P3 0 -220 7 1 2 Mn-55 P0 0 -221 7 1 2 Mn-55 P1 0 -222 7 1 2 Mn-55 P2 0 -223 7 1 2 Mn-55 P3 0 -224 7 1 2 Si-28 P0 0 -225 7 1 2 Si-28 P1 0 -226 7 1 2 Si-28 P2 0 -227 7 1 2 Si-28 P3 0 -228 7 1 2 Si-29 P0 0 -229 7 1 2 Si-29 P1 0 -230 7 1 2 Si-29 P2 0 -231 7 1 2 Si-29 P3 0 -232 7 1 2 Si-30 P0 0 -233 7 1 2 Si-30 P1 0 -234 7 1 2 Si-30 P2 0 -235 7 1 2 Si-30 P3 0 -236 7 1 2 Cr-50 P0 0 -237 7 1 2 Cr-50 P1 0 -238 7 1 2 Cr-50 P2 0 -239 7 1 2 Cr-50 P3 0 -240 7 1 2 Cr-52 P0 0 -241 7 1 2 Cr-52 P1 0 -242 7 1 2 Cr-52 P2 0 -243 7 1 2 Cr-52 P3 0 -244 7 1 2 Cr-53 P0 0 -245 7 1 2 Cr-53 P1 0 -246 7 1 2 Cr-53 P2 0 -247 7 1 2 Cr-53 P3 0 -248 7 1 2 Cr-54 P0 0 -249 7 1 2 Cr-54 P1 0 -250 7 1 2 Cr-54 P2 0 -251 7 1 2 Cr-54 P3 0 -84 7 2 1 H-1 P0 0 -85 7 2 1 H-1 P1 0 -86 7 2 1 H-1 P2 0 -87 7 2 1 H-1 P3 0 -88 7 2 1 O-16 P0 0 -89 7 2 1 O-16 P1 0 -90 7 2 1 O-16 P2 0 -91 7 2 1 O-16 P3 0 -92 7 2 1 B-10 P0 0 -93 7 2 1 B-10 P1 0 -94 7 2 1 B-10 P2 0 -95 7 2 1 B-10 P3 0 -96 7 2 1 B-11 P0 0 -97 7 2 1 B-11 P1 0 -98 7 2 1 B-11 P2 0 -99 7 2 1 B-11 P3 0 -100 7 2 1 Fe-54 P0 0 -101 7 2 1 Fe-54 P1 0 -102 7 2 1 Fe-54 P2 0 -103 7 2 1 Fe-54 P3 0 -104 7 2 1 Fe-56 P0 0 -105 7 2 1 Fe-56 P1 0 -106 7 2 1 Fe-56 P2 0 -107 7 2 1 Fe-56 P3 0 -108 7 2 1 Fe-57 P0 0 -109 7 2 1 Fe-57 P1 0 -110 7 2 1 Fe-57 P2 0 -111 7 2 1 Fe-57 P3 0 -112 7 2 1 Fe-58 P0 0 -113 7 2 1 Fe-58 P1 0 -114 7 2 1 Fe-58 P2 0 -115 7 2 1 Fe-58 P3 0 -116 7 2 1 Ni-58 P0 0 -117 7 2 1 Ni-58 P1 0 -118 7 2 1 Ni-58 P2 0 -119 7 2 1 Ni-58 P3 0 -120 7 2 1 Ni-60 P0 0 -121 7 2 1 Ni-60 P1 0 -122 7 2 1 Ni-60 P2 0 -123 7 2 1 Ni-60 P3 0 -124 7 2 1 Ni-61 P0 0 -125 7 2 1 Ni-61 P1 0 -126 7 2 1 Ni-61 P2 0 -127 7 2 1 Ni-61 P3 0 -128 7 2 1 Ni-62 P0 0 -129 7 2 1 Ni-62 P1 0 -130 7 2 1 Ni-62 P2 0 -131 7 2 1 Ni-62 P3 0 -132 7 2 1 Ni-64 P0 0 -133 7 2 1 Ni-64 P1 0 -134 7 2 1 Ni-64 P2 0 -135 7 2 1 Ni-64 P3 0 -136 7 2 1 Mn-55 P0 0 -137 7 2 1 Mn-55 P1 0 -138 7 2 1 Mn-55 P2 0 -139 7 2 1 Mn-55 P3 0 -140 7 2 1 Si-28 P0 0 -141 7 2 1 Si-28 P1 0 -142 7 2 1 Si-28 P2 0 -143 7 2 1 Si-28 P3 0 -144 7 2 1 Si-29 P0 0 -145 7 2 1 Si-29 P1 0 -146 7 2 1 Si-29 P2 0 -147 7 2 1 Si-29 P3 0 -148 7 2 1 Si-30 P0 0 -149 7 2 1 Si-30 P1 0 -150 7 2 1 Si-30 P2 0 -151 7 2 1 Si-30 P3 0 -152 7 2 1 Cr-50 P0 0 -153 7 2 1 Cr-50 P1 0 -154 7 2 1 Cr-50 P2 0 -155 7 2 1 Cr-50 P3 0 -156 7 2 1 Cr-52 P0 0 -157 7 2 1 Cr-52 P1 0 -158 7 2 1 Cr-52 P2 0 -159 7 2 1 Cr-52 P3 0 -160 7 2 1 Cr-53 P0 0 -161 7 2 1 Cr-53 P1 0 -162 7 2 1 Cr-53 P2 0 -163 7 2 1 Cr-53 P3 0 -164 7 2 1 Cr-54 P0 0 -165 7 2 1 Cr-54 P1 0 -166 7 2 1 Cr-54 P2 0 -167 7 2 1 Cr-54 P3 0 -0 7 2 2 H-1 P0 0 -1 7 2 2 H-1 P1 0 -2 7 2 2 H-1 P2 0 -3 7 2 2 H-1 P3 0 -4 7 2 2 O-16 P0 0 -5 7 2 2 O-16 P1 0 -6 7 2 2 O-16 P2 0 -7 7 2 2 O-16 P3 0 -8 7 2 2 B-10 P0 0 -9 7 2 2 B-10 P1 0 -10 7 2 2 B-10 P2 0 -11 7 2 2 B-10 P3 0 -12 7 2 2 B-11 P0 0 -13 7 2 2 B-11 P1 0 -14 7 2 2 B-11 P2 0 -15 7 2 2 B-11 P3 0 -16 7 2 2 Fe-54 P0 0 -17 7 2 2 Fe-54 P1 0 -18 7 2 2 Fe-54 P2 0 -19 7 2 2 Fe-54 P3 0 -20 7 2 2 Fe-56 P0 0 -21 7 2 2 Fe-56 P1 0 -22 7 2 2 Fe-56 P2 0 -23 7 2 2 Fe-56 P3 0 -24 7 2 2 Fe-57 P0 0 -25 7 2 2 Fe-57 P1 0 -26 7 2 2 Fe-57 P2 0 -27 7 2 2 Fe-57 P3 0 -28 7 2 2 Fe-58 P0 0 -29 7 2 2 Fe-58 P1 0 -30 7 2 2 Fe-58 P2 0 -31 7 2 2 Fe-58 P3 0 -32 7 2 2 Ni-58 P0 0 -33 7 2 2 Ni-58 P1 0 -34 7 2 2 Ni-58 P2 0 -35 7 2 2 Ni-58 P3 0 -36 7 2 2 Ni-60 P0 0 -37 7 2 2 Ni-60 P1 0 -38 7 2 2 Ni-60 P2 0 -39 7 2 2 Ni-60 P3 0 -40 7 2 2 Ni-61 P0 0 -41 7 2 2 Ni-61 P1 0 -42 7 2 2 Ni-61 P2 0 -43 7 2 2 Ni-61 P3 0 -44 7 2 2 Ni-62 P0 0 -45 7 2 2 Ni-62 P1 0 -46 7 2 2 Ni-62 P2 0 -47 7 2 2 Ni-62 P3 0 -48 7 2 2 Ni-64 P0 0 -49 7 2 2 Ni-64 P1 0 -50 7 2 2 Ni-64 P2 0 -51 7 2 2 Ni-64 P3 0 -52 7 2 2 Mn-55 P0 0 -53 7 2 2 Mn-55 P1 0 -54 7 2 2 Mn-55 P2 0 -55 7 2 2 Mn-55 P3 0 -56 7 2 2 Si-28 P0 0 -57 7 2 2 Si-28 P1 0 -58 7 2 2 Si-28 P2 0 -59 7 2 2 Si-28 P3 0 -60 7 2 2 Si-29 P0 0 -61 7 2 2 Si-29 P1 0 -62 7 2 2 Si-29 P2 0 -63 7 2 2 Si-29 P3 0 -64 7 2 2 Si-30 P0 0 -65 7 2 2 Si-30 P1 0 -66 7 2 2 Si-30 P2 0 -67 7 2 2 Si-30 P3 0 -68 7 2 2 Cr-50 P0 0 -69 7 2 2 Cr-50 P1 0 -70 7 2 2 Cr-50 P2 0 -71 7 2 2 Cr-50 P3 0 -72 7 2 2 Cr-52 P0 0 -73 7 2 2 Cr-52 P1 0 -74 7 2 2 Cr-52 P2 0 -75 7 2 2 Cr-52 P3 0 -76 7 2 2 Cr-53 P0 0 -77 7 2 2 Cr-53 P1 0 -78 7 2 2 Cr-53 P2 0 -79 7 2 2 Cr-53 P3 0 -80 7 2 2 Cr-54 P0 0 -81 7 2 2 Cr-54 P1 0 -82 7 2 2 Cr-54 P2 0 -83 7 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. -21 7 1 H-1 0 0 -22 7 1 O-16 0 0 -23 7 1 B-10 0 0 -24 7 1 B-11 0 0 -25 7 1 Fe-54 0 0 -26 7 1 Fe-56 0 0 -27 7 1 Fe-57 0 0 -28 7 1 Fe-58 0 0 -29 7 1 Ni-58 0 0 -30 7 1 Ni-60 0 0 -31 7 1 Ni-61 0 0 -32 7 1 Ni-62 0 0 -33 7 1 Ni-64 0 0 -34 7 1 Mn-55 0 0 -35 7 1 Si-28 0 0 -36 7 1 Si-29 0 0 -37 7 1 Si-30 0 0 -38 7 1 Cr-50 0 0 -39 7 1 Cr-52 0 0 -40 7 1 Cr-53 0 0 -41 7 1 Cr-54 0 0 -0 7 2 H-1 0 0 -1 7 2 O-16 0 0 -2 7 2 B-10 0 0 -3 7 2 B-11 0 0 -4 7 2 Fe-54 0 0 -5 7 2 Fe-56 0 0 -6 7 2 Fe-57 0 0 -7 7 2 Fe-58 0 0 -8 7 2 Ni-58 0 0 -9 7 2 Ni-60 0 0 -10 7 2 Ni-61 0 0 -11 7 2 Ni-62 0 0 -12 7 2 Ni-64 0 0 -13 7 2 Mn-55 0 0 -14 7 2 Si-28 0 0 -15 7 2 Si-29 0 0 -16 7 2 Si-30 0 0 -17 7 2 Cr-50 0 0 -18 7 2 Cr-52 0 0 -19 7 2 Cr-53 0 0 -20 7 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in group out nuclide moment mean -252 8 1 1 H-1 P0 0 -253 8 1 1 H-1 P1 0 -254 8 1 1 H-1 P2 0 -255 8 1 1 H-1 P3 0 -256 8 1 1 O-16 P0 0 -257 8 1 1 O-16 P1 0 -258 8 1 1 O-16 P2 0 -259 8 1 1 O-16 P3 0 -260 8 1 1 B-10 P0 0 -261 8 1 1 B-10 P1 0 -262 8 1 1 B-10 P2 0 -263 8 1 1 B-10 P3 0 -264 8 1 1 B-11 P0 0 -265 8 1 1 B-11 P1 0 -266 8 1 1 B-11 P2 0 -267 8 1 1 B-11 P3 0 -268 8 1 1 Fe-54 P0 0 -269 8 1 1 Fe-54 P1 0 -270 8 1 1 Fe-54 P2 0 -271 8 1 1 Fe-54 P3 0 -272 8 1 1 Fe-56 P0 0 -273 8 1 1 Fe-56 P1 0 -274 8 1 1 Fe-56 P2 0 -275 8 1 1 Fe-56 P3 0 -276 8 1 1 Fe-57 P0 0 -277 8 1 1 Fe-57 P1 0 -278 8 1 1 Fe-57 P2 0 -279 8 1 1 Fe-57 P3 0 -280 8 1 1 Fe-58 P0 0 -281 8 1 1 Fe-58 P1 0 -282 8 1 1 Fe-58 P2 0 -283 8 1 1 Fe-58 P3 0 -284 8 1 1 Ni-58 P0 0 -285 8 1 1 Ni-58 P1 0 -286 8 1 1 Ni-58 P2 0 -287 8 1 1 Ni-58 P3 0 -288 8 1 1 Ni-60 P0 0 -289 8 1 1 Ni-60 P1 0 -290 8 1 1 Ni-60 P2 0 -291 8 1 1 Ni-60 P3 0 -292 8 1 1 Ni-61 P0 0 -293 8 1 1 Ni-61 P1 0 -294 8 1 1 Ni-61 P2 0 -295 8 1 1 Ni-61 P3 0 -296 8 1 1 Ni-62 P0 0 -297 8 1 1 Ni-62 P1 0 -298 8 1 1 Ni-62 P2 0 -299 8 1 1 Ni-62 P3 0 -300 8 1 1 Ni-64 P0 0 -301 8 1 1 Ni-64 P1 0 -302 8 1 1 Ni-64 P2 0 -303 8 1 1 Ni-64 P3 0 -304 8 1 1 Mn-55 P0 0 -305 8 1 1 Mn-55 P1 0 -306 8 1 1 Mn-55 P2 0 -307 8 1 1 Mn-55 P3 0 -308 8 1 1 Si-28 P0 0 -309 8 1 1 Si-28 P1 0 -310 8 1 1 Si-28 P2 0 -311 8 1 1 Si-28 P3 0 -312 8 1 1 Si-29 P0 0 -313 8 1 1 Si-29 P1 0 -314 8 1 1 Si-29 P2 0 -315 8 1 1 Si-29 P3 0 -316 8 1 1 Si-30 P0 0 -317 8 1 1 Si-30 P1 0 -318 8 1 1 Si-30 P2 0 -319 8 1 1 Si-30 P3 0 -320 8 1 1 Cr-50 P0 0 -321 8 1 1 Cr-50 P1 0 -322 8 1 1 Cr-50 P2 0 -323 8 1 1 Cr-50 P3 0 -324 8 1 1 Cr-52 P0 0 -325 8 1 1 Cr-52 P1 0 -326 8 1 1 Cr-52 P2 0 -327 8 1 1 Cr-52 P3 0 -328 8 1 1 Cr-53 P0 0 -329 8 1 1 Cr-53 P1 0 -330 8 1 1 Cr-53 P2 0 -331 8 1 1 Cr-53 P3 0 -332 8 1 1 Cr-54 P0 0 -333 8 1 1 Cr-54 P1 0 -334 8 1 1 Cr-54 P2 0 -335 8 1 1 Cr-54 P3 0 -168 8 1 2 H-1 P0 0 -169 8 1 2 H-1 P1 0 -170 8 1 2 H-1 P2 0 -171 8 1 2 H-1 P3 0 -172 8 1 2 O-16 P0 0 -173 8 1 2 O-16 P1 0 -174 8 1 2 O-16 P2 0 -175 8 1 2 O-16 P3 0 -176 8 1 2 B-10 P0 0 -177 8 1 2 B-10 P1 0 -178 8 1 2 B-10 P2 0 -179 8 1 2 B-10 P3 0 -180 8 1 2 B-11 P0 0 -181 8 1 2 B-11 P1 0 -182 8 1 2 B-11 P2 0 -183 8 1 2 B-11 P3 0 -184 8 1 2 Fe-54 P0 0 -185 8 1 2 Fe-54 P1 0 -186 8 1 2 Fe-54 P2 0 -187 8 1 2 Fe-54 P3 0 -188 8 1 2 Fe-56 P0 0 -189 8 1 2 Fe-56 P1 0 -190 8 1 2 Fe-56 P2 0 -191 8 1 2 Fe-56 P3 0 -192 8 1 2 Fe-57 P0 0 -193 8 1 2 Fe-57 P1 0 -194 8 1 2 Fe-57 P2 0 -195 8 1 2 Fe-57 P3 0 -196 8 1 2 Fe-58 P0 0 -197 8 1 2 Fe-58 P1 0 -198 8 1 2 Fe-58 P2 0 -199 8 1 2 Fe-58 P3 0 -200 8 1 2 Ni-58 P0 0 -201 8 1 2 Ni-58 P1 0 -202 8 1 2 Ni-58 P2 0 -203 8 1 2 Ni-58 P3 0 -204 8 1 2 Ni-60 P0 0 -205 8 1 2 Ni-60 P1 0 -206 8 1 2 Ni-60 P2 0 -207 8 1 2 Ni-60 P3 0 -208 8 1 2 Ni-61 P0 0 -209 8 1 2 Ni-61 P1 0 -210 8 1 2 Ni-61 P2 0 -211 8 1 2 Ni-61 P3 0 -212 8 1 2 Ni-62 P0 0 -213 8 1 2 Ni-62 P1 0 -214 8 1 2 Ni-62 P2 0 -215 8 1 2 Ni-62 P3 0 -216 8 1 2 Ni-64 P0 0 -217 8 1 2 Ni-64 P1 0 -218 8 1 2 Ni-64 P2 0 -219 8 1 2 Ni-64 P3 0 -220 8 1 2 Mn-55 P0 0 -221 8 1 2 Mn-55 P1 0 -222 8 1 2 Mn-55 P2 0 -223 8 1 2 Mn-55 P3 0 -224 8 1 2 Si-28 P0 0 -225 8 1 2 Si-28 P1 0 -226 8 1 2 Si-28 P2 0 -227 8 1 2 Si-28 P3 0 -228 8 1 2 Si-29 P0 0 -229 8 1 2 Si-29 P1 0 -230 8 1 2 Si-29 P2 0 -231 8 1 2 Si-29 P3 0 -232 8 1 2 Si-30 P0 0 -233 8 1 2 Si-30 P1 0 -234 8 1 2 Si-30 P2 0 -235 8 1 2 Si-30 P3 0 -236 8 1 2 Cr-50 P0 0 -237 8 1 2 Cr-50 P1 0 -238 8 1 2 Cr-50 P2 0 -239 8 1 2 Cr-50 P3 0 -240 8 1 2 Cr-52 P0 0 -241 8 1 2 Cr-52 P1 0 -242 8 1 2 Cr-52 P2 0 -243 8 1 2 Cr-52 P3 0 -244 8 1 2 Cr-53 P0 0 -245 8 1 2 Cr-53 P1 0 -246 8 1 2 Cr-53 P2 0 -247 8 1 2 Cr-53 P3 0 -248 8 1 2 Cr-54 P0 0 -249 8 1 2 Cr-54 P1 0 -250 8 1 2 Cr-54 P2 0 -251 8 1 2 Cr-54 P3 0 -84 8 2 1 H-1 P0 0 -85 8 2 1 H-1 P1 0 -86 8 2 1 H-1 P2 0 -87 8 2 1 H-1 P3 0 -88 8 2 1 O-16 P0 0 -89 8 2 1 O-16 P1 0 -90 8 2 1 O-16 P2 0 -91 8 2 1 O-16 P3 0 -92 8 2 1 B-10 P0 0 -93 8 2 1 B-10 P1 0 -94 8 2 1 B-10 P2 0 -95 8 2 1 B-10 P3 0 -96 8 2 1 B-11 P0 0 -97 8 2 1 B-11 P1 0 -98 8 2 1 B-11 P2 0 -99 8 2 1 B-11 P3 0 -100 8 2 1 Fe-54 P0 0 -101 8 2 1 Fe-54 P1 0 -102 8 2 1 Fe-54 P2 0 -103 8 2 1 Fe-54 P3 0 -104 8 2 1 Fe-56 P0 0 -105 8 2 1 Fe-56 P1 0 -106 8 2 1 Fe-56 P2 0 -107 8 2 1 Fe-56 P3 0 -108 8 2 1 Fe-57 P0 0 -109 8 2 1 Fe-57 P1 0 -110 8 2 1 Fe-57 P2 0 -111 8 2 1 Fe-57 P3 0 -112 8 2 1 Fe-58 P0 0 -113 8 2 1 Fe-58 P1 0 -114 8 2 1 Fe-58 P2 0 -115 8 2 1 Fe-58 P3 0 -116 8 2 1 Ni-58 P0 0 -117 8 2 1 Ni-58 P1 0 -118 8 2 1 Ni-58 P2 0 -119 8 2 1 Ni-58 P3 0 -120 8 2 1 Ni-60 P0 0 -121 8 2 1 Ni-60 P1 0 -122 8 2 1 Ni-60 P2 0 -123 8 2 1 Ni-60 P3 0 -124 8 2 1 Ni-61 P0 0 -125 8 2 1 Ni-61 P1 0 -126 8 2 1 Ni-61 P2 0 -127 8 2 1 Ni-61 P3 0 -128 8 2 1 Ni-62 P0 0 -129 8 2 1 Ni-62 P1 0 -130 8 2 1 Ni-62 P2 0 -131 8 2 1 Ni-62 P3 0 -132 8 2 1 Ni-64 P0 0 -133 8 2 1 Ni-64 P1 0 -134 8 2 1 Ni-64 P2 0 -135 8 2 1 Ni-64 P3 0 -136 8 2 1 Mn-55 P0 0 -137 8 2 1 Mn-55 P1 0 -138 8 2 1 Mn-55 P2 0 -139 8 2 1 Mn-55 P3 0 -140 8 2 1 Si-28 P0 0 -141 8 2 1 Si-28 P1 0 -142 8 2 1 Si-28 P2 0 -143 8 2 1 Si-28 P3 0 -144 8 2 1 Si-29 P0 0 -145 8 2 1 Si-29 P1 0 -146 8 2 1 Si-29 P2 0 -147 8 2 1 Si-29 P3 0 -148 8 2 1 Si-30 P0 0 -149 8 2 1 Si-30 P1 0 -150 8 2 1 Si-30 P2 0 -151 8 2 1 Si-30 P3 0 -152 8 2 1 Cr-50 P0 0 -153 8 2 1 Cr-50 P1 0 -154 8 2 1 Cr-50 P2 0 -155 8 2 1 Cr-50 P3 0 -156 8 2 1 Cr-52 P0 0 -157 8 2 1 Cr-52 P1 0 -158 8 2 1 Cr-52 P2 0 -159 8 2 1 Cr-52 P3 0 -160 8 2 1 Cr-53 P0 0 -161 8 2 1 Cr-53 P1 0 -162 8 2 1 Cr-53 P2 0 -163 8 2 1 Cr-53 P3 0 -164 8 2 1 Cr-54 P0 0 -165 8 2 1 Cr-54 P1 0 -166 8 2 1 Cr-54 P2 0 -167 8 2 1 Cr-54 P3 0 -0 8 2 2 H-1 P0 0 -1 8 2 2 H-1 P1 0 -2 8 2 2 H-1 P2 0 -3 8 2 2 H-1 P3 0 -4 8 2 2 O-16 P0 0 -5 8 2 2 O-16 P1 0 -6 8 2 2 O-16 P2 0 -7 8 2 2 O-16 P3 0 -8 8 2 2 B-10 P0 0 -9 8 2 2 B-10 P1 0 -10 8 2 2 B-10 P2 0 -11 8 2 2 B-10 P3 0 -12 8 2 2 B-11 P0 0 -13 8 2 2 B-11 P1 0 -14 8 2 2 B-11 P2 0 -15 8 2 2 B-11 P3 0 -16 8 2 2 Fe-54 P0 0 -17 8 2 2 Fe-54 P1 0 -18 8 2 2 Fe-54 P2 0 -19 8 2 2 Fe-54 P3 0 -20 8 2 2 Fe-56 P0 0 -21 8 2 2 Fe-56 P1 0 -22 8 2 2 Fe-56 P2 0 -23 8 2 2 Fe-56 P3 0 -24 8 2 2 Fe-57 P0 0 -25 8 2 2 Fe-57 P1 0 -26 8 2 2 Fe-57 P2 0 -27 8 2 2 Fe-57 P3 0 -28 8 2 2 Fe-58 P0 0 -29 8 2 2 Fe-58 P1 0 -30 8 2 2 Fe-58 P2 0 -31 8 2 2 Fe-58 P3 0 -32 8 2 2 Ni-58 P0 0 -33 8 2 2 Ni-58 P1 0 -34 8 2 2 Ni-58 P2 0 -35 8 2 2 Ni-58 P3 0 -36 8 2 2 Ni-60 P0 0 -37 8 2 2 Ni-60 P1 0 -38 8 2 2 Ni-60 P2 0 -39 8 2 2 Ni-60 P3 0 -40 8 2 2 Ni-61 P0 0 -41 8 2 2 Ni-61 P1 0 -42 8 2 2 Ni-61 P2 0 -43 8 2 2 Ni-61 P3 0 -44 8 2 2 Ni-62 P0 0 -45 8 2 2 Ni-62 P1 0 -46 8 2 2 Ni-62 P2 0 -47 8 2 2 Ni-62 P3 0 -48 8 2 2 Ni-64 P0 0 -49 8 2 2 Ni-64 P1 0 -50 8 2 2 Ni-64 P2 0 -51 8 2 2 Ni-64 P3 0 -52 8 2 2 Mn-55 P0 0 -53 8 2 2 Mn-55 P1 0 -54 8 2 2 Mn-55 P2 0 -55 8 2 2 Mn-55 P3 0 -56 8 2 2 Si-28 P0 0 -57 8 2 2 Si-28 P1 0 -58 8 2 2 Si-28 P2 0 -59 8 2 2 Si-28 P3 0 -60 8 2 2 Si-29 P0 0 -61 8 2 2 Si-29 P1 0 -62 8 2 2 Si-29 P2 0 -63 8 2 2 Si-29 P3 0 -64 8 2 2 Si-30 P0 0 -65 8 2 2 Si-30 P1 0 -66 8 2 2 Si-30 P2 0 -67 8 2 2 Si-30 P3 0 -68 8 2 2 Cr-50 P0 0 -69 8 2 2 Cr-50 P1 0 -70 8 2 2 Cr-50 P2 0 -71 8 2 2 Cr-50 P3 0 -72 8 2 2 Cr-52 P0 0 -73 8 2 2 Cr-52 P1 0 -74 8 2 2 Cr-52 P2 0 -75 8 2 2 Cr-52 P3 0 -76 8 2 2 Cr-53 P0 0 -77 8 2 2 Cr-53 P1 0 -78 8 2 2 Cr-53 P2 0 -79 8 2 2 Cr-53 P3 0 -80 8 2 2 Cr-54 P0 0 -81 8 2 2 Cr-54 P1 0 -82 8 2 2 Cr-54 P2 0 -83 8 2 2 Cr-54 P3 0 material group out nuclide mean std. dev. -21 8 1 H-1 0 0 -22 8 1 O-16 0 0 -23 8 1 B-10 0 0 -24 8 1 B-11 0 0 -25 8 1 Fe-54 0 0 -26 8 1 Fe-56 0 0 -27 8 1 Fe-57 0 0 -28 8 1 Fe-58 0 0 -29 8 1 Ni-58 0 0 -30 8 1 Ni-60 0 0 -31 8 1 Ni-61 0 0 -32 8 1 Ni-62 0 0 -33 8 1 Ni-64 0 0 -34 8 1 Mn-55 0 0 -35 8 1 Si-28 0 0 -36 8 1 Si-29 0 0 -37 8 1 Si-30 0 0 -38 8 1 Cr-50 0 0 -39 8 1 Cr-52 0 0 -40 8 1 Cr-53 0 0 -41 8 1 Cr-54 0 0 -0 8 2 H-1 0 0 -1 8 2 O-16 0 0 -2 8 2 B-10 0 0 -3 8 2 B-11 0 0 -4 8 2 Fe-54 0 0 -5 8 2 Fe-56 0 0 -6 8 2 Fe-57 0 0 -7 8 2 Fe-58 0 0 -8 8 2 Ni-58 0 0 -9 8 2 Ni-60 0 0 -10 8 2 Ni-61 0 0 -11 8 2 Ni-62 0 0 -12 8 2 Ni-64 0 0 -13 8 2 Mn-55 0 0 -14 8 2 Si-28 0 0 -15 8 2 Si-29 0 0 -16 8 2 Si-30 0 0 -17 8 2 Cr-50 0 0 -18 8 2 Cr-52 0 0 -19 8 2 Cr-53 0 0 -20 8 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 9 1 H-1 0.150655 0.480993 -22 9 1 O-16 0.116221 0.114089 -23 9 1 B-10 0.000000 0.000000 -24 9 1 B-11 0.000000 0.000000 -25 9 1 Fe-54 0.000000 0.000000 -26 9 1 Fe-56 0.186217 0.199795 -27 9 1 Fe-57 0.000000 0.000000 -28 9 1 Fe-58 0.000000 0.000000 -29 9 1 Ni-58 0.000000 0.000000 -30 9 1 Ni-60 0.000000 0.000000 -31 9 1 Ni-61 0.000000 0.000000 -32 9 1 Ni-62 0.000000 0.000000 -33 9 1 Ni-64 0.000000 0.000000 -34 9 1 Mn-55 0.000000 0.000000 -35 9 1 Si-28 0.000000 0.000000 -36 9 1 Si-29 0.000000 0.000000 -37 9 1 Si-30 0.000000 0.000000 -38 9 1 Cr-50 0.000000 0.000000 -39 9 1 Cr-52 0.000000 0.000000 -40 9 1 Cr-53 0.147443 0.139574 -41 9 1 Cr-54 0.000000 0.000000 -0 9 2 H-1 0.000000 0.000000 -1 9 2 O-16 0.000000 0.000000 -2 9 2 B-10 0.000000 0.000000 -3 9 2 B-11 0.000000 0.000000 -4 9 2 Fe-54 0.000000 0.000000 -5 9 2 Fe-56 0.000000 0.000000 -6 9 2 Fe-57 0.000000 0.000000 -7 9 2 Fe-58 0.000000 0.000000 -8 9 2 Ni-58 0.000000 0.000000 -9 9 2 Ni-60 0.000000 0.000000 -10 9 2 Ni-61 0.000000 0.000000 -11 9 2 Ni-62 0.000000 0.000000 -12 9 2 Ni-64 0.000000 0.000000 -13 9 2 Mn-55 0.000000 0.000000 -14 9 2 Si-28 0.000000 0.000000 -15 9 2 Si-29 0.000000 0.000000 -16 9 2 Si-30 0.000000 0.000000 -17 9 2 Cr-50 0.000000 0.000000 -18 9 2 Cr-52 0.000000 0.000000 -19 9 2 Cr-53 0.000000 0.000000 -20 9 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 9 1 H-1 0 0 -22 9 1 O-16 0 0 -23 9 1 B-10 0 0 -24 9 1 B-11 0 0 -25 9 1 Fe-54 0 0 -26 9 1 Fe-56 0 0 -27 9 1 Fe-57 0 0 -28 9 1 Fe-58 0 0 -29 9 1 Ni-58 0 0 -30 9 1 Ni-60 0 0 -31 9 1 Ni-61 0 0 -32 9 1 Ni-62 0 0 -33 9 1 Ni-64 0 0 -34 9 1 Mn-55 0 0 -35 9 1 Si-28 0 0 -36 9 1 Si-29 0 0 -37 9 1 Si-30 0 0 -38 9 1 Cr-50 0 0 -39 9 1 Cr-52 0 0 -40 9 1 Cr-53 0 0 -41 9 1 Cr-54 0 0 -0 9 2 H-1 0 0 -1 9 2 O-16 0 0 -2 9 2 B-10 0 0 -3 9 2 B-11 0 0 -4 9 2 Fe-54 0 0 -5 9 2 Fe-56 0 0 -6 9 2 Fe-57 0 0 -7 9 2 Fe-58 0 0 -8 9 2 Ni-58 0 0 -9 9 2 Ni-60 0 0 -10 9 2 Ni-61 0 0 -11 9 2 Ni-62 0 0 -12 9 2 Ni-64 0 0 -13 9 2 Mn-55 0 0 -14 9 2 Si-28 0 0 -15 9 2 Si-29 0 0 -16 9 2 Si-30 0 0 -17 9 2 Cr-50 0 0 -18 9 2 Cr-52 0 0 -19 9 2 Cr-53 0 0 -20 9 2 Cr-54 0 0 material group in group out nuclide moment mean -252 9 1 1 H-1 P0 0.400211 -253 9 1 1 H-1 P1 0.249556 -254 9 1 1 H-1 P2 0.082049 -255 9 1 1 H-1 P3 0.001559 -256 9 1 1 O-16 P0 0.080042 -257 9 1 1 O-16 P1 -0.036179 -258 9 1 1 O-16 P2 -0.015492 -259 9 1 1 O-16 P3 0.035790 -260 9 1 1 B-10 P0 0.000000 -261 9 1 1 B-10 P1 0.000000 -262 9 1 1 B-10 P2 0.000000 -263 9 1 1 B-10 P3 0.000000 -264 9 1 1 B-11 P0 0.000000 -265 9 1 1 B-11 P1 0.000000 -266 9 1 1 B-11 P2 0.000000 -267 9 1 1 B-11 P3 0.000000 -268 9 1 1 Fe-54 P0 0.000000 -269 9 1 1 Fe-54 P1 0.000000 -270 9 1 1 Fe-54 P2 0.000000 -271 9 1 1 Fe-54 P3 0.000000 -272 9 1 1 Fe-56 P0 0.160084 -273 9 1 1 Fe-56 P1 -0.026133 -274 9 1 1 Fe-56 P2 -0.073149 -275 9 1 1 Fe-56 P3 0.037054 -276 9 1 1 Fe-57 P0 0.000000 -277 9 1 1 Fe-57 P1 0.000000 -278 9 1 1 Fe-57 P2 0.000000 -279 9 1 1 Fe-57 P3 0.000000 -280 9 1 1 Fe-58 P0 0.000000 -281 9 1 1 Fe-58 P1 0.000000 -282 9 1 1 Fe-58 P2 0.000000 -283 9 1 1 Fe-58 P3 0.000000 -284 9 1 1 Ni-58 P0 0.000000 -285 9 1 1 Ni-58 P1 0.000000 -286 9 1 1 Ni-58 P2 0.000000 -287 9 1 1 Ni-58 P3 0.000000 -288 9 1 1 Ni-60 P0 0.000000 -289 9 1 1 Ni-60 P1 0.000000 -290 9 1 1 Ni-60 P2 0.000000 -291 9 1 1 Ni-60 P3 0.000000 -292 9 1 1 Ni-61 P0 0.000000 -293 9 1 1 Ni-61 P1 0.000000 -294 9 1 1 Ni-61 P2 0.000000 -295 9 1 1 Ni-61 P3 0.000000 -296 9 1 1 Ni-62 P0 0.000000 -297 9 1 1 Ni-62 P1 0.000000 -298 9 1 1 Ni-62 P2 0.000000 -299 9 1 1 Ni-62 P3 0.000000 -300 9 1 1 Ni-64 P0 0.000000 -301 9 1 1 Ni-64 P1 0.000000 -302 9 1 1 Ni-64 P2 0.000000 -303 9 1 1 Ni-64 P3 0.000000 -304 9 1 1 Mn-55 P0 0.000000 -305 9 1 1 Mn-55 P1 0.000000 -306 9 1 1 Mn-55 P2 0.000000 -307 9 1 1 Mn-55 P3 0.000000 -308 9 1 1 Si-28 P0 0.000000 -309 9 1 1 Si-28 P1 0.000000 -310 9 1 1 Si-28 P2 0.000000 -311 9 1 1 Si-28 P3 0.000000 -312 9 1 1 Si-29 P0 0.000000 -313 9 1 1 Si-29 P1 0.000000 -314 9 1 1 Si-29 P2 0.000000 -315 9 1 1 Si-29 P3 0.000000 -316 9 1 1 Si-30 P0 0.000000 -317 9 1 1 Si-30 P1 0.000000 -318 9 1 1 Si-30 P2 0.000000 -319 9 1 1 Si-30 P3 0.000000 -320 9 1 1 Cr-50 P0 0.000000 -321 9 1 1 Cr-50 P1 0.000000 -322 9 1 1 Cr-50 P2 0.000000 -323 9 1 1 Cr-50 P3 0.000000 -324 9 1 1 Cr-52 P0 0.000000 -325 9 1 1 Cr-52 P1 0.000000 -326 9 1 1 Cr-52 P2 0.000000 -327 9 1 1 Cr-52 P3 0.000000 -328 9 1 1 Cr-53 P0 0.080042 -329 9 1 1 Cr-53 P1 -0.067401 -330 9 1 1 Cr-53 P2 0.045113 -331 9 1 1 Cr-53 P3 -0.018380 -332 9 1 1 Cr-54 P0 0.000000 -333 9 1 1 Cr-54 P1 0.000000 -334 9 1 1 Cr-54 P2 0.000000 -335 9 1 1 Cr-54 P3 0.000000 -168 9 1 2 H-1 P0 0.000000 -169 9 1 2 H-1 P1 0.000000 -170 9 1 2 H-1 P2 0.000000 -171 9 1 2 H-1 P3 0.000000 -172 9 1 2 O-16 P0 0.000000 -173 9 1 2 O-16 P1 0.000000 -174 9 1 2 O-16 P2 0.000000 -175 9 1 2 O-16 P3 0.000000 -176 9 1 2 B-10 P0 0.000000 -177 9 1 2 B-10 P1 0.000000 -178 9 1 2 B-10 P2 0.000000 -179 9 1 2 B-10 P3 0.000000 -180 9 1 2 B-11 P0 0.000000 -181 9 1 2 B-11 P1 0.000000 -182 9 1 2 B-11 P2 0.000000 -183 9 1 2 B-11 P3 0.000000 -184 9 1 2 Fe-54 P0 0.000000 -185 9 1 2 Fe-54 P1 0.000000 -186 9 1 2 Fe-54 P2 0.000000 -187 9 1 2 Fe-54 P3 0.000000 -188 9 1 2 Fe-56 P0 0.000000 -189 9 1 2 Fe-56 P1 0.000000 -190 9 1 2 Fe-56 P2 0.000000 -191 9 1 2 Fe-56 P3 0.000000 -192 9 1 2 Fe-57 P0 0.000000 -193 9 1 2 Fe-57 P1 0.000000 -194 9 1 2 Fe-57 P2 0.000000 -195 9 1 2 Fe-57 P3 0.000000 -196 9 1 2 Fe-58 P0 0.000000 -197 9 1 2 Fe-58 P1 0.000000 -198 9 1 2 Fe-58 P2 0.000000 -199 9 1 2 Fe-58 P3 0.000000 -200 9 1 2 Ni-58 P0 0.000000 -201 9 1 2 Ni-58 P1 0.000000 -202 9 1 2 Ni-58 P2 0.000000 -203 9 1 2 Ni-58 P3 0.000000 -204 9 1 2 Ni-60 P0 0.000000 -205 9 1 2 Ni-60 P1 0.000000 -206 9 1 2 Ni-60 P2 0.000000 -207 9 1 2 Ni-60 P3 0.000000 -208 9 1 2 Ni-61 P0 0.000000 -209 9 1 2 Ni-61 P1 0.000000 -210 9 1 2 Ni-61 P2 0.000000 -211 9 1 2 Ni-61 P3 0.000000 -212 9 1 2 Ni-62 P0 0.000000 -213 9 1 2 Ni-62 P1 0.000000 -214 9 1 2 Ni-62 P2 0.000000 -215 9 1 2 Ni-62 P3 0.000000 -216 9 1 2 Ni-64 P0 0.000000 -217 9 1 2 Ni-64 P1 0.000000 -218 9 1 2 Ni-64 P2 0.000000 -219 9 1 2 Ni-64 P3 0.000000 -220 9 1 2 Mn-55 P0 0.000000 -221 9 1 2 Mn-55 P1 0.000000 -222 9 1 2 Mn-55 P2 0.000000 -223 9 1 2 Mn-55 P3 0.000000 -224 9 1 2 Si-28 P0 0.000000 -225 9 1 2 Si-28 P1 0.000000 -226 9 1 2 Si-28 P2 0.000000 -227 9 1 2 Si-28 P3 0.000000 -228 9 1 2 Si-29 P0 0.000000 -229 9 1 2 Si-29 P1 0.000000 -230 9 1 2 Si-29 P2 0.000000 -231 9 1 2 Si-29 P3 0.000000 -232 9 1 2 Si-30 P0 0.000000 -233 9 1 2 Si-30 P1 0.000000 -234 9 1 2 Si-30 P2 0.000000 -235 9 1 2 Si-30 P3 0.000000 -236 9 1 2 Cr-50 P0 0.000000 -237 9 1 2 Cr-50 P1 0.000000 -238 9 1 2 Cr-50 P2 0.000000 -239 9 1 2 Cr-50 P3 0.000000 -240 9 1 2 Cr-52 P0 0.000000 -241 9 1 2 Cr-52 P1 0.000000 -242 9 1 2 Cr-52 P2 0.000000 -243 9 1 2 Cr-52 P3 0.000000 -244 9 1 2 Cr-53 P0 0.000000 -245 9 1 2 Cr-53 P1 0.000000 -246 9 1 2 Cr-53 P2 0.000000 -247 9 1 2 Cr-53 P3 0.000000 -248 9 1 2 Cr-54 P0 0.000000 -249 9 1 2 Cr-54 P1 0.000000 -250 9 1 2 Cr-54 P2 0.000000 -251 9 1 2 Cr-54 P3 0.000000 -84 9 2 1 H-1 P0 0.000000 -85 9 2 1 H-1 P1 0.000000 -86 9 2 1 H-1 P2 0.000000 -87 9 2 1 H-1 P3 0.000000 -88 9 2 1 O-16 P0 0.000000 -89 9 2 1 O-16 P1 0.000000 -90 9 2 1 O-16 P2 0.000000 -91 9 2 1 O-16 P3 0.000000 -92 9 2 1 B-10 P0 0.000000 -93 9 2 1 B-10 P1 0.000000 -94 9 2 1 B-10 P2 0.000000 -95 9 2 1 B-10 P3 0.000000 -96 9 2 1 B-11 P0 0.000000 -97 9 2 1 B-11 P1 0.000000 -98 9 2 1 B-11 P2 0.000000 -99 9 2 1 B-11 P3 0.000000 -100 9 2 1 Fe-54 P0 0.000000 -101 9 2 1 Fe-54 P1 0.000000 -102 9 2 1 Fe-54 P2 0.000000 -103 9 2 1 Fe-54 P3 0.000000 -104 9 2 1 Fe-56 P0 0.000000 -105 9 2 1 Fe-56 P1 0.000000 -106 9 2 1 Fe-56 P2 0.000000 -107 9 2 1 Fe-56 P3 0.000000 -108 9 2 1 Fe-57 P0 0.000000 -109 9 2 1 Fe-57 P1 0.000000 -110 9 2 1 Fe-57 P2 0.000000 -111 9 2 1 Fe-57 P3 0.000000 -112 9 2 1 Fe-58 P0 0.000000 -113 9 2 1 Fe-58 P1 0.000000 -114 9 2 1 Fe-58 P2 0.000000 -115 9 2 1 Fe-58 P3 0.000000 -116 9 2 1 Ni-58 P0 0.000000 -117 9 2 1 Ni-58 P1 0.000000 -118 9 2 1 Ni-58 P2 0.000000 -119 9 2 1 Ni-58 P3 0.000000 -120 9 2 1 Ni-60 P0 0.000000 -121 9 2 1 Ni-60 P1 0.000000 -122 9 2 1 Ni-60 P2 0.000000 -123 9 2 1 Ni-60 P3 0.000000 -124 9 2 1 Ni-61 P0 0.000000 -125 9 2 1 Ni-61 P1 0.000000 -126 9 2 1 Ni-61 P2 0.000000 -127 9 2 1 Ni-61 P3 0.000000 -128 9 2 1 Ni-62 P0 0.000000 -129 9 2 1 Ni-62 P1 0.000000 -130 9 2 1 Ni-62 P2 0.000000 -131 9 2 1 Ni-62 P3 0.000000 -132 9 2 1 Ni-64 P0 0.000000 -133 9 2 1 Ni-64 P1 0.000000 -134 9 2 1 Ni-64 P2 0.000000 -135 9 2 1 Ni-64 P3 0.000000 -136 9 2 1 Mn-55 P0 0.000000 -137 9 2 1 Mn-55 P1 0.000000 -138 9 2 1 Mn-55 P2 0.000000 -139 9 2 1 Mn-55 P3 0.000000 -140 9 2 1 Si-28 P0 0.000000 -141 9 2 1 Si-28 P1 0.000000 -142 9 2 1 Si-28 P2 0.000000 -143 9 2 1 Si-28 P3 0.000000 -144 9 2 1 Si-29 P0 0.000000 -145 9 2 1 Si-29 P1 0.000000 -146 9 2 1 Si-29 P2 0.000000 -147 9 2 1 Si-29 P3 0.000000 -148 9 2 1 Si-30 P0 0.000000 -149 9 2 1 Si-30 P1 0.000000 -150 9 2 1 Si-30 P2 0.000000 -151 9 2 1 Si-30 P3 0.000000 -152 9 2 1 Cr-50 P0 0.000000 -153 9 2 1 Cr-50 P1 0.000000 -154 9 2 1 Cr-50 P2 0.000000 -155 9 2 1 Cr-50 P3 0.000000 -156 9 2 1 Cr-52 P0 0.000000 -157 9 2 1 Cr-52 P1 0.000000 -158 9 2 1 Cr-52 P2 0.000000 -159 9 2 1 Cr-52 P3 0.000000 -160 9 2 1 Cr-53 P0 0.000000 -161 9 2 1 Cr-53 P1 0.000000 -162 9 2 1 Cr-53 P2 0.000000 -163 9 2 1 Cr-53 P3 0.000000 -164 9 2 1 Cr-54 P0 0.000000 -165 9 2 1 Cr-54 P1 0.000000 -166 9 2 1 Cr-54 P2 0.000000 -167 9 2 1 Cr-54 P3 0.000000 -0 9 2 2 H-1 P0 0.000000 -1 9 2 2 H-1 P1 0.000000 -2 9 2 2 H-1 P2 0.000000 -3 9 2 2 H-1 P3 0.000000 -4 9 2 2 O-16 P0 0.000000 -5 9 2 2 O-16 P1 0.000000 -6 9 2 2 O-16 P2 0.000000 -7 9 2 2 O-16 P3 0.000000 -8 9 2 2 B-10 P0 0.000000 -9 9 2 2 B-10 P1 0.000000 -10 9 2 2 B-10 P2 0.000000 -11 9 2 2 B-10 P3 0.000000 -12 9 2 2 B-11 P0 0.000000 -13 9 2 2 B-11 P1 0.000000 -14 9 2 2 B-11 P2 0.000000 -15 9 2 2 B-11 P3 0.000000 -16 9 2 2 Fe-54 P0 0.000000 -17 9 2 2 Fe-54 P1 0.000000 -18 9 2 2 Fe-54 P2 0.000000 -19 9 2 2 Fe-54 P3 0.000000 -20 9 2 2 Fe-56 P0 0.000000 -21 9 2 2 Fe-56 P1 0.000000 -22 9 2 2 Fe-56 P2 0.000000 -23 9 2 2 Fe-56 P3 0.000000 -24 9 2 2 Fe-57 P0 0.000000 -25 9 2 2 Fe-57 P1 0.000000 -26 9 2 2 Fe-57 P2 0.000000 -27 9 2 2 Fe-57 P3 0.000000 -28 9 2 2 Fe-58 P0 0.000000 -29 9 2 2 Fe-58 P1 0.000000 -30 9 2 2 Fe-58 P2 0.000000 -31 9 2 2 Fe-58 P3 0.000000 -32 9 2 2 Ni-58 P0 0.000000 -33 9 2 2 Ni-58 P1 0.000000 -34 9 2 2 Ni-58 P2 0.000000 -35 9 2 2 Ni-58 P3 0.000000 -36 9 2 2 Ni-60 P0 0.000000 -37 9 2 2 Ni-60 P1 0.000000 -38 9 2 2 Ni-60 P2 0.000000 -39 9 2 2 Ni-60 P3 0.000000 -40 9 2 2 Ni-61 P0 0.000000 -41 9 2 2 Ni-61 P1 0.000000 -42 9 2 2 Ni-61 P2 0.000000 -43 9 2 2 Ni-61 P3 0.000000 -44 9 2 2 Ni-62 P0 0.000000 -45 9 2 2 Ni-62 P1 0.000000 -46 9 2 2 Ni-62 P2 0.000000 -47 9 2 2 Ni-62 P3 0.000000 -48 9 2 2 Ni-64 P0 0.000000 -49 9 2 2 Ni-64 P1 0.000000 -50 9 2 2 Ni-64 P2 0.000000 -51 9 2 2 Ni-64 P3 0.000000 -52 9 2 2 Mn-55 P0 0.000000 -53 9 2 2 Mn-55 P1 0.000000 -54 9 2 2 Mn-55 P2 0.000000 -55 9 2 2 Mn-55 P3 0.000000 -56 9 2 2 Si-28 P0 0.000000 -57 9 2 2 Si-28 P1 0.000000 -58 9 2 2 Si-28 P2 0.000000 -59 9 2 2 Si-28 P3 0.000000 -60 9 2 2 Si-29 P0 0.000000 -61 9 2 2 Si-29 P1 0.000000 -62 9 2 2 Si-29 P2 0.000000 -63 9 2 2 Si-29 P3 0.000000 -64 9 2 2 Si-30 P0 0.000000 -65 9 2 2 Si-30 P1 0.000000 -66 9 2 2 Si-30 P2 0.000000 -67 9 2 2 Si-30 P3 0.000000 -68 9 2 2 Cr-50 P0 0.000000 -69 9 2 2 Cr-50 P1 0.000000 -70 9 2 2 Cr-50 P2 0.000000 -71 9 2 2 Cr-50 P3 0.000000 -72 9 2 2 Cr-52 P0 0.000000 -73 9 2 2 Cr-52 P1 0.000000 -74 9 2 2 Cr-52 P2 0.000000 -75 9 2 2 Cr-52 P3 0.000000 -76 9 2 2 Cr-53 P0 0.000000 -77 9 2 2 Cr-53 P1 0.000000 -78 9 2 2 Cr-53 P2 0.000000 -79 9 2 2 Cr-53 P3 0.000000 -80 9 2 2 Cr-54 P0 0.000000 -81 9 2 2 Cr-54 P1 0.000000 -82 9 2 2 Cr-54 P2 0.000000 -83 9 2 2 Cr-54 P3 0.000000 material group out nuclide mean std. dev. -21 9 1 H-1 0 0 -22 9 1 O-16 0 0 -23 9 1 B-10 0 0 -24 9 1 B-11 0 0 -25 9 1 Fe-54 0 0 -26 9 1 Fe-56 0 0 -27 9 1 Fe-57 0 0 -28 9 1 Fe-58 0 0 -29 9 1 Ni-58 0 0 -30 9 1 Ni-60 0 0 -31 9 1 Ni-61 0 0 -32 9 1 Ni-62 0 0 -33 9 1 Ni-64 0 0 -34 9 1 Mn-55 0 0 -35 9 1 Si-28 0 0 -36 9 1 Si-29 0 0 -37 9 1 Si-30 0 0 -38 9 1 Cr-50 0 0 -39 9 1 Cr-52 0 0 -40 9 1 Cr-53 0 0 -41 9 1 Cr-54 0 0 -0 9 2 H-1 0 0 -1 9 2 O-16 0 0 -2 9 2 B-10 0 0 -3 9 2 B-11 0 0 -4 9 2 Fe-54 0 0 -5 9 2 Fe-56 0 0 -6 9 2 Fe-57 0 0 -7 9 2 Fe-58 0 0 -8 9 2 Ni-58 0 0 -9 9 2 Ni-60 0 0 -10 9 2 Ni-61 0 0 -11 9 2 Ni-62 0 0 -12 9 2 Ni-64 0 0 -13 9 2 Mn-55 0 0 -14 9 2 Si-28 0 0 -15 9 2 Si-29 0 0 -16 9 2 Si-30 0 0 -17 9 2 Cr-50 0 0 -18 9 2 Cr-52 0 0 -19 9 2 Cr-53 0 0 -20 9 2 Cr-54 0 0 material group in nuclide mean std. dev. -21 10 1 H-1 0.123944 0.541390 -22 10 1 O-16 0.000000 0.000000 -23 10 1 B-10 0.000000 0.000000 -24 10 1 B-11 0.000000 0.000000 -25 10 1 Fe-54 0.000000 0.000000 -26 10 1 Fe-56 0.000000 0.000000 -27 10 1 Fe-57 0.000000 0.000000 -28 10 1 Fe-58 0.000000 0.000000 -29 10 1 Ni-58 0.000000 0.000000 -30 10 1 Ni-60 0.000000 0.000000 -31 10 1 Ni-61 0.000000 0.000000 -32 10 1 Ni-62 0.000000 0.000000 -33 10 1 Ni-64 0.000000 0.000000 -34 10 1 Mn-55 0.000000 0.000000 -35 10 1 Si-28 0.000000 0.000000 -36 10 1 Si-29 0.000000 0.000000 -37 10 1 Si-30 0.000000 0.000000 -38 10 1 Cr-50 0.111571 0.138458 -39 10 1 Cr-52 0.000000 0.000000 -40 10 1 Cr-53 0.000000 0.000000 -41 10 1 Cr-54 0.000000 0.000000 -0 10 2 H-1 0.000000 0.000000 -1 10 2 O-16 0.000000 0.000000 -2 10 2 B-10 0.000000 0.000000 -3 10 2 B-11 0.000000 0.000000 -4 10 2 Fe-54 0.000000 0.000000 -5 10 2 Fe-56 0.000000 0.000000 -6 10 2 Fe-57 0.000000 0.000000 -7 10 2 Fe-58 0.000000 0.000000 -8 10 2 Ni-58 0.000000 0.000000 -9 10 2 Ni-60 0.000000 0.000000 -10 10 2 Ni-61 0.000000 0.000000 -11 10 2 Ni-62 0.000000 0.000000 -12 10 2 Ni-64 0.000000 0.000000 -13 10 2 Mn-55 0.000000 0.000000 -14 10 2 Si-28 0.000000 0.000000 -15 10 2 Si-29 0.000000 0.000000 -16 10 2 Si-30 0.000000 0.000000 -17 10 2 Cr-50 0.000000 0.000000 -18 10 2 Cr-52 0.000000 0.000000 -19 10 2 Cr-53 0.000000 0.000000 -20 10 2 Cr-54 0.000000 0.000000 material group in nuclide mean std. dev. -21 10 1 H-1 0 0 -22 10 1 O-16 0 0 -23 10 1 B-10 0 0 -24 10 1 B-11 0 0 -25 10 1 Fe-54 0 0 -26 10 1 Fe-56 0 0 -27 10 1 Fe-57 0 0 -28 10 1 Fe-58 0 0 -29 10 1 Ni-58 0 0 -30 10 1 Ni-60 0 0 -31 10 1 Ni-61 0 0 -32 10 1 Ni-62 0 0 -33 10 1 Ni-64 0 0 -34 10 1 Mn-55 0 0 -35 10 1 Si-28 0 0 -36 10 1 Si-29 0 0 -37 10 1 Si-30 0 0 -38 10 1 Cr-50 0 0 -39 10 1 Cr-52 0 0 -40 10 1 Cr-53 0 0 -41 10 1 Cr-54 0 0 -0 10 2 H-1 0 0 -1 10 2 O-16 0 0 -2 10 2 B-10 0 0 -3 10 2 B-11 0 0 -4 10 2 Fe-54 0 0 -5 10 2 Fe-56 0 0 -6 10 2 Fe-57 0 0 -7 10 2 Fe-58 0 0 -8 10 2 Ni-58 0 0 -9 10 2 Ni-60 0 0 -10 10 2 Ni-61 0 0 -11 10 2 Ni-62 0 0 -12 10 2 Ni-64 0 0 -13 10 2 Mn-55 0 0 -14 10 2 Si-28 0 0 -15 10 2 Si-29 0 0 -16 10 2 Si-30 0 0 -17 10 2 Cr-50 0 0 -18 10 2 Cr-52 0 0 -19 10 2 Cr-53 0 0 -20 10 2 Cr-54 0 0 material group in group out nuclide moment mean -252 10 1 1 H-1 P0 0.429436 -253 10 1 1 H-1 P1 0.305492 -254 10 1 1 H-1 P2 0.144235 -255 10 1 1 H-1 P3 0.045491 -256 10 1 1 O-16 P0 0.000000 -257 10 1 1 O-16 P1 0.000000 -258 10 1 1 O-16 P2 0.000000 -259 10 1 1 O-16 P3 0.000000 -260 10 1 1 B-10 P0 0.000000 -261 10 1 1 B-10 P1 0.000000 -262 10 1 1 B-10 P2 0.000000 -263 10 1 1 B-10 P3 0.000000 -264 10 1 1 B-11 P0 0.000000 -265 10 1 1 B-11 P1 0.000000 -266 10 1 1 B-11 P2 0.000000 -267 10 1 1 B-11 P3 0.000000 -268 10 1 1 Fe-54 P0 0.000000 -269 10 1 1 Fe-54 P1 0.000000 -270 10 1 1 Fe-54 P2 0.000000 -271 10 1 1 Fe-54 P3 0.000000 -272 10 1 1 Fe-56 P0 0.000000 -273 10 1 1 Fe-56 P1 0.000000 -274 10 1 1 Fe-56 P2 0.000000 -275 10 1 1 Fe-56 P3 0.000000 -276 10 1 1 Fe-57 P0 0.000000 -277 10 1 1 Fe-57 P1 0.000000 -278 10 1 1 Fe-57 P2 0.000000 -279 10 1 1 Fe-57 P3 0.000000 -280 10 1 1 Fe-58 P0 0.000000 -281 10 1 1 Fe-58 P1 0.000000 -282 10 1 1 Fe-58 P2 0.000000 -283 10 1 1 Fe-58 P3 0.000000 -284 10 1 1 Ni-58 P0 0.000000 -285 10 1 1 Ni-58 P1 0.000000 -286 10 1 1 Ni-58 P2 0.000000 -287 10 1 1 Ni-58 P3 0.000000 -288 10 1 1 Ni-60 P0 0.000000 -289 10 1 1 Ni-60 P1 0.000000 -290 10 1 1 Ni-60 P2 0.000000 -291 10 1 1 Ni-60 P3 0.000000 -292 10 1 1 Ni-61 P0 0.000000 -293 10 1 1 Ni-61 P1 0.000000 -294 10 1 1 Ni-61 P2 0.000000 -295 10 1 1 Ni-61 P3 0.000000 -296 10 1 1 Ni-62 P0 0.000000 -297 10 1 1 Ni-62 P1 0.000000 -298 10 1 1 Ni-62 P2 0.000000 -299 10 1 1 Ni-62 P3 0.000000 -300 10 1 1 Ni-64 P0 0.000000 -301 10 1 1 Ni-64 P1 0.000000 -302 10 1 1 Ni-64 P2 0.000000 -303 10 1 1 Ni-64 P3 0.000000 -304 10 1 1 Mn-55 P0 0.000000 -305 10 1 1 Mn-55 P1 0.000000 -306 10 1 1 Mn-55 P2 0.000000 -307 10 1 1 Mn-55 P3 0.000000 -308 10 1 1 Si-28 P0 0.000000 -309 10 1 1 Si-28 P1 0.000000 -310 10 1 1 Si-28 P2 0.000000 -311 10 1 1 Si-28 P3 0.000000 -312 10 1 1 Si-29 P0 0.000000 -313 10 1 1 Si-29 P1 0.000000 -314 10 1 1 Si-29 P2 0.000000 -315 10 1 1 Si-29 P3 0.000000 -316 10 1 1 Si-30 P0 0.000000 -317 10 1 1 Si-30 P1 0.000000 -318 10 1 1 Si-30 P2 0.000000 -319 10 1 1 Si-30 P3 0.000000 -320 10 1 1 Cr-50 P0 0.071573 -321 10 1 1 Cr-50 P1 -0.039998 -322 10 1 1 Cr-50 P2 -0.002257 -323 10 1 1 Cr-50 P3 0.028768 -324 10 1 1 Cr-52 P0 0.000000 -325 10 1 1 Cr-52 P1 0.000000 -326 10 1 1 Cr-52 P2 0.000000 -327 10 1 1 Cr-52 P3 0.000000 -328 10 1 1 Cr-53 P0 0.000000 -329 10 1 1 Cr-53 P1 0.000000 -330 10 1 1 Cr-53 P2 0.000000 -331 10 1 1 Cr-53 P3 0.000000 -332 10 1 1 Cr-54 P0 0.000000 -333 10 1 1 Cr-54 P1 0.000000 -334 10 1 1 Cr-54 P2 0.000000 -335 10 1 1 Cr-54 P3 0.000000 -168 10 1 2 H-1 P0 0.000000 -169 10 1 2 H-1 P1 0.000000 -170 10 1 2 H-1 P2 0.000000 -171 10 1 2 H-1 P3 0.000000 -172 10 1 2 O-16 P0 0.000000 -173 10 1 2 O-16 P1 0.000000 -174 10 1 2 O-16 P2 0.000000 -175 10 1 2 O-16 P3 0.000000 -176 10 1 2 B-10 P0 0.000000 -177 10 1 2 B-10 P1 0.000000 -178 10 1 2 B-10 P2 0.000000 -179 10 1 2 B-10 P3 0.000000 -180 10 1 2 B-11 P0 0.000000 -181 10 1 2 B-11 P1 0.000000 -182 10 1 2 B-11 P2 0.000000 -183 10 1 2 B-11 P3 0.000000 -184 10 1 2 Fe-54 P0 0.000000 -185 10 1 2 Fe-54 P1 0.000000 -186 10 1 2 Fe-54 P2 0.000000 -187 10 1 2 Fe-54 P3 0.000000 -188 10 1 2 Fe-56 P0 0.000000 -189 10 1 2 Fe-56 P1 0.000000 -190 10 1 2 Fe-56 P2 0.000000 -191 10 1 2 Fe-56 P3 0.000000 -192 10 1 2 Fe-57 P0 0.000000 -193 10 1 2 Fe-57 P1 0.000000 -194 10 1 2 Fe-57 P2 0.000000 -195 10 1 2 Fe-57 P3 0.000000 -196 10 1 2 Fe-58 P0 0.000000 -197 10 1 2 Fe-58 P1 0.000000 -198 10 1 2 Fe-58 P2 0.000000 -199 10 1 2 Fe-58 P3 0.000000 -200 10 1 2 Ni-58 P0 0.000000 -201 10 1 2 Ni-58 P1 0.000000 -202 10 1 2 Ni-58 P2 0.000000 -203 10 1 2 Ni-58 P3 0.000000 -204 10 1 2 Ni-60 P0 0.000000 -205 10 1 2 Ni-60 P1 0.000000 -206 10 1 2 Ni-60 P2 0.000000 -207 10 1 2 Ni-60 P3 0.000000 -208 10 1 2 Ni-61 P0 0.000000 -209 10 1 2 Ni-61 P1 0.000000 -210 10 1 2 Ni-61 P2 0.000000 -211 10 1 2 Ni-61 P3 0.000000 -212 10 1 2 Ni-62 P0 0.000000 -213 10 1 2 Ni-62 P1 0.000000 -214 10 1 2 Ni-62 P2 0.000000 -215 10 1 2 Ni-62 P3 0.000000 -216 10 1 2 Ni-64 P0 0.000000 -217 10 1 2 Ni-64 P1 0.000000 -218 10 1 2 Ni-64 P2 0.000000 -219 10 1 2 Ni-64 P3 0.000000 -220 10 1 2 Mn-55 P0 0.000000 -221 10 1 2 Mn-55 P1 0.000000 -222 10 1 2 Mn-55 P2 0.000000 -223 10 1 2 Mn-55 P3 0.000000 -224 10 1 2 Si-28 P0 0.000000 -225 10 1 2 Si-28 P1 0.000000 -226 10 1 2 Si-28 P2 0.000000 -227 10 1 2 Si-28 P3 0.000000 -228 10 1 2 Si-29 P0 0.000000 -229 10 1 2 Si-29 P1 0.000000 -230 10 1 2 Si-29 P2 0.000000 -231 10 1 2 Si-29 P3 0.000000 -232 10 1 2 Si-30 P0 0.000000 -233 10 1 2 Si-30 P1 0.000000 -234 10 1 2 Si-30 P2 0.000000 -235 10 1 2 Si-30 P3 0.000000 -236 10 1 2 Cr-50 P0 0.000000 -237 10 1 2 Cr-50 P1 0.000000 -238 10 1 2 Cr-50 P2 0.000000 -239 10 1 2 Cr-50 P3 0.000000 -240 10 1 2 Cr-52 P0 0.000000 -241 10 1 2 Cr-52 P1 0.000000 -242 10 1 2 Cr-52 P2 0.000000 -243 10 1 2 Cr-52 P3 0.000000 -244 10 1 2 Cr-53 P0 0.000000 -245 10 1 2 Cr-53 P1 0.000000 -246 10 1 2 Cr-53 P2 0.000000 -247 10 1 2 Cr-53 P3 0.000000 -248 10 1 2 Cr-54 P0 0.000000 -249 10 1 2 Cr-54 P1 0.000000 -250 10 1 2 Cr-54 P2 0.000000 -251 10 1 2 Cr-54 P3 0.000000 -84 10 2 1 H-1 P0 0.000000 -85 10 2 1 H-1 P1 0.000000 -86 10 2 1 H-1 P2 0.000000 -87 10 2 1 H-1 P3 0.000000 -88 10 2 1 O-16 P0 0.000000 -89 10 2 1 O-16 P1 0.000000 -90 10 2 1 O-16 P2 0.000000 -91 10 2 1 O-16 P3 0.000000 -92 10 2 1 B-10 P0 0.000000 -93 10 2 1 B-10 P1 0.000000 -94 10 2 1 B-10 P2 0.000000 -95 10 2 1 B-10 P3 0.000000 -96 10 2 1 B-11 P0 0.000000 -97 10 2 1 B-11 P1 0.000000 -98 10 2 1 B-11 P2 0.000000 -99 10 2 1 B-11 P3 0.000000 -100 10 2 1 Fe-54 P0 0.000000 -101 10 2 1 Fe-54 P1 0.000000 -102 10 2 1 Fe-54 P2 0.000000 -103 10 2 1 Fe-54 P3 0.000000 -104 10 2 1 Fe-56 P0 0.000000 -105 10 2 1 Fe-56 P1 0.000000 -106 10 2 1 Fe-56 P2 0.000000 -107 10 2 1 Fe-56 P3 0.000000 -108 10 2 1 Fe-57 P0 0.000000 -109 10 2 1 Fe-57 P1 0.000000 -110 10 2 1 Fe-57 P2 0.000000 -111 10 2 1 Fe-57 P3 0.000000 -112 10 2 1 Fe-58 P0 0.000000 -113 10 2 1 Fe-58 P1 0.000000 -114 10 2 1 Fe-58 P2 0.000000 -115 10 2 1 Fe-58 P3 0.000000 -116 10 2 1 Ni-58 P0 0.000000 -117 10 2 1 Ni-58 P1 0.000000 -118 10 2 1 Ni-58 P2 0.000000 -119 10 2 1 Ni-58 P3 0.000000 -120 10 2 1 Ni-60 P0 0.000000 -121 10 2 1 Ni-60 P1 0.000000 -122 10 2 1 Ni-60 P2 0.000000 -123 10 2 1 Ni-60 P3 0.000000 -124 10 2 1 Ni-61 P0 0.000000 -125 10 2 1 Ni-61 P1 0.000000 -126 10 2 1 Ni-61 P2 0.000000 -127 10 2 1 Ni-61 P3 0.000000 -128 10 2 1 Ni-62 P0 0.000000 -129 10 2 1 Ni-62 P1 0.000000 -130 10 2 1 Ni-62 P2 0.000000 -131 10 2 1 Ni-62 P3 0.000000 -132 10 2 1 Ni-64 P0 0.000000 -133 10 2 1 Ni-64 P1 0.000000 -134 10 2 1 Ni-64 P2 0.000000 -135 10 2 1 Ni-64 P3 0.000000 -136 10 2 1 Mn-55 P0 0.000000 -137 10 2 1 Mn-55 P1 0.000000 -138 10 2 1 Mn-55 P2 0.000000 -139 10 2 1 Mn-55 P3 0.000000 -140 10 2 1 Si-28 P0 0.000000 -141 10 2 1 Si-28 P1 0.000000 -142 10 2 1 Si-28 P2 0.000000 -143 10 2 1 Si-28 P3 0.000000 -144 10 2 1 Si-29 P0 0.000000 -145 10 2 1 Si-29 P1 0.000000 -146 10 2 1 Si-29 P2 0.000000 -147 10 2 1 Si-29 P3 0.000000 -148 10 2 1 Si-30 P0 0.000000 -149 10 2 1 Si-30 P1 0.000000 -150 10 2 1 Si-30 P2 0.000000 -151 10 2 1 Si-30 P3 0.000000 -152 10 2 1 Cr-50 P0 0.000000 -153 10 2 1 Cr-50 P1 0.000000 -154 10 2 1 Cr-50 P2 0.000000 -155 10 2 1 Cr-50 P3 0.000000 -156 10 2 1 Cr-52 P0 0.000000 -157 10 2 1 Cr-52 P1 0.000000 -158 10 2 1 Cr-52 P2 0.000000 -159 10 2 1 Cr-52 P3 0.000000 -160 10 2 1 Cr-53 P0 0.000000 -161 10 2 1 Cr-53 P1 0.000000 -162 10 2 1 Cr-53 P2 0.000000 -163 10 2 1 Cr-53 P3 0.000000 -164 10 2 1 Cr-54 P0 0.000000 -165 10 2 1 Cr-54 P1 0.000000 -166 10 2 1 Cr-54 P2 0.000000 -167 10 2 1 Cr-54 P3 0.000000 -0 10 2 2 H-1 P0 0.000000 -1 10 2 2 H-1 P1 0.000000 -2 10 2 2 H-1 P2 0.000000 -3 10 2 2 H-1 P3 0.000000 -4 10 2 2 O-16 P0 0.000000 -5 10 2 2 O-16 P1 0.000000 -6 10 2 2 O-16 P2 0.000000 -7 10 2 2 O-16 P3 0.000000 -8 10 2 2 B-10 P0 0.000000 -9 10 2 2 B-10 P1 0.000000 -10 10 2 2 B-10 P2 0.000000 -11 10 2 2 B-10 P3 0.000000 -12 10 2 2 B-11 P0 0.000000 -13 10 2 2 B-11 P1 0.000000 -14 10 2 2 B-11 P2 0.000000 -15 10 2 2 B-11 P3 0.000000 -16 10 2 2 Fe-54 P0 0.000000 -17 10 2 2 Fe-54 P1 0.000000 -18 10 2 2 Fe-54 P2 0.000000 -19 10 2 2 Fe-54 P3 0.000000 -20 10 2 2 Fe-56 P0 0.000000 -21 10 2 2 Fe-56 P1 0.000000 -22 10 2 2 Fe-56 P2 0.000000 -23 10 2 2 Fe-56 P3 0.000000 -24 10 2 2 Fe-57 P0 0.000000 -25 10 2 2 Fe-57 P1 0.000000 -26 10 2 2 Fe-57 P2 0.000000 -27 10 2 2 Fe-57 P3 0.000000 -28 10 2 2 Fe-58 P0 0.000000 -29 10 2 2 Fe-58 P1 0.000000 -30 10 2 2 Fe-58 P2 0.000000 -31 10 2 2 Fe-58 P3 0.000000 -32 10 2 2 Ni-58 P0 0.000000 -33 10 2 2 Ni-58 P1 0.000000 -34 10 2 2 Ni-58 P2 0.000000 -35 10 2 2 Ni-58 P3 0.000000 -36 10 2 2 Ni-60 P0 0.000000 -37 10 2 2 Ni-60 P1 0.000000 -38 10 2 2 Ni-60 P2 0.000000 -39 10 2 2 Ni-60 P3 0.000000 -40 10 2 2 Ni-61 P0 0.000000 -41 10 2 2 Ni-61 P1 0.000000 -42 10 2 2 Ni-61 P2 0.000000 -43 10 2 2 Ni-61 P3 0.000000 -44 10 2 2 Ni-62 P0 0.000000 -45 10 2 2 Ni-62 P1 0.000000 -46 10 2 2 Ni-62 P2 0.000000 -47 10 2 2 Ni-62 P3 0.000000 -48 10 2 2 Ni-64 P0 0.000000 -49 10 2 2 Ni-64 P1 0.000000 -50 10 2 2 Ni-64 P2 0.000000 -51 10 2 2 Ni-64 P3 0.000000 -52 10 2 2 Mn-55 P0 0.000000 -53 10 2 2 Mn-55 P1 0.000000 -54 10 2 2 Mn-55 P2 0.000000 -55 10 2 2 Mn-55 P3 0.000000 -56 10 2 2 Si-28 P0 0.000000 -57 10 2 2 Si-28 P1 0.000000 -58 10 2 2 Si-28 P2 0.000000 -59 10 2 2 Si-28 P3 0.000000 -60 10 2 2 Si-29 P0 0.000000 -61 10 2 2 Si-29 P1 0.000000 -62 10 2 2 Si-29 P2 0.000000 -63 10 2 2 Si-29 P3 0.000000 -64 10 2 2 Si-30 P0 0.000000 -65 10 2 2 Si-30 P1 0.000000 -66 10 2 2 Si-30 P2 0.000000 -67 10 2 2 Si-30 P3 0.000000 -68 10 2 2 Cr-50 P0 0.000000 -69 10 2 2 Cr-50 P1 0.000000 -70 10 2 2 Cr-50 P2 0.000000 -71 10 2 2 Cr-50 P3 0.000000 -72 10 2 2 Cr-52 P0 0.000000 -73 10 2 2 Cr-52 P1 0.000000 -74 10 2 2 Cr-52 P2 0.000000 -75 10 2 2 Cr-52 P3 0.000000 -76 10 2 2 Cr-53 P0 0.000000 -77 10 2 2 Cr-53 P1 0.000000 -78 10 2 2 Cr-53 P2 0.000000 -79 10 2 2 Cr-53 P3 0.000000 -80 10 2 2 Cr-54 P0 0.000000 -81 10 2 2 Cr-54 P1 0.000000 -82 10 2 2 Cr-54 P2 0.000000 -83 10 2 2 Cr-54 P3 0.000000 material group out nuclide mean std. dev. -21 10 1 H-1 0 0 -22 10 1 O-16 0 0 -23 10 1 B-10 0 0 -24 10 1 B-11 0 0 -25 10 1 Fe-54 0 0 -26 10 1 Fe-56 0 0 -27 10 1 Fe-57 0 0 -28 10 1 Fe-58 0 0 -29 10 1 Ni-58 0 0 -30 10 1 Ni-60 0 0 -31 10 1 Ni-61 0 0 -32 10 1 Ni-62 0 0 -33 10 1 Ni-64 0 0 -34 10 1 Mn-55 0 0 -35 10 1 Si-28 0 0 -36 10 1 Si-29 0 0 -37 10 1 Si-30 0 0 -38 10 1 Cr-50 0 0 -39 10 1 Cr-52 0 0 -40 10 1 Cr-53 0 0 -41 10 1 Cr-54 0 0 -0 10 2 H-1 0 0 -1 10 2 O-16 0 0 -2 10 2 B-10 0 0 -3 10 2 B-11 0 0 -4 10 2 Fe-54 0 0 -5 10 2 Fe-56 0 0 -6 10 2 Fe-57 0 0 -7 10 2 Fe-58 0 0 -8 10 2 Ni-58 0 0 -9 10 2 Ni-60 0 0 -10 10 2 Ni-61 0 0 -11 10 2 Ni-62 0 0 -12 10 2 Ni-64 0 0 -13 10 2 Mn-55 0 0 -14 10 2 Si-28 0 0 -15 10 2 Si-29 0 0 -16 10 2 Si-30 0 0 -17 10 2 Cr-50 0 0 -18 10 2 Cr-52 0 0 -19 10 2 Cr-53 0 0 -20 10 2 Cr-54 0 0 material group in nuclide mean std. dev. -9 11 1 H-1 0.131470 0.476035 -10 11 1 O-16 0.028684 0.043000 -11 11 1 B-10 0.000000 0.000000 -12 11 1 B-11 0.000000 0.000000 -13 11 1 Zr-90 0.021980 0.039963 -14 11 1 Zr-91 0.000000 0.000000 -15 11 1 Zr-92 0.000000 0.000000 -16 11 1 Zr-94 0.004191 0.087344 -17 11 1 Zr-96 0.000000 0.000000 -0 11 2 H-1 0.687243 1.239217 -1 11 2 O-16 0.000000 0.000000 -2 11 2 B-10 0.042902 0.060672 -3 11 2 B-11 0.000000 0.000000 -4 11 2 Zr-90 0.039576 0.105193 -5 11 2 Zr-91 0.000000 0.000000 -6 11 2 Zr-92 0.084226 0.103161 -7 11 2 Zr-94 0.092039 0.125985 -8 11 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 11 1 H-1 0 0 -10 11 1 O-16 0 0 -11 11 1 B-10 0 0 -12 11 1 B-11 0 0 -13 11 1 Zr-90 0 0 -14 11 1 Zr-91 0 0 -15 11 1 Zr-92 0 0 -16 11 1 Zr-94 0 0 -17 11 1 Zr-96 0 0 -0 11 2 H-1 0 0 -1 11 2 O-16 0 0 -2 11 2 B-10 0 0 -3 11 2 B-11 0 0 -4 11 2 Zr-90 0 0 -5 11 2 Zr-91 0 0 -6 11 2 Zr-92 0 0 -7 11 2 Zr-94 0 0 -8 11 2 Zr-96 0 0 material group in group out nuclide moment mean -108 11 1 1 H-1 P0 0.350627 -109 11 1 1 H-1 P1 0.251032 -110 11 1 1 H-1 P2 0.118434 -111 11 1 1 H-1 P3 0.029897 -112 11 1 1 O-16 P0 0.031875 -113 11 1 1 O-16 P1 0.003191 -114 11 1 1 O-16 P2 -0.015458 -115 11 1 1 O-16 P3 -0.004707 -116 11 1 1 B-10 P0 0.000000 -117 11 1 1 B-10 P1 0.000000 -118 11 1 1 B-10 P2 0.000000 -119 11 1 1 B-10 P3 0.000000 -120 11 1 1 B-11 P0 0.000000 -121 11 1 1 B-11 P1 0.000000 -122 11 1 1 B-11 P2 0.000000 -123 11 1 1 B-11 P3 0.000000 -124 11 1 1 Zr-90 P0 0.031875 -125 11 1 1 Zr-90 P1 0.009895 -126 11 1 1 Zr-90 P2 -0.011330 -127 11 1 1 Zr-90 P3 -0.012459 -128 11 1 1 Zr-91 P0 0.000000 -129 11 1 1 Zr-91 P1 0.000000 -130 11 1 1 Zr-91 P2 0.000000 -131 11 1 1 Zr-91 P3 0.000000 -132 11 1 1 Zr-92 P0 0.000000 -133 11 1 1 Zr-92 P1 0.000000 -134 11 1 1 Zr-92 P2 0.000000 -135 11 1 1 Zr-92 P3 0.000000 -136 11 1 1 Zr-94 P0 0.063750 -137 11 1 1 Zr-94 P1 0.059559 -138 11 1 1 Zr-94 P2 0.051729 -139 11 1 1 Zr-94 P3 0.041273 -140 11 1 1 Zr-96 P0 0.000000 -141 11 1 1 Zr-96 P1 0.000000 -142 11 1 1 Zr-96 P2 0.000000 -143 11 1 1 Zr-96 P3 0.000000 -72 11 1 2 H-1 P0 0.031875 -73 11 1 2 H-1 P1 0.008585 -74 11 1 2 H-1 P2 -0.012470 -75 11 1 2 H-1 P3 -0.011320 -76 11 1 2 O-16 P0 0.000000 -77 11 1 2 O-16 P1 0.000000 -78 11 1 2 O-16 P2 0.000000 -79 11 1 2 O-16 P3 0.000000 -80 11 1 2 B-10 P0 0.000000 -81 11 1 2 B-10 P1 0.000000 -82 11 1 2 B-10 P2 0.000000 -83 11 1 2 B-10 P3 0.000000 -84 11 1 2 B-11 P0 0.000000 -85 11 1 2 B-11 P1 0.000000 -86 11 1 2 B-11 P2 0.000000 -87 11 1 2 B-11 P3 0.000000 -88 11 1 2 Zr-90 P0 0.000000 -89 11 1 2 Zr-90 P1 0.000000 -90 11 1 2 Zr-90 P2 0.000000 -91 11 1 2 Zr-90 P3 0.000000 -92 11 1 2 Zr-91 P0 0.000000 -93 11 1 2 Zr-91 P1 0.000000 -94 11 1 2 Zr-91 P2 0.000000 -95 11 1 2 Zr-91 P3 0.000000 -96 11 1 2 Zr-92 P0 0.000000 -97 11 1 2 Zr-92 P1 0.000000 -98 11 1 2 Zr-92 P2 0.000000 -99 11 1 2 Zr-92 P3 0.000000 -100 11 1 2 Zr-94 P0 0.000000 -101 11 1 2 Zr-94 P1 0.000000 -102 11 1 2 Zr-94 P2 0.000000 -103 11 1 2 Zr-94 P3 0.000000 -104 11 1 2 Zr-96 P0 0.000000 -105 11 1 2 Zr-96 P1 0.000000 -106 11 1 2 Zr-96 P2 0.000000 -107 11 1 2 Zr-96 P3 0.000000 -36 11 2 1 H-1 P0 0.000000 -37 11 2 1 H-1 P1 0.000000 -38 11 2 1 H-1 P2 0.000000 -39 11 2 1 H-1 P3 0.000000 -40 11 2 1 O-16 P0 0.000000 -41 11 2 1 O-16 P1 0.000000 -42 11 2 1 O-16 P2 0.000000 -43 11 2 1 O-16 P3 0.000000 -44 11 2 1 B-10 P0 0.000000 -45 11 2 1 B-10 P1 0.000000 -46 11 2 1 B-10 P2 0.000000 -47 11 2 1 B-10 P3 0.000000 -48 11 2 1 B-11 P0 0.000000 -49 11 2 1 B-11 P1 0.000000 -50 11 2 1 B-11 P2 0.000000 -51 11 2 1 B-11 P3 0.000000 -52 11 2 1 Zr-90 P0 0.000000 -53 11 2 1 Zr-90 P1 0.000000 -54 11 2 1 Zr-90 P2 0.000000 -55 11 2 1 Zr-90 P3 0.000000 -56 11 2 1 Zr-91 P0 0.000000 -57 11 2 1 Zr-91 P1 0.000000 -58 11 2 1 Zr-91 P2 0.000000 -59 11 2 1 Zr-91 P3 0.000000 -60 11 2 1 Zr-92 P0 0.000000 -61 11 2 1 Zr-92 P1 0.000000 -62 11 2 1 Zr-92 P2 0.000000 -63 11 2 1 Zr-92 P3 0.000000 -64 11 2 1 Zr-94 P0 0.000000 -65 11 2 1 Zr-94 P1 0.000000 -66 11 2 1 Zr-94 P2 0.000000 -67 11 2 1 Zr-94 P3 0.000000 -68 11 2 1 Zr-96 P0 0.000000 -69 11 2 1 Zr-96 P1 0.000000 -70 11 2 1 Zr-96 P2 0.000000 -71 11 2 1 Zr-96 P3 0.000000 -0 11 2 2 H-1 P0 0.986741 -1 11 2 2 H-1 P1 0.287943 -2 11 2 2 H-1 P2 0.156802 -3 11 2 2 H-1 P3 0.037565 -4 11 2 2 O-16 P0 0.000000 -5 11 2 2 O-16 P1 0.000000 -6 11 2 2 O-16 P2 0.000000 -7 11 2 2 O-16 P3 0.000000 -8 11 2 2 B-10 P0 0.000000 -9 11 2 2 B-10 P1 0.000000 -10 11 2 2 B-10 P2 0.000000 -11 11 2 2 B-10 P3 0.000000 -12 11 2 2 B-11 P0 0.000000 -13 11 2 2 B-11 P1 0.000000 -14 11 2 2 B-11 P2 0.000000 -15 11 2 2 B-11 P3 0.000000 -16 11 2 2 Zr-90 P0 0.085804 -17 11 2 2 Zr-90 P1 0.046227 -18 11 2 2 Zr-90 P2 -0.005520 -19 11 2 2 Zr-90 P3 -0.035731 -20 11 2 2 Zr-91 P0 0.000000 -21 11 2 2 Zr-91 P1 0.000000 -22 11 2 2 Zr-91 P2 0.000000 -23 11 2 2 Zr-91 P3 0.000000 -24 11 2 2 Zr-92 P0 0.042902 -25 11 2 2 Zr-92 P1 -0.041324 -26 11 2 2 Zr-92 P2 0.038256 -27 11 2 2 Zr-92 P3 -0.033866 -28 11 2 2 Zr-94 P0 0.085804 -29 11 2 2 Zr-94 P1 -0.006235 -30 11 2 2 Zr-94 P2 0.028653 -31 11 2 2 Zr-94 P3 -0.016482 -32 11 2 2 Zr-96 P0 0.000000 -33 11 2 2 Zr-96 P1 0.000000 -34 11 2 2 Zr-96 P2 0.000000 -35 11 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. -9 11 1 H-1 0 0 -10 11 1 O-16 0 0 -11 11 1 B-10 0 0 -12 11 1 B-11 0 0 -13 11 1 Zr-90 0 0 -14 11 1 Zr-91 0 0 -15 11 1 Zr-92 0 0 -16 11 1 Zr-94 0 0 -17 11 1 Zr-96 0 0 -0 11 2 H-1 0 0 -1 11 2 O-16 0 0 -2 11 2 B-10 0 0 -3 11 2 B-11 0 0 -4 11 2 Zr-90 0 0 -5 11 2 Zr-91 0 0 -6 11 2 Zr-92 0 0 -7 11 2 Zr-94 0 0 -8 11 2 Zr-96 0 0 material group in nuclide mean std. dev. -9 12 1 H-1 0.098944 0.178543 -10 12 1 O-16 0.013270 0.020403 -11 12 1 B-10 0.000000 0.000000 -12 12 1 B-11 0.000000 0.000000 -13 12 1 Zr-90 0.089997 0.075538 -14 12 1 Zr-91 0.000000 0.000000 -15 12 1 Zr-92 0.003501 0.017031 -16 12 1 Zr-94 0.004850 0.016327 -17 12 1 Zr-96 0.002730 0.017476 -0 12 2 H-1 1.261686 1.980336 -1 12 2 O-16 0.079159 0.104796 -2 12 2 B-10 0.016928 0.023940 -3 12 2 B-11 0.000000 0.000000 -4 12 2 Zr-90 0.000000 0.000000 -5 12 2 Zr-91 0.033201 0.040665 -6 12 2 Zr-92 0.000000 0.000000 -7 12 2 Zr-94 0.000000 0.000000 -8 12 2 Zr-96 0.000000 0.000000 material group in nuclide mean std. dev. -9 12 1 H-1 0 0 -10 12 1 O-16 0 0 -11 12 1 B-10 0 0 -12 12 1 B-11 0 0 -13 12 1 Zr-90 0 0 -14 12 1 Zr-91 0 0 -15 12 1 Zr-92 0 0 -16 12 1 Zr-94 0 0 -17 12 1 Zr-96 0 0 -0 12 2 H-1 0 0 -1 12 2 O-16 0 0 -2 12 2 B-10 0 0 -3 12 2 B-11 0 0 -4 12 2 Zr-90 0 0 -5 12 2 Zr-91 0 0 -6 12 2 Zr-92 0 0 -7 12 2 Zr-94 0 0 -8 12 2 Zr-96 0 0 material group in group out nuclide moment mean -108 12 1 1 H-1 P0 0.245156 -109 12 1 1 H-1 P1 0.173452 -110 12 1 1 H-1 P2 0.092660 -111 12 1 1 H-1 P3 0.047419 -112 12 1 1 O-16 P0 0.027240 -113 12 1 1 O-16 P1 0.013970 -114 12 1 1 O-16 P2 0.000090 -115 12 1 1 O-16 P3 -0.004169 -116 12 1 1 B-10 P0 0.000000 -117 12 1 1 B-10 P1 0.000000 -118 12 1 1 B-10 P2 0.000000 -119 12 1 1 B-10 P3 0.000000 -120 12 1 1 B-11 P0 0.000000 -121 12 1 1 B-11 P1 0.000000 -122 12 1 1 B-11 P2 0.000000 -123 12 1 1 B-11 P3 0.000000 -124 12 1 1 Zr-90 P0 0.095339 -125 12 1 1 Zr-90 P1 0.005341 -126 12 1 1 Zr-90 P2 -0.014156 -127 12 1 1 Zr-90 P3 -0.008036 -128 12 1 1 Zr-91 P0 0.000000 -129 12 1 1 Zr-91 P1 0.000000 -130 12 1 1 Zr-91 P2 0.000000 -131 12 1 1 Zr-91 P3 0.000000 -132 12 1 1 Zr-92 P0 0.013620 -133 12 1 1 Zr-92 P1 0.010119 -134 12 1 1 Zr-92 P2 0.004467 -135 12 1 1 Zr-92 P3 -0.001214 -136 12 1 1 Zr-94 P0 0.013620 -137 12 1 1 Zr-94 P1 0.008770 -138 12 1 1 Zr-94 P2 0.001661 -139 12 1 1 Zr-94 P3 -0.004065 -140 12 1 1 Zr-96 P0 0.013620 -141 12 1 1 Zr-96 P1 0.010890 -142 12 1 1 Zr-96 P2 0.006250 -143 12 1 1 Zr-96 P3 0.001069 -72 12 1 2 H-1 P0 0.027240 -73 12 1 2 H-1 P1 -0.010088 -74 12 1 2 H-1 P2 -0.006946 -75 12 1 2 H-1 P3 0.009692 -76 12 1 2 O-16 P0 0.000000 -77 12 1 2 O-16 P1 0.000000 -78 12 1 2 O-16 P2 0.000000 -79 12 1 2 O-16 P3 0.000000 -80 12 1 2 B-10 P0 0.000000 -81 12 1 2 B-10 P1 0.000000 -82 12 1 2 B-10 P2 0.000000 -83 12 1 2 B-10 P3 0.000000 -84 12 1 2 B-11 P0 0.000000 -85 12 1 2 B-11 P1 0.000000 -86 12 1 2 B-11 P2 0.000000 -87 12 1 2 B-11 P3 0.000000 -88 12 1 2 Zr-90 P0 0.000000 -89 12 1 2 Zr-90 P1 0.000000 -90 12 1 2 Zr-90 P2 0.000000 -91 12 1 2 Zr-90 P3 0.000000 -92 12 1 2 Zr-91 P0 0.000000 -93 12 1 2 Zr-91 P1 0.000000 -94 12 1 2 Zr-91 P2 0.000000 -95 12 1 2 Zr-91 P3 0.000000 -96 12 1 2 Zr-92 P0 0.000000 -97 12 1 2 Zr-92 P1 0.000000 -98 12 1 2 Zr-92 P2 0.000000 -99 12 1 2 Zr-92 P3 0.000000 -100 12 1 2 Zr-94 P0 0.000000 -101 12 1 2 Zr-94 P1 0.000000 -102 12 1 2 Zr-94 P2 0.000000 -103 12 1 2 Zr-94 P3 0.000000 -104 12 1 2 Zr-96 P0 0.000000 -105 12 1 2 Zr-96 P1 0.000000 -106 12 1 2 Zr-96 P2 0.000000 -107 12 1 2 Zr-96 P3 0.000000 -36 12 2 1 H-1 P0 0.000000 -37 12 2 1 H-1 P1 0.000000 -38 12 2 1 H-1 P2 0.000000 -39 12 2 1 H-1 P3 0.000000 -40 12 2 1 O-16 P0 0.000000 -41 12 2 1 O-16 P1 0.000000 -42 12 2 1 O-16 P2 0.000000 -43 12 2 1 O-16 P3 0.000000 -44 12 2 1 B-10 P0 0.000000 -45 12 2 1 B-10 P1 0.000000 -46 12 2 1 B-10 P2 0.000000 -47 12 2 1 B-10 P3 0.000000 -48 12 2 1 B-11 P0 0.000000 -49 12 2 1 B-11 P1 0.000000 -50 12 2 1 B-11 P2 0.000000 -51 12 2 1 B-11 P3 0.000000 -52 12 2 1 Zr-90 P0 0.000000 -53 12 2 1 Zr-90 P1 0.000000 -54 12 2 1 Zr-90 P2 0.000000 -55 12 2 1 Zr-90 P3 0.000000 -56 12 2 1 Zr-91 P0 0.000000 -57 12 2 1 Zr-91 P1 0.000000 -58 12 2 1 Zr-91 P2 0.000000 -59 12 2 1 Zr-91 P3 0.000000 -60 12 2 1 Zr-92 P0 0.000000 -61 12 2 1 Zr-92 P1 0.000000 -62 12 2 1 Zr-92 P2 0.000000 -63 12 2 1 Zr-92 P3 0.000000 -64 12 2 1 Zr-94 P0 0.000000 -65 12 2 1 Zr-94 P1 0.000000 -66 12 2 1 Zr-94 P2 0.000000 -67 12 2 1 Zr-94 P3 0.000000 -68 12 2 1 Zr-96 P0 0.000000 -69 12 2 1 Zr-96 P1 0.000000 -70 12 2 1 Zr-96 P2 0.000000 -71 12 2 1 Zr-96 P3 0.000000 -0 12 2 2 H-1 P0 1.489686 -1 12 2 2 H-1 P1 0.257467 -2 12 2 2 H-1 P2 0.001678 -3 12 2 2 H-1 P3 0.044735 -4 12 2 2 O-16 P0 0.067713 -5 12 2 2 O-16 P1 -0.011446 -6 12 2 2 O-16 P2 -0.002500 -7 12 2 2 O-16 P3 0.007446 -8 12 2 2 B-10 P0 0.000000 -9 12 2 2 B-10 P1 0.000000 -10 12 2 2 B-10 P2 0.000000 -11 12 2 2 B-10 P3 0.000000 -12 12 2 2 B-11 P0 0.000000 -13 12 2 2 B-11 P1 0.000000 -14 12 2 2 B-11 P2 0.000000 -15 12 2 2 B-11 P3 0.000000 -16 12 2 2 Zr-90 P0 0.000000 -17 12 2 2 Zr-90 P1 0.000000 -18 12 2 2 Zr-90 P2 0.000000 -19 12 2 2 Zr-90 P3 0.000000 -20 12 2 2 Zr-91 P0 0.016928 -21 12 2 2 Zr-91 P1 -0.016273 -22 12 2 2 Zr-91 P2 0.015000 -23 12 2 2 Zr-91 P3 -0.013183 -24 12 2 2 Zr-92 P0 0.000000 -25 12 2 2 Zr-92 P1 0.000000 -26 12 2 2 Zr-92 P2 0.000000 -27 12 2 2 Zr-92 P3 0.000000 -28 12 2 2 Zr-94 P0 0.000000 -29 12 2 2 Zr-94 P1 0.000000 -30 12 2 2 Zr-94 P2 0.000000 -31 12 2 2 Zr-94 P3 0.000000 -32 12 2 2 Zr-96 P0 0.000000 -33 12 2 2 Zr-96 P1 0.000000 -34 12 2 2 Zr-96 P2 0.000000 -35 12 2 2 Zr-96 P3 0.000000 material group out nuclide mean std. dev. -9 12 1 H-1 0 0 -10 12 1 O-16 0 0 -11 12 1 B-10 0 0 -12 12 1 B-11 0 0 -13 12 1 Zr-90 0 0 -14 12 1 Zr-91 0 0 -15 12 1 Zr-92 0 0 -16 12 1 Zr-94 0 0 -17 12 1 Zr-96 0 0 -0 12 2 H-1 0 0 -1 12 2 O-16 0 0 -2 12 2 B-10 0 0 -3 12 2 B-11 0 0 -4 12 2 Zr-90 0 0 -5 12 2 Zr-91 0 0 -6 12 2 Zr-92 0 0 -7 12 2 Zr-94 0 0 -8 12 2 Zr-96 0 0 \ No newline at end of file +002a4c91c4b4288dbac2cba267175c4560cca43685bfd5d415775e9fc1635866c1f9c3396a44d01dd29f734a0432e132408d36c9f7c4e34783cc295f2d9dc393 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py index e0a7c199a..47c1ec60a 100644 --- a/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py +++ b/tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py @@ -37,7 +37,7 @@ class MGXSTestHarness(PyAPITestHarness): self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False) self._input_set.tallies.export_to_xml() - def _get_results(self, hash_output=False): + def _get_results(self, hash_output=True): """Digest info in the statepoint and return as a string.""" # Read the statepoint file. From eb20de6a51b35d221c8ee8e1f0cc0d86478bba14 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Fri, 13 May 2016 22:32:48 -0400 Subject: [PATCH 130/147] Updating per the latest round of comments. This includes simplifying the notebook significantly, and adding a get_xsdata method to Library. --- .../pythonapi/examples/mgxs-part-iv.ipynb | 1428 +++-------------- docs/source/usersguide/mgxs_library.rst | 6 +- openmc/material.py | 12 +- openmc/mgxs/library.py | 275 ++-- openmc/mgxs_library.py | 211 +-- src/input_xml.F90 | 12 +- 6 files changed, 393 insertions(+), 1551 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index 823d67ae1..d03db2cce 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -7,9 +7,8 @@ "This Notebook illustrates the use of the openmc.mgxs.Library class specifically for application in OpenMC's multi-group mode. This example notebook follows the same process as was done in MGXS Part III, but instead uses OpenMC as the multi-group solver. This Notebook illustrates the following features:\n", "\n", " - Calculation of multi-group cross sections for a fuel assembly\n", - " - Automated creation, manipulation and storage of MGXS with openmc.mgxs.Library\n", - " - Validation of multi-group cross sections with OpenMC\n", - " - Steady-state pin-by-pin fission rates comparison between Continuous-Energy mode and Multi-Group OpenMC.\n", + " - Automated creation and storage of MGXS with openmc.mgxs.Library\n", + " - Steady-state pin-by-pin fission rates comparison between continuous-energy and multi-group OpenMC.\n", "\n", "Note: This Notebook illustrates the use of Pandas DataFrames to containerize multi-group cross section data. We recommend using Pandas >v0.15.0 or later since OpenMC's Python API leverages the multi-indexing feature included in the most recent releases of Pandas.\n" ] @@ -84,23 +83,23 @@ "outputs": [], "source": [ "# 1.6 enriched fuel\n", - "fuel = openmc.Material(name='1.6% Fuel')\n", + "fuel = openmc.Material(name='1.6% Fuel', material_id=1)\n", "fuel.set_density('g/cm3', 10.31341)\n", "fuel.add_nuclide(u235, 3.7503e-4)\n", "fuel.add_nuclide(u238, 2.2625e-2)\n", "fuel.add_nuclide(o16, 4.6007e-2)\n", "\n", + "# zircaloy\n", + "zircaloy = openmc.Material(name='Zircaloy', material_id=2)\n", + "zircaloy.set_density('g/cm3', 6.55)\n", + "zircaloy.add_nuclide(zr90, 7.2758e-3)\n", + "\n", "# borated water\n", - "water = openmc.Material(name='Borated Water')\n", + "water = openmc.Material(name='Borated Water', material_id=3)\n", "water.set_density('g/cm3', 0.740582)\n", "water.add_nuclide(h1, 4.9457e-2)\n", "water.add_nuclide(o16, 2.4732e-2)\n", - "water.add_nuclide(b10, 8.0042e-6)\n", - "\n", - "# zircaloy\n", - "zircaloy = openmc.Material(name='Zircaloy')\n", - "zircaloy.set_density('g/cm3', 6.55)\n", - "zircaloy.add_nuclide(zr90, 7.2758e-3)" + "water.add_nuclide(b10, 8.0042e-6)\n" ] }, { @@ -119,7 +118,7 @@ "outputs": [], "source": [ "# Instantiate a Materials object\n", - "materials_file = openmc.Materials((fuel, water, zircaloy))\n", + "materials_file = openmc.Materials((fuel, zircaloy, water))\n", "materials_file.default_xs = '71c'\n", "\n", "# Export to \"materials.xml\"\n", @@ -347,7 +346,7 @@ "outputs": [], "source": [ "# OpenMC simulation parameters\n", - "batches = 500\n", + "batches = 50\n", "inactive = 10\n", "particles = 5000\n", "\n", @@ -434,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -523,7 +522,7 @@ "source": [ "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material,\" \"cell,\" and \"universe\" domain types. We will use a \"cell\" domain type here to compute cross sections in each of the cells in the fuel assembly geometry.\n", "\n", - "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell or universe) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property. In our case, we wish to compute multi-group cross sections in each and every cell since they will be needed in our downstream multi-group OpenMC calculation on the identical combinatorial geometry mesh." + "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell or universe) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property. In our this simple example, we wish to compute multi-group cross sections only for each material." ] }, { @@ -535,10 +534,10 @@ "outputs": [], "source": [ "# Specify a \"cell\" domain type for the cross section tally filters\n", - "mgxs_lib.domain_type = \"cell\"\n", + "mgxs_lib.domain_type = \"material\"\n", "\n", "# Specify the cell domains over which to compute multi-group cross sections\n", - "mgxs_lib.domains = geometry.get_all_material_cells()" + "mgxs_lib.domains = geometry.get_all_materials()" ] }, { @@ -697,7 +696,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-12 21:15:02\n", + " Date/Time: 2016-05-13 22:29:41\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -713,9 +712,9 @@ " Loading ACE cross section table: 92235.71c\n", " Loading ACE cross section table: 92238.71c\n", " Loading ACE cross section table: 8016.71c\n", + " Loading ACE cross section table: 40090.71c\n", " Loading ACE cross section table: 1001.71c\n", " Loading ACE cross section table: 5010.71c\n", - " Loading ACE cross section table: 40090.71c\n", " Maximum neutron transport energy: 20.0000 MeV for 92235.71c\n", " Initializing source particles...\n", "\n", @@ -725,507 +724,57 @@ "\n", " Bat./Gen. k Average k \n", " ========= ======== ==================== \n", - " 1/1 1.05162 \n", - " 2/1 1.05369 \n", - " 3/1 1.02989 \n", - " 4/1 1.00126 \n", - " 5/1 1.03151 \n", - " 6/1 1.00183 \n", - " 7/1 0.99379 \n", - " 8/1 1.04193 \n", - " 9/1 1.01578 \n", - " 10/1 1.03349 \n", - " 11/1 1.03354 \n", - " 12/1 1.03646 1.03500 +/- 0.00146\n", - " 13/1 1.00873 1.02624 +/- 0.00880\n", - " 14/1 1.04263 1.03034 +/- 0.00745\n", - " 15/1 1.01556 1.02738 +/- 0.00648\n", - " 16/1 1.04897 1.03098 +/- 0.00640\n", - " 17/1 1.01796 1.02912 +/- 0.00572\n", - " 18/1 1.02276 1.02833 +/- 0.00502\n", - " 19/1 1.04003 1.02963 +/- 0.00461\n", - " 20/1 1.00695 1.02736 +/- 0.00471\n", - " 21/1 1.00012 1.02488 +/- 0.00493\n", - " 22/1 1.03580 1.02579 +/- 0.00459\n", - " 23/1 1.03427 1.02644 +/- 0.00427\n", - " 24/1 1.06024 1.02886 +/- 0.00463\n", - " 25/1 1.00742 1.02743 +/- 0.00454\n", - " 26/1 1.02556 1.02731 +/- 0.00425\n", - " 27/1 1.02207 1.02700 +/- 0.00401\n", - " 28/1 1.05847 1.02875 +/- 0.00416\n", - " 29/1 1.01125 1.02783 +/- 0.00404\n", - " 30/1 1.03213 1.02804 +/- 0.00384\n", - " 31/1 1.02241 1.02778 +/- 0.00366\n", - " 32/1 1.02675 1.02773 +/- 0.00349\n", - " 33/1 1.05484 1.02891 +/- 0.00354\n", - " 34/1 1.01893 1.02849 +/- 0.00341\n", - " 35/1 0.99044 1.02697 +/- 0.00361\n", - " 36/1 1.02602 1.02693 +/- 0.00347\n", - " 37/1 1.04107 1.02746 +/- 0.00338\n", - " 38/1 1.03237 1.02763 +/- 0.00326\n", - " 39/1 1.01489 1.02719 +/- 0.00318\n", - " 40/1 1.01065 1.02664 +/- 0.00312\n", - " 41/1 1.03722 1.02698 +/- 0.00304\n", - " 42/1 1.04339 1.02750 +/- 0.00298\n", - " 43/1 1.00921 1.02694 +/- 0.00294\n", - " 44/1 1.04576 1.02750 +/- 0.00291\n", - " 45/1 1.02580 1.02745 +/- 0.00283\n", - " 46/1 1.03464 1.02765 +/- 0.00275\n", - " 47/1 1.01552 1.02732 +/- 0.00270\n", - " 48/1 1.03357 1.02748 +/- 0.00263\n", - " 49/1 1.03439 1.02766 +/- 0.00257\n", - " 50/1 1.04281 1.02804 +/- 0.00253\n", - " 51/1 1.02902 1.02806 +/- 0.00247\n", - " 52/1 1.02245 1.02793 +/- 0.00241\n", - " 53/1 1.05271 1.02851 +/- 0.00243\n", - " 54/1 0.98630 1.02755 +/- 0.00256\n", - " 55/1 1.02690 1.02753 +/- 0.00250\n", - " 56/1 1.04107 1.02783 +/- 0.00246\n", - " 57/1 1.03029 1.02788 +/- 0.00241\n", - " 58/1 1.01874 1.02769 +/- 0.00237\n", - " 59/1 1.04211 1.02798 +/- 0.00234\n", - " 60/1 0.99584 1.02734 +/- 0.00238\n", - " 61/1 1.05166 1.02782 +/- 0.00238\n", - " 62/1 1.05572 1.02835 +/- 0.00239\n", - " 63/1 1.02694 1.02833 +/- 0.00235\n", - " 64/1 1.03314 1.02842 +/- 0.00231\n", - " 65/1 1.05850 1.02896 +/- 0.00233\n", - " 66/1 1.01100 1.02864 +/- 0.00231\n", - " 67/1 1.03784 1.02880 +/- 0.00227\n", - " 68/1 1.04084 1.02901 +/- 0.00224\n", - " 69/1 1.03932 1.02919 +/- 0.00221\n", - " 70/1 1.02564 1.02913 +/- 0.00218\n", - " 71/1 1.00027 1.02865 +/- 0.00219\n", - " 72/1 1.02385 1.02858 +/- 0.00216\n", - " 73/1 1.04885 1.02890 +/- 0.00215\n", - " 74/1 1.00298 1.02849 +/- 0.00215\n", - " 75/1 1.02009 1.02836 +/- 0.00212\n", - " 76/1 1.04505 1.02862 +/- 0.00211\n", - " 77/1 1.02889 1.02862 +/- 0.00207\n", - " 78/1 1.01306 1.02839 +/- 0.00206\n", - " 79/1 1.01817 1.02824 +/- 0.00203\n", - " 80/1 1.00533 1.02792 +/- 0.00203\n", - " 81/1 1.04439 1.02815 +/- 0.00201\n", - " 82/1 1.02212 1.02806 +/- 0.00199\n", - " 83/1 0.99419 1.02760 +/- 0.00201\n", - " 84/1 1.07132 1.02819 +/- 0.00207\n", - " 85/1 1.02710 1.02818 +/- 0.00204\n", - " 86/1 1.01702 1.02803 +/- 0.00202\n", - " 87/1 1.02134 1.02794 +/- 0.00200\n", - " 88/1 1.05231 1.02826 +/- 0.00200\n", - " 89/1 1.05290 1.02857 +/- 0.00200\n", - " 90/1 1.05751 1.02893 +/- 0.00200\n", - " 91/1 1.03970 1.02906 +/- 0.00198\n", - " 92/1 0.99678 1.02867 +/- 0.00200\n", - " 93/1 1.04471 1.02886 +/- 0.00198\n", - " 94/1 1.00820 1.02862 +/- 0.00198\n", - " 95/1 1.05823 1.02896 +/- 0.00198\n", - " 96/1 1.05118 1.02922 +/- 0.00198\n", - " 97/1 1.03617 1.02930 +/- 0.00196\n", - " 98/1 1.00585 1.02904 +/- 0.00195\n", - " 99/1 1.06663 1.02946 +/- 0.00198\n", - " 100/1 1.01802 1.02933 +/- 0.00196\n", - " 101/1 1.02695 1.02931 +/- 0.00194\n", - " 102/1 1.01642 1.02917 +/- 0.00192\n", - " 103/1 1.02567 1.02913 +/- 0.00190\n", - " 104/1 1.03519 1.02919 +/- 0.00188\n", - " 105/1 1.02439 1.02914 +/- 0.00186\n", - " 106/1 1.03779 1.02923 +/- 0.00184\n", - " 107/1 1.01304 1.02906 +/- 0.00183\n", - " 108/1 1.02541 1.02903 +/- 0.00181\n", - " 109/1 1.04297 1.02917 +/- 0.00180\n", - " 110/1 1.00442 1.02892 +/- 0.00180\n", - " 111/1 1.03102 1.02894 +/- 0.00178\n", - " 112/1 1.00380 1.02870 +/- 0.00178\n", - " 113/1 1.04010 1.02881 +/- 0.00177\n", - " 114/1 1.01297 1.02865 +/- 0.00176\n", - " 115/1 1.00130 1.02839 +/- 0.00176\n", - " 116/1 1.02001 1.02831 +/- 0.00174\n", - " 117/1 1.03847 1.02841 +/- 0.00173\n", - " 118/1 1.00371 1.02818 +/- 0.00173\n", - " 119/1 1.02650 1.02817 +/- 0.00171\n", - " 120/1 1.00767 1.02798 +/- 0.00171\n", - " 121/1 1.00408 1.02776 +/- 0.00171\n", - " 122/1 1.00235 1.02754 +/- 0.00171\n", - " 123/1 1.01212 1.02740 +/- 0.00170\n", - " 124/1 1.03278 1.02745 +/- 0.00168\n", - " 125/1 1.00818 1.02728 +/- 0.00168\n", - " 126/1 1.02132 1.02723 +/- 0.00166\n", - " 127/1 1.03677 1.02731 +/- 0.00165\n", - " 128/1 1.04148 1.02743 +/- 0.00164\n", - " 129/1 1.01245 1.02730 +/- 0.00163\n", - " 130/1 1.04172 1.02742 +/- 0.00162\n", - " 131/1 1.04519 1.02757 +/- 0.00162\n", - " 132/1 1.02495 1.02755 +/- 0.00160\n", - " 133/1 0.99747 1.02731 +/- 0.00161\n", - " 134/1 1.02411 1.02728 +/- 0.00160\n", - " 135/1 1.05750 1.02752 +/- 0.00160\n", - " 136/1 1.02341 1.02749 +/- 0.00159\n", - " 137/1 1.02212 1.02745 +/- 0.00158\n", - " 138/1 1.03464 1.02750 +/- 0.00157\n", - " 139/1 1.05920 1.02775 +/- 0.00157\n", - " 140/1 1.01911 1.02768 +/- 0.00156\n", - " 141/1 1.03076 1.02771 +/- 0.00155\n", - " 142/1 1.03648 1.02777 +/- 0.00154\n", - " 143/1 1.00382 1.02759 +/- 0.00154\n", - " 144/1 1.00366 1.02741 +/- 0.00154\n", - " 145/1 1.01638 1.02733 +/- 0.00153\n", - " 146/1 1.02418 1.02731 +/- 0.00152\n", - " 147/1 0.99267 1.02706 +/- 0.00153\n", - " 148/1 1.02575 1.02705 +/- 0.00152\n", - " 149/1 0.98560 1.02675 +/- 0.00153\n", - " 150/1 1.02725 1.02675 +/- 0.00152\n", - " 151/1 1.03723 1.02683 +/- 0.00151\n", - " 152/1 1.00857 1.02670 +/- 0.00151\n", - " 153/1 1.00642 1.02656 +/- 0.00151\n", - " 154/1 1.03461 1.02661 +/- 0.00150\n", - " 155/1 1.00088 1.02643 +/- 0.00150\n", - " 156/1 1.02589 1.02643 +/- 0.00149\n", - " 157/1 1.02494 1.02642 +/- 0.00148\n", - " 158/1 1.03303 1.02646 +/- 0.00147\n", - " 159/1 1.02276 1.02644 +/- 0.00146\n", - " 160/1 1.03293 1.02648 +/- 0.00145\n", - " 161/1 1.04758 1.02662 +/- 0.00144\n", - " 162/1 1.01033 1.02652 +/- 0.00144\n", - " 163/1 1.03883 1.02660 +/- 0.00143\n", - " 164/1 1.00519 1.02646 +/- 0.00143\n", - " 165/1 1.05958 1.02667 +/- 0.00144\n", - " 166/1 1.03849 1.02675 +/- 0.00143\n", - " 167/1 1.02306 1.02672 +/- 0.00142\n", - " 168/1 1.02693 1.02672 +/- 0.00141\n", - " 169/1 1.02584 1.02672 +/- 0.00140\n", - " 170/1 0.99388 1.02651 +/- 0.00141\n", - " 171/1 0.99376 1.02631 +/- 0.00141\n", - " 172/1 1.00453 1.02618 +/- 0.00141\n", - " 173/1 1.04516 1.02629 +/- 0.00141\n", - " 174/1 1.02402 1.02628 +/- 0.00140\n", - " 175/1 0.99012 1.02606 +/- 0.00141\n", - " 176/1 1.02084 1.02603 +/- 0.00140\n", - " 177/1 1.03959 1.02611 +/- 0.00139\n", - " 178/1 1.01719 1.02606 +/- 0.00139\n", - " 179/1 1.01671 1.02600 +/- 0.00138\n", - " 180/1 1.03691 1.02606 +/- 0.00137\n", - " 181/1 1.04276 1.02616 +/- 0.00137\n", - " 182/1 1.02002 1.02613 +/- 0.00136\n", - " 183/1 1.03081 1.02615 +/- 0.00135\n", - " 184/1 1.02432 1.02614 +/- 0.00135\n", - " 185/1 1.02225 1.02612 +/- 0.00134\n", - " 186/1 1.04722 1.02624 +/- 0.00134\n", - " 187/1 0.98045 1.02598 +/- 0.00135\n", - " 188/1 1.02555 1.02598 +/- 0.00135\n", - " 189/1 1.03645 1.02604 +/- 0.00134\n", - " 190/1 1.00407 1.02592 +/- 0.00134\n", - " 191/1 1.03033 1.02594 +/- 0.00133\n", - " 192/1 1.04175 1.02603 +/- 0.00133\n", - " 193/1 1.00555 1.02592 +/- 0.00132\n", - " 194/1 1.00183 1.02578 +/- 0.00132\n", - " 195/1 1.04328 1.02588 +/- 0.00132\n", - " 196/1 1.03041 1.02590 +/- 0.00131\n", - " 197/1 1.04791 1.02602 +/- 0.00131\n", - " 198/1 1.01366 1.02596 +/- 0.00130\n", - " 199/1 1.04471 1.02605 +/- 0.00130\n", - " 200/1 1.02416 1.02604 +/- 0.00129\n", - " 201/1 1.01172 1.02597 +/- 0.00129\n", - " 202/1 1.01683 1.02592 +/- 0.00128\n", - " 203/1 1.01341 1.02586 +/- 0.00128\n", - " 204/1 1.01507 1.02580 +/- 0.00127\n", - " 205/1 1.02540 1.02580 +/- 0.00127\n", - " 206/1 1.00310 1.02568 +/- 0.00127\n", - " 207/1 1.02822 1.02570 +/- 0.00126\n", - " 208/1 1.01023 1.02562 +/- 0.00126\n", - " 209/1 1.04603 1.02572 +/- 0.00125\n", - " 210/1 1.00775 1.02563 +/- 0.00125\n", - " 211/1 1.01706 1.02559 +/- 0.00125\n", - " 212/1 0.99434 1.02543 +/- 0.00125\n", - " 213/1 1.03346 1.02547 +/- 0.00124\n", - " 214/1 1.05322 1.02561 +/- 0.00124\n", - " 215/1 1.03057 1.02563 +/- 0.00124\n", - " 216/1 1.00976 1.02556 +/- 0.00123\n", - " 217/1 1.02760 1.02557 +/- 0.00123\n", - " 218/1 1.01259 1.02550 +/- 0.00122\n", - " 219/1 1.02829 1.02552 +/- 0.00122\n", - " 220/1 1.02228 1.02550 +/- 0.00121\n", - " 221/1 1.06679 1.02570 +/- 0.00122\n", - " 222/1 1.03417 1.02574 +/- 0.00122\n", - " 223/1 1.04239 1.02582 +/- 0.00121\n", - " 224/1 1.02062 1.02579 +/- 0.00121\n", - " 225/1 1.00331 1.02569 +/- 0.00121\n", - " 226/1 1.00131 1.02557 +/- 0.00121\n", - " 227/1 1.01768 1.02554 +/- 0.00120\n", - " 228/1 1.00813 1.02546 +/- 0.00120\n", - " 229/1 1.05320 1.02558 +/- 0.00120\n", - " 230/1 1.03472 1.02563 +/- 0.00120\n", - " 231/1 1.01426 1.02557 +/- 0.00119\n", - " 232/1 1.00782 1.02549 +/- 0.00119\n", - " 233/1 1.02813 1.02551 +/- 0.00118\n", - " 234/1 1.01184 1.02545 +/- 0.00118\n", - " 235/1 1.02156 1.02543 +/- 0.00118\n", - " 236/1 0.99029 1.02527 +/- 0.00118\n", - " 237/1 1.04196 1.02535 +/- 0.00118\n", - " 238/1 1.01594 1.02531 +/- 0.00117\n", - " 239/1 1.02732 1.02531 +/- 0.00117\n", - " 240/1 0.98987 1.02516 +/- 0.00117\n", - " 241/1 1.03388 1.02520 +/- 0.00117\n", - " 242/1 1.01319 1.02515 +/- 0.00116\n", - " 243/1 1.02870 1.02516 +/- 0.00116\n", - " 244/1 1.01943 1.02514 +/- 0.00115\n", - " 245/1 1.04463 1.02522 +/- 0.00115\n", - " 246/1 1.03551 1.02526 +/- 0.00115\n", - " 247/1 1.00436 1.02517 +/- 0.00115\n", - " 248/1 1.03326 1.02521 +/- 0.00114\n", - " 249/1 1.05769 1.02534 +/- 0.00115\n", - " 250/1 1.01372 1.02530 +/- 0.00114\n", - " 251/1 1.02971 1.02531 +/- 0.00114\n", - " 252/1 1.01166 1.02526 +/- 0.00113\n", - " 253/1 1.03992 1.02532 +/- 0.00113\n", - " 254/1 1.01507 1.02528 +/- 0.00113\n", - " 255/1 1.03222 1.02530 +/- 0.00112\n", - " 256/1 1.03096 1.02533 +/- 0.00112\n", - " 257/1 1.01153 1.02527 +/- 0.00112\n", - " 258/1 1.03668 1.02532 +/- 0.00111\n", - " 259/1 1.03070 1.02534 +/- 0.00111\n", - " 260/1 1.01189 1.02529 +/- 0.00111\n", - " 261/1 1.00082 1.02519 +/- 0.00111\n", - " 262/1 1.03653 1.02523 +/- 0.00110\n", - " 263/1 1.02908 1.02525 +/- 0.00110\n", - " 264/1 1.00072 1.02515 +/- 0.00110\n", - " 265/1 1.00832 1.02509 +/- 0.00109\n", - " 266/1 1.04385 1.02516 +/- 0.00109\n", - " 267/1 1.00117 1.02507 +/- 0.00109\n", - " 268/1 1.02682 1.02507 +/- 0.00109\n", - " 269/1 1.03202 1.02510 +/- 0.00108\n", - " 270/1 1.01275 1.02505 +/- 0.00108\n", - " 271/1 1.02633 1.02506 +/- 0.00108\n", - " 272/1 1.04811 1.02514 +/- 0.00108\n", - " 273/1 1.02851 1.02516 +/- 0.00107\n", - " 274/1 1.01270 1.02511 +/- 0.00107\n", - " 275/1 1.06222 1.02525 +/- 0.00107\n", - " 276/1 1.02778 1.02526 +/- 0.00107\n", - " 277/1 1.02601 1.02526 +/- 0.00107\n", - " 278/1 1.02356 1.02526 +/- 0.00106\n", - " 279/1 1.00792 1.02519 +/- 0.00106\n", - " 280/1 1.02331 1.02518 +/- 0.00106\n", - " 281/1 1.00985 1.02513 +/- 0.00105\n", - " 282/1 1.02035 1.02511 +/- 0.00105\n", - " 283/1 0.98181 1.02495 +/- 0.00106\n", - " 284/1 1.01829 1.02493 +/- 0.00106\n", - " 285/1 1.02929 1.02494 +/- 0.00105\n", - " 286/1 1.03524 1.02498 +/- 0.00105\n", - " 287/1 1.01212 1.02493 +/- 0.00105\n", - " 288/1 1.03584 1.02497 +/- 0.00104\n", - " 289/1 1.02961 1.02499 +/- 0.00104\n", - " 290/1 0.99692 1.02489 +/- 0.00104\n", - " 291/1 1.03966 1.02494 +/- 0.00104\n", - " 292/1 1.00965 1.02489 +/- 0.00104\n", - " 293/1 1.02601 1.02489 +/- 0.00103\n", - " 294/1 1.03224 1.02492 +/- 0.00103\n", - " 295/1 1.01596 1.02489 +/- 0.00103\n", - " 296/1 1.06964 1.02504 +/- 0.00103\n", - " 297/1 1.03982 1.02509 +/- 0.00103\n", - " 298/1 0.99758 1.02500 +/- 0.00103\n", - " 299/1 1.01479 1.02496 +/- 0.00103\n", - " 300/1 1.04517 1.02503 +/- 0.00103\n", - " 301/1 0.99128 1.02492 +/- 0.00103\n", - " 302/1 1.01493 1.02488 +/- 0.00103\n", - " 303/1 1.00623 1.02482 +/- 0.00103\n", - " 304/1 1.02560 1.02482 +/- 0.00102\n", - " 305/1 1.00806 1.02477 +/- 0.00102\n", - " 306/1 1.03524 1.02480 +/- 0.00102\n", - " 307/1 0.99244 1.02469 +/- 0.00102\n", - " 308/1 0.98013 1.02454 +/- 0.00103\n", - " 309/1 1.00853 1.02449 +/- 0.00103\n", - " 310/1 1.00116 1.02441 +/- 0.00103\n", - " 311/1 1.01730 1.02439 +/- 0.00102\n", - " 312/1 1.01198 1.02435 +/- 0.00102\n", - " 313/1 1.02405 1.02435 +/- 0.00102\n", - " 314/1 1.01734 1.02432 +/- 0.00101\n", - " 315/1 1.02320 1.02432 +/- 0.00101\n", - " 316/1 1.03438 1.02435 +/- 0.00101\n", - " 317/1 1.00106 1.02428 +/- 0.00101\n", - " 318/1 1.03114 1.02430 +/- 0.00100\n", - " 319/1 1.04955 1.02438 +/- 0.00100\n", - " 320/1 1.03259 1.02441 +/- 0.00100\n", - " 321/1 1.00687 1.02435 +/- 0.00100\n", - " 322/1 1.05753 1.02446 +/- 0.00100\n", - " 323/1 1.03676 1.02450 +/- 0.00100\n", - " 324/1 0.99796 1.02441 +/- 0.00100\n", - " 325/1 1.03783 1.02445 +/- 0.00100\n", - " 326/1 1.02315 1.02445 +/- 0.00099\n", - " 327/1 1.04205 1.02451 +/- 0.00099\n", - " 328/1 1.01971 1.02449 +/- 0.00099\n", - " 329/1 1.02394 1.02449 +/- 0.00099\n", - " 330/1 1.03318 1.02452 +/- 0.00098\n", - " 331/1 1.01503 1.02449 +/- 0.00098\n", - " 332/1 1.07143 1.02463 +/- 0.00099\n", - " 333/1 1.00991 1.02459 +/- 0.00099\n", - " 334/1 1.03115 1.02461 +/- 0.00098\n", - " 335/1 1.04400 1.02467 +/- 0.00098\n", - " 336/1 1.03516 1.02470 +/- 0.00098\n", - " 337/1 1.02025 1.02468 +/- 0.00098\n", - " 338/1 1.03269 1.02471 +/- 0.00098\n", - " 339/1 1.03745 1.02475 +/- 0.00097\n", - " 340/1 1.03685 1.02478 +/- 0.00097\n", - " 341/1 1.01831 1.02476 +/- 0.00097\n", - " 342/1 1.01425 1.02473 +/- 0.00097\n", - " 343/1 1.02990 1.02475 +/- 0.00096\n", - " 344/1 1.02958 1.02476 +/- 0.00096\n", - " 345/1 1.03133 1.02478 +/- 0.00096\n", - " 346/1 1.02441 1.02478 +/- 0.00095\n", - " 347/1 1.07010 1.02492 +/- 0.00096\n", - " 348/1 1.02327 1.02491 +/- 0.00096\n", - " 349/1 1.03123 1.02493 +/- 0.00096\n", - " 350/1 1.03158 1.02495 +/- 0.00095\n", - " 351/1 1.03473 1.02498 +/- 0.00095\n", - " 352/1 1.04000 1.02502 +/- 0.00095\n", - " 353/1 1.01651 1.02500 +/- 0.00095\n", - " 354/1 1.03647 1.02503 +/- 0.00094\n", - " 355/1 1.04650 1.02509 +/- 0.00094\n", - " 356/1 1.04703 1.02516 +/- 0.00094\n", - " 357/1 1.00260 1.02509 +/- 0.00094\n", - " 358/1 1.00075 1.02502 +/- 0.00094\n", - " 359/1 1.04874 1.02509 +/- 0.00094\n", - " 360/1 1.03211 1.02511 +/- 0.00094\n", - " 361/1 1.02136 1.02510 +/- 0.00094\n", - " 362/1 1.00803 1.02505 +/- 0.00094\n", - " 363/1 1.00319 1.02499 +/- 0.00094\n", - " 364/1 1.01443 1.02496 +/- 0.00093\n", - " 365/1 1.02685 1.02496 +/- 0.00093\n", - " 366/1 1.02373 1.02496 +/- 0.00093\n", - " 367/1 1.02026 1.02495 +/- 0.00093\n", - " 368/1 1.01579 1.02492 +/- 0.00092\n", - " 369/1 1.08004 1.02508 +/- 0.00093\n", - " 370/1 1.01715 1.02505 +/- 0.00093\n", - " 371/1 0.98578 1.02494 +/- 0.00093\n", - " 372/1 1.03033 1.02496 +/- 0.00093\n", - " 373/1 1.03269 1.02498 +/- 0.00093\n", - " 374/1 1.04050 1.02502 +/- 0.00093\n", - " 375/1 1.00760 1.02498 +/- 0.00093\n", - " 376/1 1.04492 1.02503 +/- 0.00093\n", - " 377/1 1.04983 1.02510 +/- 0.00093\n", - " 378/1 1.06022 1.02519 +/- 0.00093\n", - " 379/1 1.02516 1.02519 +/- 0.00093\n", - " 380/1 1.01740 1.02517 +/- 0.00092\n", - " 381/1 1.02520 1.02517 +/- 0.00092\n", - " 382/1 1.02820 1.02518 +/- 0.00092\n", - " 383/1 1.00697 1.02513 +/- 0.00092\n", - " 384/1 1.03497 1.02516 +/- 0.00092\n", - " 385/1 0.98404 1.02505 +/- 0.00092\n", - " 386/1 1.05206 1.02512 +/- 0.00092\n", - " 387/1 1.01502 1.02509 +/- 0.00092\n", - " 388/1 1.02196 1.02508 +/- 0.00092\n", - " 389/1 1.02856 1.02509 +/- 0.00091\n", - " 390/1 1.01376 1.02506 +/- 0.00091\n", - " 391/1 1.01696 1.02504 +/- 0.00091\n", - " 392/1 1.03283 1.02506 +/- 0.00091\n", - " 393/1 1.00787 1.02502 +/- 0.00091\n", - " 394/1 1.02184 1.02501 +/- 0.00090\n", - " 395/1 1.03170 1.02503 +/- 0.00090\n", - " 396/1 1.04406 1.02508 +/- 0.00090\n", - " 397/1 1.03939 1.02511 +/- 0.00090\n", - " 398/1 1.00329 1.02506 +/- 0.00090\n", - " 399/1 1.04518 1.02511 +/- 0.00090\n", - " 400/1 1.03435 1.02513 +/- 0.00090\n", - " 401/1 1.00525 1.02508 +/- 0.00089\n", - " 402/1 1.03112 1.02510 +/- 0.00089\n", - " 403/1 1.00188 1.02504 +/- 0.00089\n", - " 404/1 1.01241 1.02501 +/- 0.00089\n", - " 405/1 1.01796 1.02499 +/- 0.00089\n", - " 406/1 1.02686 1.02499 +/- 0.00089\n", - " 407/1 1.01003 1.02496 +/- 0.00088\n", - " 408/1 1.02359 1.02495 +/- 0.00088\n", - " 409/1 1.01258 1.02492 +/- 0.00088\n", - " 410/1 1.04361 1.02497 +/- 0.00088\n", - " 411/1 1.00885 1.02493 +/- 0.00088\n", - " 412/1 1.00999 1.02489 +/- 0.00088\n", - " 413/1 0.97832 1.02477 +/- 0.00088\n", - " 414/1 1.04183 1.02482 +/- 0.00088\n", - " 415/1 1.02279 1.02481 +/- 0.00088\n", - " 416/1 1.04197 1.02485 +/- 0.00088\n", - " 417/1 1.04617 1.02491 +/- 0.00088\n", - " 418/1 1.01311 1.02488 +/- 0.00088\n", - " 419/1 1.03904 1.02491 +/- 0.00087\n", - " 420/1 1.00458 1.02486 +/- 0.00087\n", - " 421/1 0.98580 1.02477 +/- 0.00088\n", - " 422/1 1.01850 1.02475 +/- 0.00087\n", - " 423/1 1.03739 1.02478 +/- 0.00087\n", - " 424/1 1.02716 1.02479 +/- 0.00087\n", - " 425/1 1.00711 1.02475 +/- 0.00087\n", - " 426/1 1.01008 1.02471 +/- 0.00087\n", - " 427/1 1.03332 1.02473 +/- 0.00087\n", - " 428/1 1.00501 1.02468 +/- 0.00087\n", - " 429/1 1.04549 1.02473 +/- 0.00086\n", - " 430/1 1.00582 1.02469 +/- 0.00086\n", - " 431/1 1.00586 1.02464 +/- 0.00086\n", - " 432/1 1.00082 1.02459 +/- 0.00086\n", - " 433/1 1.00835 1.02455 +/- 0.00086\n", - " 434/1 1.03965 1.02458 +/- 0.00086\n", - " 435/1 1.02385 1.02458 +/- 0.00086\n", - " 436/1 1.01440 1.02456 +/- 0.00086\n", - " 437/1 1.03127 1.02458 +/- 0.00085\n", - " 438/1 1.02961 1.02459 +/- 0.00085\n", - " 439/1 0.99584 1.02452 +/- 0.00085\n", - " 440/1 1.04964 1.02458 +/- 0.00085\n", - " 441/1 0.99792 1.02452 +/- 0.00085\n", - " 442/1 1.04971 1.02457 +/- 0.00085\n", - " 443/1 1.01504 1.02455 +/- 0.00085\n", - " 444/1 1.04359 1.02460 +/- 0.00085\n", - " 445/1 1.01148 1.02457 +/- 0.00085\n", - " 446/1 1.01203 1.02454 +/- 0.00085\n", - " 447/1 1.02353 1.02454 +/- 0.00085\n", - " 448/1 1.06299 1.02462 +/- 0.00085\n", - " 449/1 1.00017 1.02457 +/- 0.00085\n", - " 450/1 1.01193 1.02454 +/- 0.00085\n", - " 451/1 1.00179 1.02449 +/- 0.00085\n", - " 452/1 1.02425 1.02449 +/- 0.00085\n", - " 453/1 1.03629 1.02451 +/- 0.00084\n", - " 454/1 1.01955 1.02450 +/- 0.00084\n", - " 455/1 1.00870 1.02447 +/- 0.00084\n", - " 456/1 1.04230 1.02451 +/- 0.00084\n", - " 457/1 1.05081 1.02457 +/- 0.00084\n", - " 458/1 1.00271 1.02452 +/- 0.00084\n", - " 459/1 1.01010 1.02448 +/- 0.00084\n", - " 460/1 1.04656 1.02453 +/- 0.00084\n", - " 461/1 1.00790 1.02450 +/- 0.00084\n", - " 462/1 1.02214 1.02449 +/- 0.00084\n", - " 463/1 1.04401 1.02453 +/- 0.00083\n", - " 464/1 1.02863 1.02454 +/- 0.00083\n", - " 465/1 0.99971 1.02449 +/- 0.00083\n", - " 466/1 1.00344 1.02444 +/- 0.00083\n", - " 467/1 1.02810 1.02445 +/- 0.00083\n", - " 468/1 1.02091 1.02444 +/- 0.00083\n", - " 469/1 1.00545 1.02440 +/- 0.00083\n", - " 470/1 1.01590 1.02438 +/- 0.00083\n", - " 471/1 1.04465 1.02443 +/- 0.00083\n", - " 472/1 1.02028 1.02442 +/- 0.00082\n", - " 473/1 1.01951 1.02441 +/- 0.00082\n", - " 474/1 1.03280 1.02443 +/- 0.00082\n", - " 475/1 1.04722 1.02447 +/- 0.00082\n", - " 476/1 1.03587 1.02450 +/- 0.00082\n", - " 477/1 1.02234 1.02449 +/- 0.00082\n", - " 478/1 1.07848 1.02461 +/- 0.00082\n", - " 479/1 1.04759 1.02466 +/- 0.00082\n", - " 480/1 1.07189 1.02476 +/- 0.00083\n", - " 481/1 1.05811 1.02483 +/- 0.00083\n", - " 482/1 1.04554 1.02487 +/- 0.00083\n", - " 483/1 1.01956 1.02486 +/- 0.00083\n", - " 484/1 1.01055 1.02483 +/- 0.00083\n", - " 485/1 1.00845 1.02480 +/- 0.00082\n", - " 486/1 1.04607 1.02484 +/- 0.00082\n", - " 487/1 1.05955 1.02492 +/- 0.00083\n", - " 488/1 1.02245 1.02491 +/- 0.00082\n", - " 489/1 0.98206 1.02482 +/- 0.00083\n", - " 490/1 1.03786 1.02485 +/- 0.00083\n", - " 491/1 1.02973 1.02486 +/- 0.00082\n", - " 492/1 1.02890 1.02487 +/- 0.00082\n", - " 493/1 1.02086 1.02486 +/- 0.00082\n", - " 494/1 1.01194 1.02483 +/- 0.00082\n", - " 495/1 1.01902 1.02482 +/- 0.00082\n", - " 496/1 1.01783 1.02481 +/- 0.00082\n", - " 497/1 1.02129 1.02480 +/- 0.00081\n", - " 498/1 1.02407 1.02480 +/- 0.00081\n", - " 499/1 1.02873 1.02480 +/- 0.00081\n", - " 500/1 1.00998 1.02477 +/- 0.00081\n", - " Creating state point statepoint.500.h5...\n", + " 1/1 1.05201 \n", + " 2/1 1.02017 \n", + " 3/1 1.02398 \n", + " 4/1 1.02677 \n", + " 5/1 1.01070 \n", + " 6/1 1.02964 \n", + " 7/1 1.02163 \n", + " 8/1 1.04524 \n", + " 9/1 1.00773 \n", + " 10/1 1.01536 \n", + " 11/1 1.02992 \n", + " 12/1 1.03248 1.03120 +/- 0.00128\n", + " 13/1 0.99044 1.01761 +/- 0.01361\n", + " 14/1 1.01484 1.01692 +/- 0.00965\n", + " 15/1 1.01491 1.01652 +/- 0.00748\n", + " 16/1 1.03809 1.02011 +/- 0.00709\n", + " 17/1 1.02536 1.02086 +/- 0.00604\n", + " 18/1 1.03663 1.02283 +/- 0.00559\n", + " 19/1 1.03902 1.02463 +/- 0.00525\n", + " 20/1 1.01557 1.02373 +/- 0.00478\n", + " 21/1 1.01286 1.02274 +/- 0.00443\n", + " 22/1 1.01392 1.02200 +/- 0.00411\n", + " 23/1 1.04439 1.02372 +/- 0.00416\n", + " 24/1 1.04034 1.02491 +/- 0.00403\n", + " 25/1 0.99433 1.02287 +/- 0.00427\n", + " 26/1 1.02720 1.02314 +/- 0.00400\n", + " 27/1 1.03545 1.02387 +/- 0.00383\n", + " 28/1 1.03853 1.02468 +/- 0.00370\n", + " 29/1 1.02735 1.02482 +/- 0.00350\n", + " 30/1 1.02429 1.02480 +/- 0.00332\n", + " 31/1 1.02901 1.02500 +/- 0.00317\n", + " 32/1 1.03296 1.02536 +/- 0.00304\n", + " 33/1 1.03605 1.02582 +/- 0.00294\n", + " 34/1 1.04247 1.02652 +/- 0.00290\n", + " 35/1 1.02088 1.02629 +/- 0.00279\n", + " 36/1 1.03017 1.02644 +/- 0.00269\n", + " 37/1 1.03216 1.02665 +/- 0.00259\n", + " 38/1 1.01459 1.02622 +/- 0.00254\n", + " 39/1 1.03706 1.02659 +/- 0.00248\n", + " 40/1 1.01383 1.02617 +/- 0.00243\n", + " 41/1 0.99043 1.02502 +/- 0.00262\n", + " 42/1 1.02891 1.02514 +/- 0.00254\n", + " 43/1 1.02100 1.02501 +/- 0.00246\n", + " 44/1 0.99546 1.02414 +/- 0.00254\n", + " 45/1 1.01562 1.02390 +/- 0.00248\n", + " 46/1 1.03025 1.02408 +/- 0.00242\n", + " 47/1 0.99409 1.02327 +/- 0.00249\n", + " 48/1 1.04355 1.02380 +/- 0.00248\n", + " 49/1 1.02763 1.02390 +/- 0.00242\n", + " 50/1 0.99426 1.02316 +/- 0.00247\n", + " Creating state point statepoint.50.h5...\n", "\n", " ===========================================================================\n", " ======================> SIMULATION FINISHED <======================\n", @@ -1234,27 +783,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.5880E+00 seconds\n", - " Reading cross sections = 1.2650E+00 seconds\n", - " Total time in simulation = 2.6051E+02 seconds\n", - " Time in transport only = 2.6013E+02 seconds\n", - " Time in inactive batches = 2.0990E+00 seconds\n", - " Time in active batches = 2.5841E+02 seconds\n", - " Time synchronizing fission bank = 6.5000E-02 seconds\n", - " Sampling source sites = 4.4000E-02 seconds\n", - " SEND/RECV source sites = 2.1000E-02 seconds\n", - " Time accumulating tallies = 2.0000E-03 seconds\n", + " Total time for initialization = 1.4550E+00 seconds\n", + " Reading cross sections = 1.1400E+00 seconds\n", + " Total time in simulation = 1.9150E+01 seconds\n", + " Time in transport only = 1.9021E+01 seconds\n", + " Time in inactive batches = 2.1570E+00 seconds\n", + " Time in active batches = 1.6993E+01 seconds\n", + " Time synchronizing fission bank = 7.0000E-03 seconds\n", + " Sampling source sites = 5.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.6211E+02 seconds\n", - " Calculation Rate (inactive) = 23820.9 neutrons/second\n", - " Calculation Rate (active) = 9480.98 neutrons/second\n", + " Total time elapsed = 2.0614E+01 seconds\n", + " Calculation Rate (inactive) = 23180.3 neutrons/second\n", + " Calculation Rate (active) = 11769.6 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02480 +/- 0.00073\n", - " k-effective (Track-length) = 1.02477 +/- 0.00081\n", - " k-effective (Absorption) = 1.02552 +/- 0.00068\n", - " Combined k-effective = 1.02519 +/- 0.00055\n", + " k-effective (Collision) = 1.02389 +/- 0.00235\n", + " k-effective (Track-length) = 1.02316 +/- 0.00247\n", + " k-effective (Absorption) = 1.02494 +/- 0.00180\n", + " Combined k-effective = 1.02429 +/- 0.00140\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -1399,10 +948,12 @@ } ], "source": [ - "mgxs_lib.write_mg_library(filename='mgxs', xs_type='macro',\n", - " domain_names=['fuel', 'fuel_clad', 'fuel_mod',\n", - " 'gt_inmod', 'gt_clad', 'gt_outmod'],\n", - " xs_ids='2m')" + "# Create a MGXS File which can then be written to disk\n", + "mgxs_file = mgxs_lib.create_mg_library(xs_type='macro', domain_names=['fuel', 'zircaloy', 'water'],\n", + " xs_ids='2m')\n", + "\n", + "# Write the file to disk using the default filename of `mgxs.xml`\n", + "mgxs_file.export_to_xml()" ] }, { @@ -1420,49 +971,27 @@ }, "outputs": [], "source": [ - "# Instantiate our Macroscopic Data using mat_names for the name\n", + "# Instantiate our Macroscopic Data\n", "fuel_macro = openmc.Macroscopic('fuel')\n", - "fuel_clad_macro = openmc.Macroscopic('fuel_clad')\n", - "fuel_mod_macro = openmc.Macroscopic('fuel_mod')\n", - "gt_inmod_macro = openmc.Macroscopic('gt_inmod')\n", - "gt_clad_macro = openmc.Macroscopic('gt_clad')\n", - "gt_outmod_macro = openmc.Macroscopic('gt_outmod')\n", - "\n", - "# Now define the materials\n", + "zircaloy_macro = openmc.Macroscopic('zircaloy')\n", + "water_macro = openmc.Macroscopic('water')\n", "\n", + "# Now re-define our materials to use the Multi-Group macroscopic data\n", + "# instead of the continuous-energy data.\n", "# 1.6 enriched fuel UO2\n", - "fuel = openmc.Material(name='1.6% Fuel UO2', material_id=1)\n", - "fuel.set_density('macro', 1.0)\n", + "fuel = openmc.Material(name='UO2', material_id=1)\n", "fuel.add_macroscopic(fuel_macro)\n", "\n", - "# 1.6 enriched fuel cladding\n", - "fuel_clad = openmc.Material(name='1.6% Fuel Clad', material_id=2)\n", - "fuel_clad.set_density('macro', 1.0)\n", - "fuel_clad.add_macroscopic(fuel_clad_macro)\n", + "# cladding\n", + "zircaloy = openmc.Material(name='Clad', material_id=2)\n", + "zircaloy.add_macroscopic(zircaloy_macro)\n", "\n", - "# 1.6 enriched fuel moderator\n", - "fuel_mod = openmc.Material(name='1.6% Fuel Water', material_id=3)\n", - "fuel_mod.set_density('macro', 1.0)\n", - "fuel_mod.add_macroscopic(fuel_mod_macro)\n", - "\n", - "# Guide Tube Inner Moderator\n", - "gt_inmod = openmc.Material(name='GT Inner Water', material_id=4)\n", - "gt_inmod.set_density('macro', 1.0)\n", - "gt_inmod.add_macroscopic(gt_inmod_macro)\n", - "\n", - "# Guide Tube Cladding\n", - "gt_clad = openmc.Material(name='GT Clad', material_id=5)\n", - "gt_clad.set_density('macro', 1.0)\n", - "gt_clad.add_macroscopic(gt_clad_macro)\n", - "\n", - "# Guide Tube Outer Moderator\n", - "gt_outmod = openmc.Material(name='GT Outer Water', material_id=6)\n", - "gt_outmod.set_density('macro', 1.0)\n", - "gt_outmod.add_macroscopic(gt_outmod_macro)\n", + "# moderator\n", + "water = openmc.Material(name='Water', material_id=3)\n", + "water.add_macroscopic(water_macro)\n", "\n", "# Finally, instantiate our Materials object\n", - "materials_file = openmc.Materials((fuel, fuel_clad, fuel_mod,\n", - " gt_inmod, gt_clad, gt_outmod))\n", + "materials_file = openmc.Materials((fuel, zircaloy, water))\n", "materials_file.default_xs = '2m'\n", "\n", "# Export to \"materials.xml\"\n", @@ -1473,98 +1002,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "\n", - "For our geometry files we will do the same as before but now we will be pointing at our newly created materials instead." - ] - }, - { - "cell_type": "code", - "execution_count": 33, - "metadata": { - "collapsed": false - }, - "outputs": [], - "source": [ - "# Create a Universe to encapsulate a fuel pin\n", - "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin', universe_id=10)\n", - "\n", - "# Create fuel Cell\n", - "fuel_cell = openmc.Cell(name='1.6% Fuel', cell_id=1)\n", - "fuel_cell.fill = fuel\n", - "fuel_cell.region = -fuel_outer_radius\n", - "fuel_pin_universe.add_cell(fuel_cell)\n", - "\n", - "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='1.6% Clad', cell_id=2)\n", - "clad_cell.fill = fuel_clad\n", - "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", - "fuel_pin_universe.add_cell(clad_cell)\n", - "\n", - "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='1.6% Moderator', cell_id=3)\n", - "moderator_cell.fill = fuel_mod\n", - "moderator_cell.region = +clad_outer_radius\n", - "fuel_pin_universe.add_cell(moderator_cell)\n", - "\n", - "# Create a Universe to encapsulate a control rod guide tube\n", - "guide_tube_universe = openmc.Universe(name='Guide Tube', universe_id=20)\n", - "\n", - "# Create guide tube Cell\n", - "guide_tube_cell = openmc.Cell(name='Guide Tube Water', cell_id=4)\n", - "guide_tube_cell.fill = gt_inmod\n", - "guide_tube_cell.region = -fuel_outer_radius\n", - "guide_tube_universe.add_cell(guide_tube_cell)\n", - "\n", - "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='Guide Clad', cell_id=5)\n", - "clad_cell.fill = gt_clad\n", - "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", - "guide_tube_universe.add_cell(clad_cell)\n", - "\n", - "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='Guide Tube Moderator', cell_id=6)\n", - "moderator_cell.fill = gt_outmod\n", - "moderator_cell.region = +clad_outer_radius\n", - "guide_tube_universe.add_cell(moderator_cell)\n", - "\n", - "# Create fuel assembly Lattice\n", - "assembly = openmc.RectLattice(name='1.6% Fuel Assembly', lattice_id=100)\n", - "assembly.dimension = (17, 17)\n", - "assembly.pitch = (1.26, 1.26)\n", - "assembly.lower_left = [-1.26 * 17. / 2.0] * 2\n", - "\n", - "# Create array indices for guide tube locations in lattice\n", - "template_x = np.array([5, 8, 11, 3, 13, 2, 5, 8, 11, 14, 2, 5, 8,\n", - " 11, 14, 2, 5, 8, 11, 14, 3, 13, 5, 8, 11])\n", - "template_y = np.array([2, 2, 2, 3, 3, 5, 5, 5, 5, 5, 8, 8, 8, 8,\n", - " 8, 11, 11, 11, 11, 11, 13, 13, 14, 14, 14])\n", - "\n", - "# Initialize an empty 17x17 array of the lattice universes\n", - "universes = np.empty((17, 17), dtype=openmc.Universe)\n", - "\n", - "# Fill the array with the fuel pin and guide tube universes\n", - "universes[:,:] = fuel_pin_universe\n", - "universes[template_x, template_y] = guide_tube_universe\n", - "\n", - "# Store the array of universes in the lattice\n", - "assembly.universes = universes\n", - "\n", - "# Create root Cell\n", - "root_cell = openmc.Cell(name='root cell', cell_id=0)\n", - "root_cell.fill = assembly\n", - "\n", - "# Add boundary planes\n", - "root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z\n", - "\n", - "# Create root Universe\n", - "root_universe = openmc.Universe(universe_id=0, name='root universe')\n", - "root_universe.add_cell(root_cell)\n", - "\n", - "# Create Geometry and set root Universe\n", - "geometry = openmc.Geometry()\n", - "geometry.root_universe = root_universe\n", - "# Export to \"geometry.xml\"\n", - "geometry.export_to_xml()" + "No geometry file neeeds to be written as the continuous-energy file is correctly defined for the multi-group case as well." ] }, { @@ -1577,7 +1015,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 33, "metadata": { "collapsed": true }, @@ -1602,9 +1040,10 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 34, "metadata": { - "collapsed": false + "collapsed": false, + "scrolled": true }, "outputs": [ { @@ -1628,7 +1067,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-12 21:19:25\n", + " Date/Time: 2016-05-13 22:30:02\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1643,11 +1082,8 @@ " Building neighboring cells lists for each surface...\n", " Loading Cross Section Data...\n", " Loading fuel.2m Data...\n", - " Loading fuel_clad.2m Data...\n", - " Loading fuel_mod.2m Data...\n", - " Loading gt_inmod.2m Data...\n", - " Loading gt_clad.2m Data...\n", - " Loading gt_outmod.2m Data...\n", + " Loading zircaloy.2m Data...\n", + " Loading water.2m Data...\n", " Initializing source particles...\n", "\n", " ===========================================================================\n", @@ -1656,507 +1092,57 @@ "\n", " Bat./Gen. k Average k \n", " ========= ======== ==================== \n", - " 1/1 1.01702 \n", - " 2/1 0.99463 \n", - " 3/1 1.02321 \n", - " 4/1 0.98628 \n", - " 5/1 1.03122 \n", - " 6/1 1.00774 \n", - " 7/1 1.05616 \n", - " 8/1 1.03051 \n", - " 9/1 1.02321 \n", - " 10/1 1.04380 \n", - " 11/1 1.05837 \n", - " 12/1 1.01514 1.03676 +/- 0.02161\n", - " 13/1 1.06720 1.04690 +/- 0.01608\n", - " 14/1 1.01696 1.03942 +/- 0.01361\n", - " 15/1 1.03549 1.03863 +/- 0.01057\n", - " 16/1 1.01599 1.03486 +/- 0.00942\n", - " 17/1 1.03070 1.03427 +/- 0.00799\n", - " 18/1 1.03778 1.03470 +/- 0.00693\n", - " 19/1 1.03042 1.03423 +/- 0.00613\n", - " 20/1 1.01047 1.03185 +/- 0.00598\n", - " 21/1 1.03251 1.03191 +/- 0.00541\n", - " 22/1 1.02047 1.03096 +/- 0.00503\n", - " 23/1 1.01729 1.02991 +/- 0.00474\n", - " 24/1 1.02948 1.02988 +/- 0.00439\n", - " 25/1 1.01963 1.02919 +/- 0.00414\n", - " 26/1 1.00626 1.02776 +/- 0.00413\n", - " 27/1 1.04531 1.02879 +/- 0.00402\n", - " 28/1 0.99936 1.02716 +/- 0.00412\n", - " 29/1 1.04497 1.02809 +/- 0.00401\n", - " 30/1 1.02429 1.02790 +/- 0.00381\n", - " 31/1 1.05112 1.02901 +/- 0.00379\n", - " 32/1 1.01843 1.02853 +/- 0.00365\n", - " 33/1 1.04478 1.02924 +/- 0.00355\n", - " 34/1 1.01719 1.02873 +/- 0.00344\n", - " 35/1 0.99873 1.02753 +/- 0.00351\n", - " 36/1 1.00054 1.02649 +/- 0.00353\n", - " 37/1 1.03986 1.02699 +/- 0.00343\n", - " 38/1 1.02243 1.02683 +/- 0.00331\n", - " 39/1 1.02744 1.02685 +/- 0.00319\n", - " 40/1 1.01174 1.02634 +/- 0.00313\n", - " 41/1 1.04973 1.02710 +/- 0.00312\n", - " 42/1 0.99564 1.02612 +/- 0.00317\n", - " 43/1 1.03022 1.02624 +/- 0.00308\n", - " 44/1 1.03526 1.02650 +/- 0.00300\n", - " 45/1 1.02143 1.02636 +/- 0.00292\n", - " 46/1 1.03264 1.02653 +/- 0.00284\n", - " 47/1 1.03868 1.02686 +/- 0.00278\n", - " 48/1 1.02385 1.02678 +/- 0.00271\n", - " 49/1 1.03897 1.02710 +/- 0.00266\n", - " 50/1 1.01267 1.02674 +/- 0.00261\n", - " 51/1 0.99683 1.02601 +/- 0.00265\n", - " 52/1 1.04189 1.02638 +/- 0.00261\n", - " 53/1 1.02871 1.02644 +/- 0.00255\n", - " 54/1 1.02564 1.02642 +/- 0.00250\n", - " 55/1 1.02955 1.02649 +/- 0.00244\n", - " 56/1 1.02390 1.02643 +/- 0.00239\n", - " 57/1 1.03342 1.02658 +/- 0.00234\n", - " 58/1 1.01430 1.02633 +/- 0.00231\n", - " 59/1 0.99242 1.02563 +/- 0.00236\n", - " 60/1 1.00442 1.02521 +/- 0.00235\n", - " 61/1 1.03870 1.02547 +/- 0.00232\n", - " 62/1 1.02146 1.02540 +/- 0.00228\n", - " 63/1 1.04782 1.02582 +/- 0.00227\n", - " 64/1 1.02872 1.02587 +/- 0.00223\n", - " 65/1 1.02420 1.02584 +/- 0.00219\n", - " 66/1 1.01974 1.02573 +/- 0.00215\n", - " 67/1 1.00774 1.02542 +/- 0.00214\n", - " 68/1 1.01323 1.02521 +/- 0.00211\n", - " 69/1 1.01468 1.02503 +/- 0.00208\n", - " 70/1 1.02869 1.02509 +/- 0.00205\n", - " 71/1 1.02284 1.02505 +/- 0.00202\n", - " 72/1 1.04815 1.02543 +/- 0.00202\n", - " 73/1 1.01119 1.02520 +/- 0.00200\n", - " 74/1 1.03314 1.02533 +/- 0.00197\n", - " 75/1 1.02333 1.02529 +/- 0.00194\n", - " 76/1 1.04030 1.02552 +/- 0.00193\n", - " 77/1 1.02537 1.02552 +/- 0.00190\n", - " 78/1 1.02875 1.02557 +/- 0.00187\n", - " 79/1 1.03588 1.02572 +/- 0.00185\n", - " 80/1 1.05250 1.02610 +/- 0.00186\n", - " 81/1 1.00477 1.02580 +/- 0.00186\n", - " 82/1 1.03903 1.02598 +/- 0.00184\n", - " 83/1 1.02378 1.02595 +/- 0.00182\n", - " 84/1 1.01107 1.02575 +/- 0.00180\n", - " 85/1 1.01550 1.02561 +/- 0.00178\n", - " 86/1 1.00540 1.02535 +/- 0.00178\n", - " 87/1 1.03056 1.02542 +/- 0.00176\n", - " 88/1 1.01742 1.02531 +/- 0.00174\n", - " 89/1 0.99730 1.02496 +/- 0.00175\n", - " 90/1 1.03569 1.02509 +/- 0.00174\n", - " 91/1 1.04514 1.02534 +/- 0.00173\n", - " 92/1 1.02757 1.02537 +/- 0.00171\n", - " 93/1 1.00610 1.02514 +/- 0.00171\n", - " 94/1 1.03576 1.02526 +/- 0.00169\n", - " 95/1 1.03732 1.02540 +/- 0.00168\n", - " 96/1 1.04784 1.02567 +/- 0.00168\n", - " 97/1 1.06507 1.02612 +/- 0.00172\n", - " 98/1 1.03673 1.02624 +/- 0.00170\n", - " 99/1 1.01270 1.02609 +/- 0.00169\n", - " 100/1 1.01980 1.02602 +/- 0.00167\n", - " 101/1 1.01357 1.02588 +/- 0.00166\n", - " 102/1 1.03125 1.02594 +/- 0.00164\n", - " 103/1 1.01527 1.02582 +/- 0.00163\n", - " 104/1 1.02403 1.02580 +/- 0.00161\n", - " 105/1 1.03435 1.02589 +/- 0.00160\n", - " 106/1 1.04113 1.02605 +/- 0.00159\n", - " 107/1 1.03291 1.02612 +/- 0.00157\n", - " 108/1 1.02478 1.02611 +/- 0.00156\n", - " 109/1 1.05814 1.02643 +/- 0.00158\n", - " 110/1 1.02647 1.02643 +/- 0.00156\n", - " 111/1 0.98951 1.02607 +/- 0.00159\n", - " 112/1 1.00739 1.02589 +/- 0.00158\n", - " 113/1 1.04165 1.02604 +/- 0.00157\n", - " 114/1 1.00047 1.02579 +/- 0.00158\n", - " 115/1 1.02550 1.02579 +/- 0.00156\n", - " 116/1 1.02408 1.02577 +/- 0.00155\n", - " 117/1 1.03110 1.02582 +/- 0.00153\n", - " 118/1 1.02874 1.02585 +/- 0.00152\n", - " 119/1 1.02348 1.02583 +/- 0.00151\n", - " 120/1 1.01969 1.02577 +/- 0.00149\n", - " 121/1 1.02312 1.02575 +/- 0.00148\n", - " 122/1 1.03261 1.02581 +/- 0.00147\n", - " 123/1 0.98394 1.02544 +/- 0.00150\n", - " 124/1 1.03771 1.02555 +/- 0.00149\n", - " 125/1 1.01857 1.02549 +/- 0.00148\n", - " 126/1 1.00066 1.02527 +/- 0.00148\n", - " 127/1 1.02372 1.02526 +/- 0.00147\n", - " 128/1 1.03307 1.02533 +/- 0.00146\n", - " 129/1 1.00889 1.02519 +/- 0.00145\n", - " 130/1 1.02053 1.02515 +/- 0.00144\n", - " 131/1 1.00943 1.02502 +/- 0.00144\n", - " 132/1 1.07225 1.02541 +/- 0.00148\n", - " 133/1 1.04068 1.02553 +/- 0.00147\n", - " 134/1 1.03509 1.02561 +/- 0.00146\n", - " 135/1 1.01250 1.02550 +/- 0.00145\n", - " 136/1 1.02179 1.02547 +/- 0.00144\n", - " 137/1 1.05685 1.02572 +/- 0.00145\n", - " 138/1 1.04217 1.02585 +/- 0.00144\n", - " 139/1 1.02793 1.02586 +/- 0.00143\n", - " 140/1 1.01207 1.02576 +/- 0.00143\n", - " 141/1 1.03445 1.02582 +/- 0.00142\n", - " 142/1 1.03579 1.02590 +/- 0.00141\n", - " 143/1 1.00786 1.02576 +/- 0.00140\n", - " 144/1 0.99089 1.02550 +/- 0.00142\n", - " 145/1 1.02617 1.02551 +/- 0.00141\n", - " 146/1 1.01691 1.02545 +/- 0.00140\n", - " 147/1 1.00692 1.02531 +/- 0.00139\n", - " 148/1 0.97702 1.02496 +/- 0.00143\n", - " 149/1 1.04002 1.02507 +/- 0.00142\n", - " 150/1 1.01262 1.02498 +/- 0.00141\n", - " 151/1 1.03613 1.02506 +/- 0.00141\n", - " 152/1 1.02920 1.02509 +/- 0.00140\n", - " 153/1 1.02199 1.02507 +/- 0.00139\n", - " 154/1 1.03421 1.02513 +/- 0.00138\n", - " 155/1 1.05882 1.02536 +/- 0.00139\n", - " 156/1 1.02649 1.02537 +/- 0.00138\n", - " 157/1 1.01933 1.02533 +/- 0.00137\n", - " 158/1 1.04269 1.02545 +/- 0.00137\n", - " 159/1 0.99604 1.02525 +/- 0.00137\n", - " 160/1 1.04748 1.02540 +/- 0.00137\n", - " 161/1 1.00501 1.02526 +/- 0.00137\n", - " 162/1 1.00550 1.02513 +/- 0.00137\n", - " 163/1 1.00115 1.02498 +/- 0.00137\n", - " 164/1 1.02283 1.02496 +/- 0.00136\n", - " 165/1 1.01964 1.02493 +/- 0.00135\n", - " 166/1 1.02287 1.02491 +/- 0.00134\n", - " 167/1 1.05498 1.02511 +/- 0.00134\n", - " 168/1 1.05267 1.02528 +/- 0.00135\n", - " 169/1 1.00474 1.02515 +/- 0.00135\n", - " 170/1 1.03469 1.02521 +/- 0.00134\n", - " 171/1 1.02499 1.02521 +/- 0.00133\n", - " 172/1 1.03961 1.02530 +/- 0.00132\n", - " 173/1 1.01240 1.02522 +/- 0.00132\n", - " 174/1 1.00762 1.02511 +/- 0.00132\n", - " 175/1 1.00200 1.02497 +/- 0.00131\n", - " 176/1 1.01449 1.02491 +/- 0.00131\n", - " 177/1 1.01111 1.02483 +/- 0.00130\n", - " 178/1 1.01208 1.02475 +/- 0.00130\n", - " 179/1 1.03304 1.02480 +/- 0.00129\n", - " 180/1 1.04504 1.02492 +/- 0.00129\n", - " 181/1 1.03476 1.02498 +/- 0.00128\n", - " 182/1 1.02124 1.02495 +/- 0.00128\n", - " 183/1 0.98855 1.02474 +/- 0.00128\n", - " 184/1 1.04689 1.02487 +/- 0.00128\n", - " 185/1 1.00618 1.02476 +/- 0.00128\n", - " 186/1 1.02012 1.02474 +/- 0.00127\n", - " 187/1 1.00162 1.02461 +/- 0.00127\n", - " 188/1 1.03269 1.02465 +/- 0.00127\n", - " 189/1 1.04772 1.02478 +/- 0.00127\n", - " 190/1 1.01132 1.02471 +/- 0.00126\n", - " 191/1 1.02669 1.02472 +/- 0.00125\n", - " 192/1 1.01154 1.02464 +/- 0.00125\n", - " 193/1 1.05795 1.02483 +/- 0.00126\n", - " 194/1 1.01615 1.02478 +/- 0.00125\n", - " 195/1 1.03828 1.02485 +/- 0.00125\n", - " 196/1 1.00695 1.02476 +/- 0.00124\n", - " 197/1 1.04126 1.02484 +/- 0.00124\n", - " 198/1 1.02834 1.02486 +/- 0.00123\n", - " 199/1 1.01000 1.02478 +/- 0.00123\n", - " 200/1 0.99294 1.02462 +/- 0.00123\n", - " 201/1 1.00248 1.02450 +/- 0.00123\n", - " 202/1 1.03461 1.02455 +/- 0.00123\n", - " 203/1 1.06289 1.02475 +/- 0.00124\n", - " 204/1 1.03010 1.02478 +/- 0.00123\n", - " 205/1 1.04636 1.02489 +/- 0.00123\n", - " 206/1 1.05434 1.02504 +/- 0.00123\n", - " 207/1 1.03993 1.02512 +/- 0.00123\n", - " 208/1 1.02672 1.02512 +/- 0.00122\n", - " 209/1 1.04958 1.02525 +/- 0.00122\n", - " 210/1 0.99194 1.02508 +/- 0.00123\n", - " 211/1 1.01570 1.02503 +/- 0.00122\n", - " 212/1 1.04079 1.02511 +/- 0.00122\n", - " 213/1 1.02961 1.02513 +/- 0.00121\n", - " 214/1 1.03797 1.02520 +/- 0.00121\n", - " 215/1 1.03714 1.02526 +/- 0.00120\n", - " 216/1 1.03299 1.02529 +/- 0.00120\n", - " 217/1 1.00461 1.02519 +/- 0.00120\n", - " 218/1 1.02386 1.02519 +/- 0.00119\n", - " 219/1 1.01955 1.02516 +/- 0.00119\n", - " 220/1 1.04372 1.02525 +/- 0.00118\n", - " 221/1 1.01694 1.02521 +/- 0.00118\n", - " 222/1 0.99642 1.02507 +/- 0.00118\n", - " 223/1 1.00999 1.02500 +/- 0.00118\n", - " 224/1 1.02703 1.02501 +/- 0.00117\n", - " 225/1 1.00236 1.02491 +/- 0.00117\n", - " 226/1 1.02825 1.02492 +/- 0.00117\n", - " 227/1 1.04535 1.02502 +/- 0.00116\n", - " 228/1 1.01779 1.02498 +/- 0.00116\n", - " 229/1 1.01058 1.02492 +/- 0.00116\n", - " 230/1 1.00391 1.02482 +/- 0.00115\n", - " 231/1 1.05990 1.02498 +/- 0.00116\n", - " 232/1 1.01885 1.02495 +/- 0.00116\n", - " 233/1 1.03204 1.02498 +/- 0.00115\n", - " 234/1 0.99396 1.02485 +/- 0.00115\n", - " 235/1 1.01828 1.02482 +/- 0.00115\n", - " 236/1 1.08225 1.02507 +/- 0.00117\n", - " 237/1 1.00335 1.02498 +/- 0.00117\n", - " 238/1 1.03097 1.02500 +/- 0.00117\n", - " 239/1 1.01738 1.02497 +/- 0.00116\n", - " 240/1 1.02261 1.02496 +/- 0.00116\n", - " 241/1 1.02814 1.02497 +/- 0.00115\n", - " 242/1 1.01158 1.02491 +/- 0.00115\n", - " 243/1 1.03507 1.02496 +/- 0.00114\n", - " 244/1 1.01914 1.02493 +/- 0.00114\n", - " 245/1 1.04555 1.02502 +/- 0.00114\n", - " 246/1 1.02459 1.02502 +/- 0.00113\n", - " 247/1 1.05827 1.02516 +/- 0.00114\n", - " 248/1 1.02549 1.02516 +/- 0.00113\n", - " 249/1 1.03354 1.02520 +/- 0.00113\n", - " 250/1 1.04186 1.02526 +/- 0.00113\n", - " 251/1 1.00466 1.02518 +/- 0.00112\n", - " 252/1 0.99065 1.02504 +/- 0.00113\n", - " 253/1 1.03065 1.02506 +/- 0.00112\n", - " 254/1 1.02167 1.02505 +/- 0.00112\n", - " 255/1 1.01700 1.02501 +/- 0.00112\n", - " 256/1 1.03619 1.02506 +/- 0.00111\n", - " 257/1 1.01833 1.02503 +/- 0.00111\n", - " 258/1 1.02211 1.02502 +/- 0.00110\n", - " 259/1 1.04348 1.02509 +/- 0.00110\n", - " 260/1 1.03444 1.02513 +/- 0.00110\n", - " 261/1 1.05597 1.02525 +/- 0.00110\n", - " 262/1 1.02085 1.02524 +/- 0.00110\n", - " 263/1 1.00552 1.02516 +/- 0.00109\n", - " 264/1 1.03976 1.02522 +/- 0.00109\n", - " 265/1 1.02810 1.02523 +/- 0.00109\n", - " 266/1 1.00911 1.02516 +/- 0.00108\n", - " 267/1 1.01963 1.02514 +/- 0.00108\n", - " 268/1 1.03732 1.02519 +/- 0.00108\n", - " 269/1 1.02422 1.02519 +/- 0.00107\n", - " 270/1 1.01546 1.02515 +/- 0.00107\n", - " 271/1 1.05488 1.02526 +/- 0.00107\n", - " 272/1 1.01709 1.02523 +/- 0.00107\n", - " 273/1 1.05629 1.02535 +/- 0.00107\n", - " 274/1 1.03864 1.02540 +/- 0.00107\n", - " 275/1 1.01472 1.02536 +/- 0.00106\n", - " 276/1 1.03425 1.02539 +/- 0.00106\n", - " 277/1 1.00663 1.02532 +/- 0.00106\n", - " 278/1 1.03326 1.02535 +/- 0.00106\n", - " 279/1 1.02571 1.02535 +/- 0.00105\n", - " 280/1 1.00525 1.02528 +/- 0.00105\n", - " 281/1 1.00451 1.02520 +/- 0.00105\n", - " 282/1 1.04016 1.02526 +/- 0.00105\n", - " 283/1 0.98343 1.02510 +/- 0.00105\n", - " 284/1 1.04843 1.02519 +/- 0.00105\n", - " 285/1 1.01807 1.02516 +/- 0.00105\n", - " 286/1 1.02393 1.02516 +/- 0.00105\n", - " 287/1 1.01851 1.02514 +/- 0.00104\n", - " 288/1 1.03976 1.02519 +/- 0.00104\n", - " 289/1 1.03153 1.02521 +/- 0.00104\n", - " 290/1 1.00416 1.02514 +/- 0.00104\n", - " 291/1 1.01426 1.02510 +/- 0.00103\n", - " 292/1 1.02583 1.02510 +/- 0.00103\n", - " 293/1 1.01680 1.02507 +/- 0.00103\n", - " 294/1 1.04578 1.02514 +/- 0.00103\n", - " 295/1 1.03162 1.02517 +/- 0.00102\n", - " 296/1 1.01682 1.02514 +/- 0.00102\n", - " 297/1 1.00488 1.02507 +/- 0.00102\n", - " 298/1 1.03057 1.02508 +/- 0.00101\n", - " 299/1 1.01126 1.02504 +/- 0.00101\n", - " 300/1 1.03528 1.02507 +/- 0.00101\n", - " 301/1 1.05548 1.02518 +/- 0.00101\n", - " 302/1 1.02994 1.02519 +/- 0.00101\n", - " 303/1 1.03010 1.02521 +/- 0.00100\n", - " 304/1 1.04031 1.02526 +/- 0.00100\n", - " 305/1 1.05866 1.02537 +/- 0.00101\n", - " 306/1 1.03602 1.02541 +/- 0.00100\n", - " 307/1 1.01362 1.02537 +/- 0.00100\n", - " 308/1 1.01318 1.02533 +/- 0.00100\n", - " 309/1 1.04262 1.02539 +/- 0.00100\n", - " 310/1 1.01626 1.02536 +/- 0.00099\n", - " 311/1 1.00285 1.02528 +/- 0.00099\n", - " 312/1 0.98155 1.02514 +/- 0.00100\n", - " 313/1 1.05649 1.02524 +/- 0.00100\n", - " 314/1 1.00960 1.02519 +/- 0.00100\n", - " 315/1 1.05350 1.02528 +/- 0.00100\n", - " 316/1 1.03842 1.02533 +/- 0.00100\n", - " 317/1 1.01394 1.02529 +/- 0.00100\n", - " 318/1 1.01830 1.02527 +/- 0.00099\n", - " 319/1 1.02050 1.02525 +/- 0.00099\n", - " 320/1 1.03402 1.02528 +/- 0.00099\n", - " 321/1 1.04547 1.02534 +/- 0.00099\n", - " 322/1 1.02579 1.02534 +/- 0.00098\n", - " 323/1 1.01922 1.02533 +/- 0.00098\n", - " 324/1 1.01050 1.02528 +/- 0.00098\n", - " 325/1 1.01426 1.02524 +/- 0.00098\n", - " 326/1 1.03283 1.02527 +/- 0.00097\n", - " 327/1 1.03859 1.02531 +/- 0.00097\n", - " 328/1 1.01536 1.02528 +/- 0.00097\n", - " 329/1 1.03149 1.02530 +/- 0.00097\n", - " 330/1 1.04328 1.02535 +/- 0.00096\n", - " 331/1 1.01949 1.02534 +/- 0.00096\n", - " 332/1 1.02319 1.02533 +/- 0.00096\n", - " 333/1 1.01704 1.02530 +/- 0.00096\n", - " 334/1 1.02691 1.02531 +/- 0.00095\n", - " 335/1 1.03188 1.02533 +/- 0.00095\n", - " 336/1 1.03107 1.02535 +/- 0.00095\n", - " 337/1 1.02410 1.02534 +/- 0.00094\n", - " 338/1 0.99917 1.02526 +/- 0.00094\n", - " 339/1 1.03593 1.02529 +/- 0.00094\n", - " 340/1 1.02286 1.02529 +/- 0.00094\n", - " 341/1 1.04154 1.02534 +/- 0.00094\n", - " 342/1 1.01664 1.02531 +/- 0.00094\n", - " 343/1 1.01041 1.02527 +/- 0.00093\n", - " 344/1 1.02033 1.02525 +/- 0.00093\n", - " 345/1 1.03137 1.02527 +/- 0.00093\n", - " 346/1 1.02162 1.02526 +/- 0.00093\n", - " 347/1 1.00835 1.02521 +/- 0.00092\n", - " 348/1 1.01168 1.02517 +/- 0.00092\n", - " 349/1 1.01168 1.02513 +/- 0.00092\n", - " 350/1 1.03509 1.02516 +/- 0.00092\n", - " 351/1 1.01883 1.02514 +/- 0.00092\n", - " 352/1 1.04314 1.02519 +/- 0.00091\n", - " 353/1 0.99067 1.02509 +/- 0.00092\n", - " 354/1 1.03100 1.02511 +/- 0.00091\n", - " 355/1 1.01664 1.02508 +/- 0.00091\n", - " 356/1 1.02193 1.02507 +/- 0.00091\n", - " 357/1 1.03213 1.02509 +/- 0.00091\n", - " 358/1 1.00555 1.02504 +/- 0.00091\n", - " 359/1 1.04849 1.02511 +/- 0.00091\n", - " 360/1 1.02174 1.02510 +/- 0.00090\n", - " 361/1 1.05064 1.02517 +/- 0.00090\n", - " 362/1 1.05274 1.02525 +/- 0.00091\n", - " 363/1 1.00932 1.02520 +/- 0.00090\n", - " 364/1 1.03400 1.02523 +/- 0.00090\n", - " 365/1 1.00149 1.02516 +/- 0.00090\n", - " 366/1 1.01631 1.02514 +/- 0.00090\n", - " 367/1 1.03928 1.02517 +/- 0.00090\n", - " 368/1 1.01318 1.02514 +/- 0.00090\n", - " 369/1 1.04610 1.02520 +/- 0.00090\n", - " 370/1 1.04338 1.02525 +/- 0.00089\n", - " 371/1 1.01638 1.02523 +/- 0.00089\n", - " 372/1 1.04056 1.02527 +/- 0.00089\n", - " 373/1 1.00090 1.02520 +/- 0.00089\n", - " 374/1 1.01261 1.02517 +/- 0.00089\n", - " 375/1 1.03919 1.02520 +/- 0.00089\n", - " 376/1 0.99900 1.02513 +/- 0.00089\n", - " 377/1 1.00168 1.02507 +/- 0.00089\n", - " 378/1 0.99476 1.02499 +/- 0.00089\n", - " 379/1 1.04960 1.02505 +/- 0.00089\n", - " 380/1 0.99797 1.02498 +/- 0.00089\n", - " 381/1 1.04956 1.02505 +/- 0.00089\n", - " 382/1 1.02803 1.02505 +/- 0.00089\n", - " 383/1 0.99388 1.02497 +/- 0.00089\n", - " 384/1 1.00767 1.02492 +/- 0.00089\n", - " 385/1 1.00856 1.02488 +/- 0.00089\n", - " 386/1 1.02997 1.02489 +/- 0.00088\n", - " 387/1 0.97841 1.02477 +/- 0.00089\n", - " 388/1 0.99712 1.02470 +/- 0.00089\n", - " 389/1 0.99072 1.02461 +/- 0.00089\n", - " 390/1 1.02439 1.02461 +/- 0.00089\n", - " 391/1 1.02769 1.02462 +/- 0.00089\n", - " 392/1 1.02205 1.02461 +/- 0.00089\n", - " 393/1 1.03702 1.02464 +/- 0.00088\n", - " 394/1 1.00274 1.02458 +/- 0.00088\n", - " 395/1 1.00131 1.02452 +/- 0.00088\n", - " 396/1 1.00130 1.02446 +/- 0.00088\n", - " 397/1 1.00472 1.02441 +/- 0.00088\n", - " 398/1 1.00724 1.02437 +/- 0.00088\n", - " 399/1 1.03061 1.02438 +/- 0.00088\n", - " 400/1 0.99651 1.02431 +/- 0.00088\n", - " 401/1 0.99290 1.02423 +/- 0.00088\n", - " 402/1 1.02166 1.02423 +/- 0.00088\n", - " 403/1 1.01691 1.02421 +/- 0.00088\n", - " 404/1 1.00492 1.02416 +/- 0.00088\n", - " 405/1 1.00663 1.02411 +/- 0.00088\n", - " 406/1 1.01865 1.02410 +/- 0.00087\n", - " 407/1 1.02717 1.02411 +/- 0.00087\n", - " 408/1 1.01793 1.02409 +/- 0.00087\n", - " 409/1 1.02606 1.02410 +/- 0.00087\n", - " 410/1 1.03809 1.02413 +/- 0.00087\n", - " 411/1 1.03780 1.02417 +/- 0.00086\n", - " 412/1 1.02782 1.02418 +/- 0.00086\n", - " 413/1 1.03077 1.02419 +/- 0.00086\n", - " 414/1 1.00651 1.02415 +/- 0.00086\n", - " 415/1 1.05594 1.02423 +/- 0.00086\n", - " 416/1 0.99558 1.02416 +/- 0.00086\n", - " 417/1 1.00689 1.02411 +/- 0.00086\n", - " 418/1 1.02932 1.02413 +/- 0.00086\n", - " 419/1 1.03552 1.02415 +/- 0.00086\n", - " 420/1 1.03735 1.02419 +/- 0.00085\n", - " 421/1 1.02402 1.02419 +/- 0.00085\n", - " 422/1 1.04227 1.02423 +/- 0.00085\n", - " 423/1 1.03087 1.02425 +/- 0.00085\n", - " 424/1 1.04363 1.02429 +/- 0.00085\n", - " 425/1 1.02676 1.02430 +/- 0.00085\n", - " 426/1 1.03739 1.02433 +/- 0.00085\n", - " 427/1 1.02977 1.02434 +/- 0.00084\n", - " 428/1 1.02547 1.02435 +/- 0.00084\n", - " 429/1 1.03552 1.02437 +/- 0.00084\n", - " 430/1 1.04282 1.02442 +/- 0.00084\n", - " 431/1 1.03171 1.02443 +/- 0.00084\n", - " 432/1 1.01030 1.02440 +/- 0.00084\n", - " 433/1 1.04168 1.02444 +/- 0.00084\n", - " 434/1 0.98994 1.02436 +/- 0.00084\n", - " 435/1 0.98166 1.02426 +/- 0.00084\n", - " 436/1 1.00178 1.02421 +/- 0.00084\n", - " 437/1 1.03801 1.02424 +/- 0.00084\n", - " 438/1 1.02099 1.02423 +/- 0.00084\n", - " 439/1 1.01305 1.02421 +/- 0.00084\n", - " 440/1 1.02286 1.02420 +/- 0.00083\n", - " 441/1 1.03697 1.02423 +/- 0.00083\n", - " 442/1 0.99050 1.02415 +/- 0.00083\n", - " 443/1 1.02238 1.02415 +/- 0.00083\n", - " 444/1 1.05188 1.02421 +/- 0.00083\n", - " 445/1 1.03150 1.02423 +/- 0.00083\n", - " 446/1 1.01071 1.02420 +/- 0.00083\n", - " 447/1 1.03713 1.02423 +/- 0.00083\n", - " 448/1 1.03631 1.02426 +/- 0.00083\n", - " 449/1 1.02968 1.02427 +/- 0.00083\n", - " 450/1 1.03031 1.02428 +/- 0.00082\n", - " 451/1 1.02161 1.02428 +/- 0.00082\n", - " 452/1 0.99036 1.02420 +/- 0.00082\n", - " 453/1 1.02581 1.02420 +/- 0.00082\n", - " 454/1 1.03140 1.02422 +/- 0.00082\n", - " 455/1 1.01962 1.02421 +/- 0.00082\n", - " 456/1 1.00680 1.02417 +/- 0.00082\n", - " 457/1 1.00178 1.02412 +/- 0.00082\n", - " 458/1 1.02306 1.02412 +/- 0.00082\n", - " 459/1 1.02653 1.02412 +/- 0.00081\n", - " 460/1 1.02934 1.02413 +/- 0.00081\n", - " 461/1 1.00872 1.02410 +/- 0.00081\n", - " 462/1 1.00012 1.02405 +/- 0.00081\n", - " 463/1 0.99057 1.02397 +/- 0.00081\n", - " 464/1 1.02353 1.02397 +/- 0.00081\n", - " 465/1 1.01402 1.02395 +/- 0.00081\n", - " 466/1 1.01651 1.02393 +/- 0.00081\n", - " 467/1 1.01024 1.02390 +/- 0.00081\n", - " 468/1 1.02504 1.02391 +/- 0.00080\n", - " 469/1 1.00891 1.02387 +/- 0.00080\n", - " 470/1 1.04038 1.02391 +/- 0.00080\n", - " 471/1 1.04346 1.02395 +/- 0.00080\n", - " 472/1 1.02634 1.02396 +/- 0.00080\n", - " 473/1 1.01207 1.02393 +/- 0.00080\n", - " 474/1 1.00787 1.02390 +/- 0.00080\n", - " 475/1 1.03591 1.02392 +/- 0.00080\n", - " 476/1 1.04257 1.02396 +/- 0.00080\n", - " 477/1 1.00536 1.02392 +/- 0.00079\n", - " 478/1 1.07545 1.02403 +/- 0.00080\n", - " 479/1 1.02306 1.02403 +/- 0.00080\n", - " 480/1 1.02733 1.02404 +/- 0.00080\n", - " 481/1 1.00990 1.02401 +/- 0.00080\n", - " 482/1 0.99031 1.02394 +/- 0.00080\n", - " 483/1 0.98006 1.02384 +/- 0.00080\n", - " 484/1 1.05635 1.02391 +/- 0.00080\n", - " 485/1 1.02410 1.02391 +/- 0.00080\n", - " 486/1 1.01227 1.02389 +/- 0.00080\n", - " 487/1 1.00614 1.02385 +/- 0.00080\n", - " 488/1 1.01837 1.02384 +/- 0.00080\n", - " 489/1 1.02565 1.02384 +/- 0.00080\n", - " 490/1 1.00530 1.02381 +/- 0.00079\n", - " 491/1 1.01958 1.02380 +/- 0.00079\n", - " 492/1 1.04490 1.02384 +/- 0.00079\n", - " 493/1 1.02567 1.02384 +/- 0.00079\n", - " 494/1 1.03865 1.02387 +/- 0.00079\n", - " 495/1 1.03990 1.02391 +/- 0.00079\n", - " 496/1 0.98352 1.02382 +/- 0.00079\n", - " 497/1 1.00909 1.02379 +/- 0.00079\n", - " 498/1 1.03661 1.02382 +/- 0.00079\n", - " 499/1 1.04423 1.02386 +/- 0.00079\n", - " 500/1 1.06406 1.02394 +/- 0.00079\n", - " Creating state point statepoint.500.h5...\n", + " 1/1 1.02073 \n", + " 2/1 1.04004 \n", + " 3/1 1.02324 \n", + " 4/1 1.01690 \n", + " 5/1 1.03702 \n", + " 6/1 1.01796 \n", + " 7/1 1.01779 \n", + " 8/1 1.02764 \n", + " 9/1 1.03324 \n", + " 10/1 1.01465 \n", + " 11/1 1.02268 \n", + " 12/1 1.01598 1.01933 +/- 0.00335\n", + " 13/1 1.01993 1.01953 +/- 0.00194\n", + " 14/1 1.01779 1.01910 +/- 0.00144\n", + " 15/1 1.01014 1.01731 +/- 0.00211\n", + " 16/1 1.04059 1.02119 +/- 0.00425\n", + " 17/1 1.04877 1.02513 +/- 0.00533\n", + " 18/1 1.05504 1.02887 +/- 0.00594\n", + " 19/1 1.02601 1.02855 +/- 0.00525\n", + " 20/1 1.04347 1.03004 +/- 0.00493\n", + " 21/1 1.01703 1.02886 +/- 0.00461\n", + " 22/1 1.02628 1.02864 +/- 0.00421\n", + " 23/1 1.02598 1.02844 +/- 0.00388\n", + " 24/1 1.05341 1.03022 +/- 0.00401\n", + " 25/1 1.02201 1.02967 +/- 0.00377\n", + " 26/1 1.00758 1.02829 +/- 0.00379\n", + " 27/1 1.00720 1.02705 +/- 0.00377\n", + " 28/1 1.03098 1.02727 +/- 0.00356\n", + " 29/1 1.03022 1.02743 +/- 0.00337\n", + " 30/1 1.01694 1.02690 +/- 0.00324\n", + " 31/1 0.99064 1.02518 +/- 0.00353\n", + " 32/1 0.99495 1.02380 +/- 0.00364\n", + " 33/1 1.03220 1.02417 +/- 0.00350\n", + " 34/1 1.02399 1.02416 +/- 0.00335\n", + " 35/1 1.03048 1.02441 +/- 0.00322\n", + " 36/1 1.05360 1.02553 +/- 0.00329\n", + " 37/1 1.05030 1.02645 +/- 0.00330\n", + " 38/1 1.04167 1.02699 +/- 0.00322\n", + " 39/1 1.04406 1.02758 +/- 0.00317\n", + " 40/1 1.01169 1.02705 +/- 0.00310\n", + " 41/1 1.00191 1.02624 +/- 0.00311\n", + " 42/1 1.02729 1.02628 +/- 0.00301\n", + " 43/1 1.02263 1.02616 +/- 0.00292\n", + " 44/1 1.05344 1.02697 +/- 0.00295\n", + " 45/1 1.03607 1.02723 +/- 0.00287\n", + " 46/1 1.00357 1.02657 +/- 0.00287\n", + " 47/1 1.03353 1.02676 +/- 0.00279\n", + " 48/1 1.03817 1.02706 +/- 0.00274\n", + " 49/1 1.01454 1.02674 +/- 0.00269\n", + " 50/1 0.99860 1.02603 +/- 0.00271\n", + " Creating state point statepoint.50.h5...\n", "\n", " ===========================================================================\n", " ======================> SIMULATION FINISHED <======================\n", @@ -2165,27 +1151,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 5.3000E-02 seconds\n", - " Reading cross sections = 5.0000E-03 seconds\n", - " Total time in simulation = 1.8631E+02 seconds\n", - " Time in transport only = 1.8590E+02 seconds\n", - " Time in inactive batches = 1.1710E+00 seconds\n", - " Time in active batches = 1.8514E+02 seconds\n", - " Time synchronizing fission bank = 7.3000E-02 seconds\n", - " Sampling source sites = 5.1000E-02 seconds\n", - " SEND/RECV source sites = 2.2000E-02 seconds\n", - " Time accumulating tallies = 4.0000E-03 seconds\n", + " Total time for initialization = 3.7000E-02 seconds\n", + " Reading cross sections = 4.0000E-03 seconds\n", + " Total time in simulation = 1.2661E+01 seconds\n", + " Time in transport only = 1.2600E+01 seconds\n", + " Time in inactive batches = 1.1370E+00 seconds\n", + " Time in active batches = 1.1524E+01 seconds\n", + " Time synchronizing fission bank = 7.0000E-03 seconds\n", + " Sampling source sites = 5.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.8637E+02 seconds\n", - " Calculation Rate (inactive) = 42698.5 neutrons/second\n", - " Calculation Rate (active) = 13233.2 neutrons/second\n", + " Total time elapsed = 1.2707E+01 seconds\n", + " Calculation Rate (inactive) = 43975.4 neutrons/second\n", + " Calculation Rate (active) = 17355.1 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02403 +/- 0.00071\n", - " k-effective (Track-length) = 1.02394 +/- 0.00079\n", - " k-effective (Absorption) = 1.02539 +/- 0.00044\n", - " Combined k-effective = 1.02518 +/- 0.00042\n", + " k-effective (Collision) = 1.02471 +/- 0.00243\n", + " k-effective (Track-length) = 1.02603 +/- 0.00271\n", + " k-effective (Absorption) = 1.02312 +/- 0.00182\n", + " Combined k-effective = 1.02387 +/- 0.00172\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -2196,7 +1182,7 @@ "0" ] }, - "execution_count": 35, + "execution_count": 34, "metadata": {}, "output_type": "execute_result" } @@ -2219,7 +1205,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 35, "metadata": { "collapsed": false }, @@ -2239,7 +1225,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 36, "metadata": { "collapsed": true }, @@ -2257,7 +1243,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 37, "metadata": { "collapsed": false }, @@ -2266,9 +1252,9 @@ "name": "stdout", "output_type": "stream", "text": [ - "Continuous-Energy keff = 1.025194\n", - "Multi-Group keff = 1.025183\n", - "bias [pcm]: 1.1\n" + "Continuous-Energy keff = 1.024295\n", + "Multi-Group keff = 1.023875\n", + "bias [pcm]: 42.0\n" ] } ], @@ -2284,7 +1270,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We see quite good agreement with only an 1 pcm difference between the two. While these results are quite favorable, due to the high degree of approximations inherent in practical application of multi-group theory, one should not expect results of such fidelity always for multi-group Monte Carlo calculations." + "We see quite good agreement with only a 42 pcm difference between the two methods. Due to the high degree of approximations inherent in practical application of multi-group theory, one should not expect results of such high fidelity always for multi-group Monte Carlo calculations." ] }, { @@ -2305,7 +1291,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -2313,39 +1299,39 @@ "source": [ "# Get the OpenMC fission rate mesh tally data\n", "mg_mesh_tally = mgsp.get_tally(name='mesh tally')\n", - "mgopenmc_fission_rates = mg_mesh_tally.get_values(scores=['fission'])\n", + "mg_fission_rates = mg_mesh_tally.get_values(scores=['fission'])\n", "\n", "# Reshape array to 2D for plotting\n", - "mgopenmc_fission_rates.shape = (17,17)\n", + "mg_fission_rates.shape = (17,17)\n", "\n", "# Normalize to the average pin power\n", - "mgopenmc_fission_rates /= np.mean(mgopenmc_fission_rates)" + "mg_fission_rates /= np.mean(mg_fission_rates)" ] }, { "cell_type": "markdown", "metadata": {}, "source": [ - "Now we can do the same for the Multi-Group results." + "Now we can do the same for the Continuous-Energy results." ] }, { "cell_type": "code", - "execution_count": 40, + "execution_count": 39, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ "# Get the OpenMC fission rate mesh tally data\n", - "mesh_tally = sp.get_tally(name='mesh tally')\n", - "openmc_fission_rates = mesh_tally.get_values(scores=['fission'])\n", + "ce_mesh_tally = sp.get_tally(name='mesh tally')\n", + "ce_fission_rates = ce_mesh_tally.get_values(scores=['fission'])\n", "\n", "# Reshape array to 2D for plotting\n", - "openmc_fission_rates.shape = (17,17)\n", + "ce_fission_rates.shape = (17,17)\n", "\n", "# Normalize to the average pin power\n", - "openmc_fission_rates /= np.mean(openmc_fission_rates)" + "ce_fission_rates /= np.mean(ce_fission_rates)" ] }, { @@ -2357,7 +1343,7 @@ }, { "cell_type": "code", - "execution_count": 41, + "execution_count": 40, "metadata": { "collapsed": false }, @@ -2365,18 +1351,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 41, + "execution_count": 40, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -2386,12 +1372,12 @@ "source": [ "# Plot the CE fission rates in the left subplot\n", "fig = plt.subplot(121)\n", - "plt.imshow(openmc_fission_rates, interpolation='none', cmap='jet')\n", + "plt.imshow(ce_fission_rates, interpolation='none', cmap='jet')\n", "plt.title('Continuous-Energy Fission Rates')\n", "\n", "# Plot the MG fission rates in the right subplot\n", "fig2 = plt.subplot(122)\n", - "plt.imshow(mgopenmc_fission_rates, interpolation='none', cmap='jet')\n", + "plt.imshow(mg_fission_rates, interpolation='none', cmap='jet')\n", "plt.title('Multi-Group Fission Rates')\n" ] }, diff --git a/docs/source/usersguide/mgxs_library.rst b/docs/source/usersguide/mgxs_library.rst index a5d2ec0d0..8628bef4e 100644 --- a/docs/source/usersguide/mgxs_library.rst +++ b/docs/source/usersguide/mgxs_library.rst @@ -8,10 +8,10 @@ OpenMC can be run in continuous-energy mode or multi-group mode, provided the nuclear data is available. In continuous-energy mode, the ``cross_sections.xml`` file contains necessary meta-data for each data set, including the name and a file system location where the complete library -can be found. In multi-group mode, this ``cross_sections.xml`` file contains +can be found. In multi-group mode, this ``mgxs.xml`` file contains this same meta-data describing the nuclide or material, but also contains the group-wise nuclear data. This portion of the manual describes the format of -the multi-group data library required to be used in the ``cross_sections.xml`` +the multi-group data library required to be used in the ``mgxs.xml`` file. Similar to the other input file types, the multi-group library is provided in @@ -23,7 +23,7 @@ materials. .. _XML: http://www.w3.org/XML/ ------------------------------------------------ -MGXS Library Specification -- cross_sections.xml +MGXS Library Specification -- mgxs.xml ------------------------------------------------ The multi-group library meta-data is contained within the groups_, diff --git a/openmc/material.py b/openmc/material.py index e9a74f1e7..02cbc117d 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -348,7 +348,9 @@ class Material(object): del self._nuclides[nuclide._name] def add_macroscopic(self, macroscopic): - """Add a macroscopic to the material + """Add a macroscopic to the material. This will also set the + density of the material to 1.0, unless it has been otherwise set, + as a default for Macroscopic cross sections. Parameters ---------- @@ -386,6 +388,14 @@ class Material(object): 'Material!'.format(self._id, macroscopic) raise ValueError(msg) + # Generally speaking, the density for a macroscopic object will + # be 1.0. Therefore, lets set density to 1.0 so that the user + # doesnt need to set it unless its needed. + # Of course, if the user has already set a value of density, + # then we will not override it. + if self._density is None: + self.set_density('macro', 1.0) + def remove_macroscopic(self, macroscopic): """Remove a macroscopic from the material diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 334a0fa9c..44746e209 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -722,11 +722,140 @@ class Library(object): # Load and return pickled Library object return pickle.load(open(full_filename, 'rb')) - def write_mg_library(self, xs_type='macro', domain_names=None, xs_ids=None, - filename='mg_cross_sections', directory='./', - return_names=False): - """Creates a cross-section data library file for the Multi-Group - mode of OpenMC. + def get_xsdata(self, domain, domain_name, nuclide='total', xs_type='macro', + xs_id='1m', order=-1): + """Generates an openmc.XSdata object describing a multi-group cross section + data set for eventual combination in to an openmc.MGXSLibrary object + (i.e., the library). + + Parameters + ---------- + domain : openmc.Material or openmc.Cell or openmc.Universe + The domain for spatial homogenization + domain_name : str + Name to apply to the "xsdata" entry produced by this method + nuclide : str + A nuclide name string (e.g., 'U-235'). Defaults to 'total' to + obtain a material-wise macroscopic cross section. + xs_type: {'macro', 'micro'} + Provide the macro or micro cross section in units of cm^-1 or + barns. Defaults to 'macro'. If the Library object is not tallied by + nuclide this will be set to 'macro' regardless. + xs_ids : str + Cross section set identifier. Defaults to '1m'. + order : Scattering order for this dataset entry. Default is -1, + which will force the XSdata object to use whatever the maximum + order available. + + Returns + ------- + xsdata : openmc.XSdata + Multi-Group Cross Section data set object. + + Raises + ------ + ValueError + When the Library object is initialized with insufficient types of + cross sections for the Library. + + See also + -------- + Library.create_mg_library(...) + + """ + + cv.check_type('domain', domain, (openmc.Material, openmc.Cell, + openmc.Cell)) + cv.check_type('domain_name', domain_name, basestring) + cv.check_type('nuclide', nuclide, basestring) + cv.check_value('xs_type', xs_type, ['macro', 'micro']) + cv.check_type('xs_id', xs_id, basestring) + cv.check_type('order', order, Integral) + cv.check_greater_than('order', order, -1, equality=True) + + # Make sure statepoint has been loaded + if self._sp_filename is None: + msg = 'A StatePoint must be loaded before calling ' \ + 'the create_mg_library() function' + raise ValueError(msg) + + # If gathering material-specific data, set the xs_type to macro + if not self.by_nuclide: + xs_type = 'macro' + + # Build & add metadata to XSdata object + name = domain_name + if nuclide is not 'total': + name += '_' + nuclide + name += '.' + xs_id + xsdata = openmc.XSdata(name, self.energy_groups) + xsdata.order = order + if nuclide is not 'total': + xsdata.zaid = self._nuclides[nuclide][0] + xsdata.awr = self._nuclides[nuclide][1] + + # Now get xs data itself + if 'transport' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'transport') + xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide]) + elif 'total' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'total') + xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide]) + if 'absorption' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'absorption') + xsdata.set_absorption_mgxs(mymgxs, xs_type=xs_type, + nuclide=[nuclide]) + if 'fission' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'fission') + xsdata.set_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=[nuclide]) + if 'kappa-fission' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'kappa-fission') + xsdata.set_kappa_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=[nuclide]) + if 'chi' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'chi') + xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide]) + if 'nu-fission' in self.mgxs_types: + mymgxs = self.get_mgxs(domain, 'nu-fission') + xsdata.set_nu_fission_mgxs(mymgxs, xs_type=xs_type, + nuclide=[nuclide]) + # multiplicity requires scatter and nu-scatter + if ((('scatter matrix' in self.mgxs_types) and + ('nu-scatter matrix' in self.mgxs_types))): + scatt_mgxs = self.get_mgxs(domain, 'scatter matrix') + nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix') + xsdata.set_multiplicity_mgxs(nuscatt_mgxs, scatt_mgxs, + xs_type=xs_type, nuclide=[nuclide]) + using_multiplicity = True + else: + using_multiplicity = False + + if using_multiplicity: + nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix') + xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, + nuclide=[nuclide]) + else: + if 'nu-scatter matrix' in self.mgxs_types: + nuscatt_mgxs = self.get_mgxs(domain, 'nu-scatter matrix') + xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, + nuclide=[nuclide]) + + # Since we are not using multiplicity, then + # scattering multiplication (nu-scatter) must be + # accounted for approximately by using an adjusted + # absorption cross section. + if 'total' in self.mgxs_types: + xsdata._absorption = \ + np.subtract(xsdata.total, + np.sum(xsdata.scatter[0, :, :], axis=1)) + + return xsdata + + def create_mg_library(self, xs_type='macro', domain_names=None, + xs_ids=None): + """Creates an openmc.MGXSLibrary object to contain the MGXS data for the + Multi-Group mode of OpenMC. Parameters ---------- @@ -735,28 +864,18 @@ class Library(object): barns. Defaults to 'macro'. If the Library object is not tallied by nuclide this will be set to 'macro' regardless. domain_names : Iterable of str - List of names to apply to the xsdata entries in the + List of names to apply to the "xsdata" entries in the resultant mgxs data file. Defaults to 'set1', 'set2', ... xs_ids : str or Iterable of str Cross section set identifier (i.e., '71c') for all data sets (if only str) or for each individual one (if iterable of str). Defaults to '1m'. - filename : str - Filename for the pickle file. Defaults to 'mg_cross_sections'. - directory : str - Directory for the pickle file. Defaults to './' (the - current working directory). - return_names : bool - Flag to indicate if the user would like the names of the - materials generated by this function returned with completion. - Defaults to False, indicating that no names will be returned. Returns ------- - mat_names : Iterable of str - Iterable of material names generated during this routine and - applies to the cross section library. Note this is returned if - the return_names parameter is provided. + mgxs_file : openmc.MGXSLibrary + Multi-Group Cross Section File that is ready to be printed to the + file of choice by the user. Raises ------ @@ -774,10 +893,9 @@ class Library(object): # multi-group cross section types self.check_library_for_openmc_mgxs() - # Check the provided parameters cv.check_value('xs_type', xs_type, ['macro', 'micro']) if domain_names is not None: - cv.check_iterable_type('domain_names', filename, basestring) + cv.check_iterable_type('domain_names', domain_names, basestring) if xs_ids is not None: if isinstance(xs_ids, basestring): # If we only have a string lets convert it now to a list @@ -787,25 +905,11 @@ class Library(object): cv.check_iterable_type('xs_ids', xs_ids, basestring) else: xs_ids = ['1m' for i in range(len(self.domains))] - cv.check_type('filename', filename, basestring) - cv.check_type('directory', directory, basestring) - # Make sure statepoint has been loaded - if self._sp_filename is None: - msg = 'A StatePoint must be loaded before calling ' \ - 'the write_mg_library() function' - raise ValueError(msg) - - # Construct the collection of the nuclides to report + # If gathering material-specific data, set the xs_type to macro if not self.by_nuclide: xs_type = 'macro' - # Make directory if it does not exist and build our filename - if not os.path.exists(directory): - os.makedirs(directory) - full_filename = os.path.join(directory, filename + '.xml') - full_filename = full_filename.replace(' ', '-') - # Initialize file mgxs_file = openmc.MGXSLibrary(self.energy_groups) @@ -813,13 +917,10 @@ class Library(object): # support for higher orders are included in openmc.mgxs order = 0 - # Build XSdata objects + # Build storage for our XSdata objects xsdatas = [] - mat_names = {} for i, domain in enumerate(self.domains): - - mat_names[domain.id] = {} if self.by_nuclide: nuclides = list(domain.get_all_nuclides().keys()) else: @@ -832,99 +933,23 @@ class Library(object): name = domain_names[i] if nuclide is not 'total': name += '_' + nuclide - name += '.' + xs_ids[i] - # Store the name - mat_names[domain.id][nuclide] = name - - xsdata = openmc.XSdata(name, self.energy_groups) - xsdata.order = order - if nuclide is not 'total': - xsdata.zaid = self._nuclides[nuclide][0] - xsdata.awr = self._nuclides[nuclide][1] - - nuclide = [nuclide] - # Now get xs data itself - if 'transport' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'transport') - xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - elif 'total' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'total') - xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - if 'absorption' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'absorption') - xsdata.set_absorption_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - if 'fission' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'fission') - xsdata.set_fission_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - if 'kappa-fission' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'kappa-fission') - xsdata.set_kappa_fission_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - if 'chi' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'chi') - xsdata.set_chi_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - if 'nu-fission' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'nu-fission') - xsdata.set_nu_fission_mgxs(mymgxs, xs_type=xs_type, - nuclide=nuclide) - # multiplicity requires scatter and nu-scatter - if ((('scatter matrix' in self.mgxs_types) and - ('nu-scatter matrix' in self.mgxs_types))): - scatt_mgxs = self.get_mgxs(domain, - 'scatter matrix') - nuscatt_mgxs = self.get_mgxs(domain, - 'nu-scatter matrix') - xsdata.set_multiplicity_mgxs(nuscatt_mgxs, scatt_mgxs, - xs_type=xs_type, - nuclide=nuclide) - using_multiplicity = True - else: - using_multiplicity = False - - if using_multiplicity: - nuscatt_mgxs = self.get_mgxs(domain, - 'nu-scatter matrix') - xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, - nuclide=nuclide) - else: - if 'nu-scatter matrix' in self.mgxs_types: - nuscatt_mgxs = self.get_mgxs(domain, - 'nu-scatter matrix') - xsdata.set_scatter_mgxs(nuscatt_mgxs, xs_type=xs_type, - nuclide=nuclide) - - # Since we are not using multiplicity, then - # scattering multiplication (nu-scatter) must be - # accounted for approximately by using an adjusted - # absorption cross section. - if 'total' in self.mgxs_types: - xsdata._absorption = \ - np.subtract(xsdata.total, - np.sum(xsdata.scatter[0, :, :], - axis=1)) + xsdata = self.get_xsdata(domain, name, nuclide=nuclide, + xs_type=xs_type, xs_id=xs_ids[i], + order=order) xsdatas.append(xsdata) # Add XSdatas to file mgxs_file.add_xsdatas(xsdatas) - # Finally, write the file - mgxs_file.export_to_xml(full_filename) - - if return_names: - return mat_names + return mgxs_file def check_library_for_openmc_mgxs(self): - """This routine will check the MGXS Types within the provided - Library to ensure the data types provided can be used to create - a MGXS Library for OpenMC's Multi-Group mode via the - `Library.write_mg_library` method. + """This routine will check the MGXS Types within a Library + to ensure the MGXS types provided can be used to create + a MGXS Library for OpenMC's Multi-Group mode. + The rules to check include: - Either total or transport should be present. - Both can be available if one wants, but we should @@ -943,7 +968,7 @@ class Library(object): See also -------- - Library.write_mg_library(...) + Library.create_mg_library(...) """ diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 29d0bfdd7..e59ef2d61 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -420,7 +420,8 @@ class XSdata(object): enable = tabular_legendre['enable'] check_type('enable', enable, bool) else: - msg = 'enable must be provided in tabular_legendre' + msg = 'The tabular_legendre dict must include a value keyed by ' \ + '"enable"' raise ValueError(msg) if 'num_points' in tabular_legendre: num_points = tabular_legendre['num_points'] @@ -448,217 +449,77 @@ class XSdata(object): @total.setter def total(self, total): - """This method sets the total cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - total: ndarray - Array of group-wise cross sections to apply - - """ - - # check we have a numpy list check_type('total', total, np.ndarray, expected_iter_type=Real) - # Check the dimensions of the data check_value('total shape', total.shape, self.vector_shape) - self._total = np.copy(total) + self._total = total @absorption.setter def absorption(self, absorption): - """This method sets the absorption cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - absorption: ndarray - Array of group-wise cross sections to apply - - """ - - # check we have a numpy list check_type('absorption', absorption, np.ndarray, expected_iter_type=Real) - # Check the dimensions of the data check_value('absorption shape', absorption.shape, self.vector_shape) - self._absorption = np.copy(absorption) + self._absorption = absorption @fission.setter def fission(self, fission): - """This method sets the fission cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - fission: ndarray - Array of group-wise cross sections to apply - - """ - - # check we have a numpy list check_type('fission', fission, np.ndarray, expected_iter_type=Real) - # Check the dimensions of the data check_value('fission shape', fission.shape, self.vector_shape) - self._fission = np.copy(fission) + self._fission = fission if np.sum(self._fission) > 0.0: self._fissionable = True @kappa_fission.setter def kappa_fission(self, kappa_fission): - """This method sets the kappa_fission cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - kappa_fission: ndarray - Array of group-wise cross sections to apply - - """ - - # check we have a numpy list - check_type('kappa_fission', fission, np.ndarray, + check_type('kappa_fission', kappa_fission, np.ndarray, expected_iter_type=Real) - # Check the dimensions of the data check_value('kappa fission shape', kappa_fission.shape, self.vector_shape) - self._kappa_fission = np.copy(fission) + self._kappa_fission = kappa_fission if np.sum(self._kappa_fission) > 0.0: self._fissionable = True @chi.setter def chi(self, chi): - """This method sets the chi cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - chi: ndarray - Array of group-wise chi values to apply - - """ - if self._use_chi is not None: if not self._use_chi: msg = 'Providing chi when nu_fission already provided as a' \ 'matrix' raise ValueError(msg) - # check we have a numpy list check_type('chi', chi, np.ndarray, expected_iter_type=Real) - # Check the dimensions of the data check_value('chi shape', chi.shape, self.vector_shape) - self._chi = np.copy(chi) + self._chi = chi if self._use_chi is not None: self._use_chi = True @scatter.setter def scatter(self, scatter): - """This method sets the scattering matrix cross sections - by performing a deep-copy of the provided ndarray. - If the angular representation is "isotropic" the shape of - the input array must be the number of scattering orders, the - number of energy groups, and the number of energy groups. If - the angular representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles, number of scattering orders, energy groups, and energy groups. - - Parameters - ---------- - scatter : ndarrays - Array of cross sections to apply - - """ - - # check we have a numpy list check_type('scatter', scatter, np.ndarray, expected_iter_type=Real, max_depth=len(scatter.shape)) - # Check the dimensions of the data check_value('scatter shape', scatter.shape, self.pn_matrix_shape) - self._scatter = np.copy(scatter) + self._scatter = scatter @multiplicity.setter def multiplicity(self, multiplicity): - """This method sets the scattering multiplicity matrix cross sections - by performing a deep-copy of the provided ndarray. Multiplicity, - in OpenMC parlance, is a factor used to account for the production - of neutrons introduced by scattering multiplication reactions, i.e., - (n,xn) events. In this sense, the multiplication matrix is simply - defined as the ratio of the nu-scatter and scatter matrices. - If the angular representation is "isotropic" the shape of - the input array must be the number of energy groups and the number - of energy groups. If the angular representation is "angle" then the - shape of the input array must be the number of polar angles, - number azimuthal angles, number of scattering orders, energy groups, - and energy groups. - - Parameters - ---------- - multiplicity : ndarrays - Array of scattering multiplications to apply - - """ - - # check we have a numpy list check_type('multiplicity', multiplicity, np.ndarray, expected_iter_type=Real, max_depth=len(multiplicity.shape)) - # Check the dimensions of the data check_value('multiplicity shape', multiplicity.shape, self.matrix_shape) - self._multiplicity = np.copy(multiplicity) + self._multiplicity = multiplicity @nu_fission.setter def nu_fission(self, nu_fission): - """This method sets the nu_fission cross section by performing a - deep-copy of the provided ndarray. If the angular - representation is "isotropic" the shape of the input array - must be the number of energy groups. If the angular - representation is "angle" then the shape of the input - array must be the number of polar angles, number azimuthal - angles and energy groups. - - Parameters - ---------- - nu_fission: ndarray - Array of group-wise cross sections to apply - - """ - # The NuFissionXS class does not have the capability to produce # a fission matrix and therefore if this path is pursued, we know # chi must be used. @@ -669,12 +530,10 @@ class XSdata(object): # chi already has been set. If not, we just check that this is OK # and set the use_chi flag accordingly - # First, check we have a numpy list check_type('nu_fission', nu_fission, np.ndarray, expected_iter_type=Real, max_depth=len(nu_fission.shape)) if self._use_chi is not None: - # Check the dimensions of the data if self._use_chi: check_value('nu_fission shape', nu_fission.shape, self.vector_shape) @@ -682,16 +541,16 @@ class XSdata(object): check_value('nu_fission shape', nu_fission.shape, self.matrix_shape) else: - # Make sure the dimensions are at least right check_value('nu_fission shape', nu_fission.shape, (self.vector_shape, self.matrix_shape)) - # Then find out which one we have so we can set use_chi + # Find out if we have a nu-fission matrix or vector + # and set a flag to allow other methods to check this later. if nu_fission.shape == self.vector_shape: self._use_chi = True else: self._use_chi = False - self._nu_fission = np.copy(nu_fission) + self._nu_fission = nu_fission if np.sum(self._nu_fission) > 0.0: self._fissionable = True @@ -716,11 +575,7 @@ class XSdata(object): check_type('total', total, (openmc.mgxs.TotalXS, openmc.mgxs.TransportXS)) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', total.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', total.domain_type, ['universe', 'cell', 'material']) @@ -750,12 +605,8 @@ class XSdata(object): """ check_type('absorption', absorption, openmc.mgxs.AbsorptionXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', absorption.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', absorption.domain_type, ['universe', 'cell', 'material']) @@ -785,12 +636,8 @@ class XSdata(object): """ check_type('fission', fission, openmc.mgxs.FissionXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', fission.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', fission.domain_type, ['universe', 'cell', 'material']) @@ -824,12 +671,8 @@ class XSdata(object): # a fission matrix and therefore if this path is pursued, we know # chi must be used. check_type('nu_fission', nu_fission, openmc.mgxs.NuFissionXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', nu_fission.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', nu_fission.domain_type, ['universe', 'cell', 'material']) @@ -866,12 +709,8 @@ class XSdata(object): """ check_type('k_fission', k_fission, openmc.mgxs.KappaFissionXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', k_fission.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', k_fission.domain_type, ['universe', 'cell', 'material']) @@ -906,11 +745,7 @@ class XSdata(object): raise ValueError(msg) check_type('chi', chi, openmc.mgxs.Chi) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', chi.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', chi.domain_type, ['universe', 'cell', 'material']) @@ -944,12 +779,8 @@ class XSdata(object): """ check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', scatter.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', scatter.domain_type, ['universe', 'cell', 'material']) @@ -990,14 +821,10 @@ class XSdata(object): check_type('nuscatter', nuscatter, openmc.mgxs.NuScatterMatrixXS) check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS) - - # Make sure passed MGXS object contains correct group structure check_value('energy_groups', nuscatter.energy_groups, [self.energy_groups]) check_value('energy_groups', scatter.energy_groups, [self.energy_groups]) - - # Make sure passed MGXS object has correct domain type check_value('domain_type', nuscatter.domain_type, ['universe', 'cell', 'material']) check_value('domain_type', scatter.domain_type, @@ -1153,14 +980,10 @@ class MGXSLibrary(object): MGXS information to add """ - - # Check the type if not isinstance(xsdata, XSdata): msg = 'Unable to add a non-XSdata "{0}" to the ' \ 'MGXSLibrary instance'.format(xsdata) raise ValueError(msg) - - # Make sure energy groups match. if xsdata.energy_groups != self._energy_groups: msg = 'Energy groups of XSdata do not match that of MGXSLibrary.' raise ValueError(msg) @@ -1176,8 +999,6 @@ class MGXSLibrary(object): XSdatas to add """ - - # Check we have an iterable of XSdatas check_iterable_type('xsdatas', xsdatas, XSdata) for xsdata in xsdatas: @@ -1222,14 +1043,14 @@ class MGXSLibrary(object): xml_element = xsdata._get_xsdata_xml() self._cross_sections_file.append(xml_element) - def export_to_xml(self, filename='mg_cross_sections.xml'): - """Create an mg_cross_sections.xml file that can be used for a + def export_to_xml(self, filename='mgxs.xml'): + """Create an mgxs.xml file that can be used for a simulation. Parameters ---------- filename : str, optional - filename of file, default is mg_cross_sections.xml + filename of file, default is mgxs.xml """ diff --git a/src/input_xml.F90 b/src/input_xml.F90 index 22eff595c..24986be87 100644 --- a/src/input_xml.F90 +++ b/src/input_xml.F90 @@ -153,7 +153,7 @@ contains else call get_environment_variable("OPENMC_MG_CROSS_SECTIONS", env_variable) if (len_trim(env_variable) == 0) then - call fatal_error("No cross_sections.xml file was specified in & + call fatal_error("No mgxs.xml file was specified in & &settings.xml or in the OPENMC_MG_CROSS_SECTIONS environment & &variable. OpenMC needs such a file to identify where to & &find the cross section libraries. Please consult the user's & @@ -4537,24 +4537,24 @@ contains subroutine read_mg_cross_sections_xml() integer :: i ! loop index - logical :: file_exists ! does cross_sections.xml exist? + logical :: file_exists ! does mgxs.xml exist? type(XsListing), pointer :: listing => null() type(Node), pointer :: doc => null() type(Node), pointer :: node_xsdata => null() type(NodeList), pointer :: node_xsdata_list => null() real(8), allocatable :: rev_energy_bins(:) - ! Check if cross_sections.xml exists + ! Check if mgxs.xml exists inquire(FILE=path_cross_sections, EXIST=file_exists) if (.not. file_exists) then - ! Could not find cross_sections.xml file + ! Could not find mgxs.xml file call fatal_error("Cross sections XML file '" & // trim(path_cross_sections) // "' does not exist!") end if call write_message("Reading cross sections XML file...", 5) - ! Parse cross_sections.xml file + ! Parse mgxs.xml file call open_xmldoc(doc, path_cross_sections) if (check_for_node(doc, "groups")) then @@ -4602,7 +4602,7 @@ contains ! Allocate xs_listings array if (n_listings == 0) then call fatal_error("At least one element must be present in & - &cross_sections.xml file!") + &mgxs.xml file!") else allocate(xs_listings(n_listings)) end if From 86cf42d7a63ab65db19986787510fe670a88e955 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 14 May 2016 07:58:10 -0400 Subject: [PATCH 131/147] Clarifications in example notebook --- .../pythonapi/examples/mgxs-part-iv.ipynb | 69 +++++++++++-------- 1 file changed, 39 insertions(+), 30 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index d03db2cce..b81e8f06b 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -433,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -520,9 +520,9 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material,\" \"cell,\" and \"universe\" domain types. We will use a \"cell\" domain type here to compute cross sections in each of the cells in the fuel assembly geometry.\n", + "Now we must specify the type of domain over which we would like the `Library` to compute multi-group cross sections. The domain type corresponds to the type of tally filter to be used in the tallies created to compute multi-group cross sections. At the present time, the `Library` supports \"material,\" \"cell,\" and \"universe\" domain types. In this simple example, we wish to compute multi-group cross sections only for each material andtherefore will use a \"material\" domain type.\n", "\n", - "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell or universe) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property. In our this simple example, we wish to compute multi-group cross sections only for each material." + "**Note:** By default, the `Library` class will instantiate `MGXS` objects for each and every domain (material, cell or universe) in the geometry of interest. However, one may specify a subset of these domains to the `Library.domains` property." ] }, { @@ -696,7 +696,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-13 22:29:41\n", + " Date/Time: 2016-05-14 07:56:31\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -783,20 +783,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4550E+00 seconds\n", - " Reading cross sections = 1.1400E+00 seconds\n", - " Total time in simulation = 1.9150E+01 seconds\n", - " Time in transport only = 1.9021E+01 seconds\n", - " Time in inactive batches = 2.1570E+00 seconds\n", - " Time in active batches = 1.6993E+01 seconds\n", - " Time synchronizing fission bank = 7.0000E-03 seconds\n", + " Total time for initialization = 1.4930E+00 seconds\n", + " Reading cross sections = 1.1850E+00 seconds\n", + " Total time in simulation = 1.9053E+01 seconds\n", + " Time in transport only = 1.9002E+01 seconds\n", + " Time in inactive batches = 2.0890E+00 seconds\n", + " Time in active batches = 1.6964E+01 seconds\n", + " Time synchronizing fission bank = 6.0000E-03 seconds\n", " Sampling source sites = 5.0000E-03 seconds\n", - " SEND/RECV source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.0614E+01 seconds\n", - " Calculation Rate (inactive) = 23180.3 neutrons/second\n", - " Calculation Rate (active) = 11769.6 neutrons/second\n", + " Total time elapsed = 2.0556E+01 seconds\n", + " Calculation Rate (inactive) = 23934.9 neutrons/second\n", + " Calculation Rate (active) = 11789.7 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -960,7 +960,11 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Now we will need to recreate similar xml files from above, beginning with materials.xml. Similar to how continuous-energy cross section libraries are named, the `openmc.Macroscopic` quantities below can either have their `xs_id` included (i.e., `'.2m'`), or this can be left off but the `default_xs` parameter of the materials file be used instead to be set to the `'xs_id'` of interest (which is `'.2m'` in this case as defined in the previous cell)." + "OpenMC's multi-group mode uses the same input files as does the continuous-energy mode (materials, geometry, settings, plots ,and tallies file). Differences would include the use of a flag to tell the code to use multi-group transport, a location of the multi-group library file, and any changes needed in the materials.xml and geometry.xml files to re-define materials as necessary (for example, if using a macroscopic cross section library instead of individual microscopic nuclide cross sections as is done in continuous-energy, or if multiple cross sections exist for the same material due to the material existing in varied spectral regions).\n", + "\n", + "Since this example is using material-wise macroscopic cross sections without considering that the neutron energy spectra and thus cross sections may be changing in space, we only need to modify the materials.xml and settings.xml files. If the material names and ids are not otherwise changed, then the geometry.xml file does not need to be modified from its continuous-energy form. The tallies.xml file will be left untouched as it currently contains the tally types that we will need to perform our comparison. \n", + "\n", + "First we will create the new materials.xml file. Continuous-energy cross section nuclidic data sets are named with the nuclide name followed by a cross section identifier. For example, the data for hydrogen is accessed in OpenMC by the name `H-1.71c`. The cross-section identifier (in this case, `71c`) can be used to distinguish between different variants of `H-1` data, such as for different evaluations or temperatures. OpenMC multi-group libraries use the same convention of a name followed by a xs identifier. We will use a cross section identifier here of `2m`. Similar to how continuous-energy cross section libraries are named, the `openmc.Macroscopic` quantities below can either have their `xs_id` included (i.e., `'fuel.2m'`). An alternative is to leave this extension off and simply change the `default_xs` parameter to `.2m`." ] }, { @@ -1067,7 +1071,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-13 22:30:02\n", + " Date/Time: 2016-05-14 07:56:52\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1151,20 +1155,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.7000E-02 seconds\n", - " Reading cross sections = 4.0000E-03 seconds\n", - " Total time in simulation = 1.2661E+01 seconds\n", - " Time in transport only = 1.2600E+01 seconds\n", - " Time in inactive batches = 1.1370E+00 seconds\n", - " Time in active batches = 1.1524E+01 seconds\n", + " Total time for initialization = 4.0000E-02 seconds\n", + " Reading cross sections = 6.0000E-03 seconds\n", + " Total time in simulation = 1.2540E+01 seconds\n", + " Time in transport only = 1.2496E+01 seconds\n", + " Time in inactive batches = 1.1110E+00 seconds\n", + " Time in active batches = 1.1429E+01 seconds\n", " Time synchronizing fission bank = 7.0000E-03 seconds\n", " Sampling source sites = 5.0000E-03 seconds\n", " SEND/RECV source sites = 2.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.2707E+01 seconds\n", - " Calculation Rate (inactive) = 43975.4 neutrons/second\n", - " Calculation Rate (active) = 17355.1 neutrons/second\n", + " Total time elapsed = 1.2589E+01 seconds\n", + " Calculation Rate (inactive) = 45004.5 neutrons/second\n", + " Calculation Rate (active) = 17499.3 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1351,7 +1355,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 40, @@ -1360,9 +1364,9 @@ }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, @@ -1370,6 +1374,11 @@ } ], "source": [ + "# Force zeros to be NaNs so their values are not included when matplotlib calculates\n", + "# the color scale\n", + "ce_fission_rates[ce_fission_rates == 0.] = np.nan\n", + "mg_fission_rates[mg_fission_rates == 0.] = np.nan\n", + "\n", "# Plot the CE fission rates in the left subplot\n", "fig = plt.subplot(121)\n", "plt.imshow(ce_fission_rates, interpolation='none', cmap='jet')\n", @@ -1387,7 +1396,7 @@ "collapsed": true }, "source": [ - "We also see very good agreement between the fission rate distributions." + "We also see very good agreement between the fission rate distributions, though these should converge closer together with an increasing number of particle histories in both the continuous-energy run to generate the multi-group cross sections, and in the multi-group calculation itself." ] }, { From 2654505089422a551f57f2653cd60c7b70e45fc3 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 14 May 2016 10:36:13 -0400 Subject: [PATCH 132/147] Updated MGXS test results using Pandas 0.18 --- .../results_true.dat | 86 +++---- .../results_true.dat | 4 +- .../results_true.dat | 236 +++++++++--------- .../results_true.dat | 2 +- 4 files changed, 164 insertions(+), 164 deletions(-) diff --git a/tests/test_mgxs_library_condense/results_true.dat b/tests/test_mgxs_library_condense/results_true.dat index ffe6f2908..184be68bf 100644 --- a/tests/test_mgxs_library_condense/results_true.dat +++ b/tests/test_mgxs_library_condense/results_true.dat @@ -5,81 +5,81 @@ 1 1 1 1 total P1 0.039277 0.004308 2 1 1 1 total P2 0.017574 0.002402 3 1 1 1 total P3 0.012203 0.002164 material group out nuclide mean std. dev. -0 1 1 total 1 0.055333 material group in nuclide mean std. dev. +0 1 1 total 1.0 0.055333 material group in nuclide mean std. dev. 0 2 1 total 0.241262 0.00841 material group in nuclide mean std. dev. -0 2 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 2 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 2 1 1 total P0 0.272369 0.006872 1 2 1 1 total P1 0.031107 0.005483 2 2 1 1 total P2 0.025999 0.006151 3 2 1 1 total P3 0.003219 0.003312 material group out nuclide mean std. dev. -0 2 1 total 0 0 material group in nuclide mean std. dev. +0 2 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 3 1 total 0.400028 0.034667 material group in nuclide mean std. dev. -0 3 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 3 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 3 1 1 total P0 0.794999 0.036548 1 3 1 1 total P1 0.401537 0.016175 2 3 1 1 total P2 0.143623 0.008719 3 3 1 1 total P3 0.001991 0.004433 material group out nuclide mean std. dev. -0 3 1 total 0 0 material group in nuclide mean std. dev. +0 3 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 4 1 total 0.377402 0.072937 material group in nuclide mean std. dev. -0 4 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 4 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 4 1 1 total P0 0.727311 0.080096 1 4 1 1 total P1 0.355839 0.037901 2 4 1 1 total P2 0.124483 0.015823 3 4 1 1 total P3 0.012168 0.006224 material group out nuclide mean std. dev. -0 4 1 total 0 0 material group in nuclide mean std. dev. -0 5 1 total 0 0 material group in nuclide mean std. dev. -0 5 1 total 0 0 material group in group out nuclide moment mean std. dev. -0 5 1 1 total P0 0 0 -1 5 1 1 total P1 0 0 -2 5 1 1 total P2 0 0 -3 5 1 1 total P3 0 0 material group out nuclide mean std. dev. -0 5 1 total 0 0 material group in nuclide mean std. dev. -0 6 1 total 0 0 material group in nuclide mean std. dev. -0 6 1 total 0 0 material group in group out nuclide moment mean std. dev. -0 6 1 1 total P0 0 0 -1 6 1 1 total P1 0 0 -2 6 1 1 total P2 0 0 -3 6 1 1 total P3 0 0 material group out nuclide mean std. dev. -0 6 1 total 0 0 material group in nuclide mean std. dev. -0 7 1 total 0 0 material group in nuclide mean std. dev. -0 7 1 total 0 0 material group in group out nuclide moment mean std. dev. -0 7 1 1 total P0 0 0 -1 7 1 1 total P1 0 0 -2 7 1 1 total P2 0 0 -3 7 1 1 total P3 0 0 material group out nuclide mean std. dev. -0 7 1 total 0 0 material group in nuclide mean std. dev. -0 8 1 total 0 0 material group in nuclide mean std. dev. -0 8 1 total 0 0 material group in group out nuclide moment mean std. dev. -0 8 1 1 total P0 0 0 -1 8 1 1 total P1 0 0 -2 8 1 1 total P2 0 0 -3 8 1 1 total P3 0 0 material group out nuclide mean std. dev. -0 8 1 total 0 0 material group in nuclide mean std. dev. +0 4 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +0 5 1 1 total P0 0.0 0.0 +1 5 1 1 total P1 0.0 0.0 +2 5 1 1 total P2 0.0 0.0 +3 5 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev. +0 5 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +0 6 1 1 total P0 0.0 0.0 +1 6 1 1 total P1 0.0 0.0 +2 6 1 1 total P2 0.0 0.0 +3 6 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev. +0 6 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +0 7 1 1 total P0 0.0 0.0 +1 7 1 1 total P1 0.0 0.0 +2 7 1 1 total P2 0.0 0.0 +3 7 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev. +0 7 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +0 8 1 1 total P0 0.0 0.0 +1 8 1 1 total P1 0.0 0.0 +2 8 1 1 total P2 0.0 0.0 +3 8 1 1 total P3 0.0 0.0 material group out nuclide mean std. dev. +0 8 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 9 1 total 0.600536 0.748875 material group in nuclide mean std. dev. -0 9 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 9 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 9 1 1 total P0 0.720380 0.771015 1 9 1 1 total P1 0.119844 0.184691 2 9 1 1 total P2 0.038522 0.064485 3 9 1 1 total P3 0.056023 0.050595 material group out nuclide mean std. dev. -0 9 1 total 0 0 material group in nuclide mean std. dev. +0 9 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 10 1 total 0.235515 0.613974 material group in nuclide mean std. dev. -0 10 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 10 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 10 1 1 total P0 0.501009 0.708534 1 10 1 1 total P1 0.265494 0.375465 2 10 1 1 total P2 0.141979 0.200788 3 10 1 1 total P3 0.074258 0.105017 material group out nuclide mean std. dev. -0 10 1 total 0 0 material group in nuclide mean std. dev. +0 10 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 11 1 total 0.510145 0.741941 material group in nuclide mean std. dev. -0 11 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 11 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 11 1 1 total P0 0.804661 0.817658 1 11 1 1 total P1 0.312803 0.315315 2 11 1 1 total P2 0.168113 0.172935 3 11 1 1 total P3 0.003808 0.037911 material group out nuclide mean std. dev. -0 11 1 total 0 0 material group in nuclide mean std. dev. +0 11 1 total 0.0 0.0 material group in nuclide mean std. dev. 0 12 1 total 0.73836 0.825631 material group in nuclide mean std. dev. -0 12 1 total 0 0 material group in group out nuclide moment mean std. dev. +0 12 1 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 0 12 1 1 total P0 0.943429 0.856119 1 12 1 1 total P1 0.220164 0.163180 2 12 1 1 total P2 0.052884 0.042440 3 12 1 1 total P3 0.039939 0.032867 material group out nuclide mean std. dev. -0 12 1 total 0 0 \ No newline at end of file +0 12 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_distribcell/results_true.dat b/tests/test_mgxs_library_distribcell/results_true.dat index ba9eaa71e..fa55249d1 100644 --- a/tests/test_mgxs_library_distribcell/results_true.dat +++ b/tests/test_mgxs_library_distribcell/results_true.dat @@ -1,8 +1,8 @@ avg(distribcell) group in nuclide mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644 avg(distribcell) group in nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 avg(distribcell) group in group out nuclide moment mean std. dev. +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 avg(distribcell) group in group out nuclide moment mean std. dev. 0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P0 1.142547 0.570131 1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322 2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504 3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621 avg(distribcell) group out nuclide mean std. dev. -0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0 0 \ No newline at end of file +0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_no_nuclides/results_true.dat b/tests/test_mgxs_library_no_nuclides/results_true.dat index 5e55a4c74..94150a202 100644 --- a/tests/test_mgxs_library_no_nuclides/results_true.dat +++ b/tests/test_mgxs_library_no_nuclides/results_true.dat @@ -19,12 +19,12 @@ 1 1 2 2 total P1 -0.011310 0.007839 2 1 2 2 total P2 -0.014807 0.008629 3 1 2 2 total P3 -0.006855 0.009047 material group out nuclide mean std. dev. -1 1 1 total 1 0.055333 -0 1 2 total 0 0.000000 material group in nuclide mean std. dev. +1 1 1 total 1.0 0.055333 +0 1 2 total 0.0 0.000000 material group in nuclide mean std. dev. 1 2 1 total 0.237254 0.008184 0 2 2 total 0.285930 0.048796 material group in nuclide mean std. dev. -1 2 1 total 0 0 -0 2 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 2 1 total 0.0 0.0 +0 2 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 2 1 1 total P0 0.273115 0.006253 13 2 1 1 total P1 0.035861 0.005878 14 2 1 1 total P2 0.029704 0.006640 @@ -41,12 +41,12 @@ 1 2 2 2 total P1 -0.021880 0.012218 2 2 2 2 total P2 -0.015295 0.010276 3 2 2 2 total P3 0.014034 0.014318 material group out nuclide mean std. dev. -1 2 1 total 0 0 -0 2 2 total 0 0 material group in nuclide mean std. dev. +1 2 1 total 0.0 0.0 +0 2 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 3 1 total 0.286906 0.027401 0 3 2 total 1.418151 0.265308 material group in nuclide mean std. dev. -1 3 1 total 0 0 -0 3 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 3 1 1 total P0 0.643346 0.028376 13 3 1 1 total P1 0.383409 0.016447 14 3 1 1 total P2 0.152185 0.009574 @@ -63,12 +63,12 @@ 1 3 2 2 total P1 0.498431 0.063421 2 3 2 2 total P2 0.091205 0.013726 3 3 2 2 total P3 0.017054 0.013916 material group out nuclide mean std. dev. -1 3 1 total 0 0 -0 3 2 total 0 0 material group in nuclide mean std. dev. +1 3 1 total 0.0 0.0 +0 3 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 4 1 total 0.242447 0.061031 0 4 2 total 1.253959 0.388363 material group in nuclide mean std. dev. -1 4 1 total 0 0 -0 4 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 4 1 total 0.0 0.0 +0 4 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 4 1 1 total P0 0.543941 0.065427 13 4 1 1 total P1 0.326011 0.038602 14 4 1 1 total P2 0.131133 0.017475 @@ -85,100 +85,100 @@ 1 4 2 2 total P1 0.500695 0.122178 2 4 2 2 total P2 0.099026 0.038719 3 4 2 2 total P3 0.032975 0.025103 material group out nuclide mean std. dev. -1 4 1 total 0 0 -0 4 2 total 0 0 material group in nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in group out nuclide moment mean std. dev. -12 5 1 1 total P0 0 0 -13 5 1 1 total P1 0 0 -14 5 1 1 total P2 0 0 -15 5 1 1 total P3 0 0 -8 5 1 2 total P0 0 0 -9 5 1 2 total P1 0 0 -10 5 1 2 total P2 0 0 -11 5 1 2 total P3 0 0 -4 5 2 1 total P0 0 0 -5 5 2 1 total P1 0 0 -6 5 2 1 total P2 0 0 -7 5 2 1 total P3 0 0 -0 5 2 2 total P0 0 0 -1 5 2 2 total P1 0 0 -2 5 2 2 total P2 0 0 -3 5 2 2 total P3 0 0 material group out nuclide mean std. dev. -1 5 1 total 0 0 -0 5 2 total 0 0 material group in nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in group out nuclide moment mean std. dev. -12 6 1 1 total P0 0 0 -13 6 1 1 total P1 0 0 -14 6 1 1 total P2 0 0 -15 6 1 1 total P3 0 0 -8 6 1 2 total P0 0 0 -9 6 1 2 total P1 0 0 -10 6 1 2 total P2 0 0 -11 6 1 2 total P3 0 0 -4 6 2 1 total P0 0 0 -5 6 2 1 total P1 0 0 -6 6 2 1 total P2 0 0 -7 6 2 1 total P3 0 0 -0 6 2 2 total P0 0 0 -1 6 2 2 total P1 0 0 -2 6 2 2 total P2 0 0 -3 6 2 2 total P3 0 0 material group out nuclide mean std. dev. -1 6 1 total 0 0 -0 6 2 total 0 0 material group in nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in group out nuclide moment mean std. dev. -12 7 1 1 total P0 0 0 -13 7 1 1 total P1 0 0 -14 7 1 1 total P2 0 0 -15 7 1 1 total P3 0 0 -8 7 1 2 total P0 0 0 -9 7 1 2 total P1 0 0 -10 7 1 2 total P2 0 0 -11 7 1 2 total P3 0 0 -4 7 2 1 total P0 0 0 -5 7 2 1 total P1 0 0 -6 7 2 1 total P2 0 0 -7 7 2 1 total P3 0 0 -0 7 2 2 total P0 0 0 -1 7 2 2 total P1 0 0 -2 7 2 2 total P2 0 0 -3 7 2 2 total P3 0 0 material group out nuclide mean std. dev. -1 7 1 total 0 0 -0 7 2 total 0 0 material group in nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in group out nuclide moment mean std. dev. -12 8 1 1 total P0 0 0 -13 8 1 1 total P1 0 0 -14 8 1 1 total P2 0 0 -15 8 1 1 total P3 0 0 -8 8 1 2 total P0 0 0 -9 8 1 2 total P1 0 0 -10 8 1 2 total P2 0 0 -11 8 1 2 total P3 0 0 -4 8 2 1 total P0 0 0 -5 8 2 1 total P1 0 0 -6 8 2 1 total P2 0 0 -7 8 2 1 total P3 0 0 -0 8 2 2 total P0 0 0 -1 8 2 2 total P1 0 0 -2 8 2 2 total P2 0 0 -3 8 2 2 total P3 0 0 material group out nuclide mean std. dev. -1 8 1 total 0 0 -0 8 2 total 0 0 material group in nuclide mean std. dev. +1 4 1 total 0.0 0.0 +0 4 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +12 5 1 1 total P0 0.0 0.0 +13 5 1 1 total P1 0.0 0.0 +14 5 1 1 total P2 0.0 0.0 +15 5 1 1 total P3 0.0 0.0 +8 5 1 2 total P0 0.0 0.0 +9 5 1 2 total P1 0.0 0.0 +10 5 1 2 total P2 0.0 0.0 +11 5 1 2 total P3 0.0 0.0 +4 5 2 1 total P0 0.0 0.0 +5 5 2 1 total P1 0.0 0.0 +6 5 2 1 total P2 0.0 0.0 +7 5 2 1 total P3 0.0 0.0 +0 5 2 2 total P0 0.0 0.0 +1 5 2 2 total P1 0.0 0.0 +2 5 2 2 total P2 0.0 0.0 +3 5 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev. +1 5 1 total 0.0 0.0 +0 5 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +12 6 1 1 total P0 0.0 0.0 +13 6 1 1 total P1 0.0 0.0 +14 6 1 1 total P2 0.0 0.0 +15 6 1 1 total P3 0.0 0.0 +8 6 1 2 total P0 0.0 0.0 +9 6 1 2 total P1 0.0 0.0 +10 6 1 2 total P2 0.0 0.0 +11 6 1 2 total P3 0.0 0.0 +4 6 2 1 total P0 0.0 0.0 +5 6 2 1 total P1 0.0 0.0 +6 6 2 1 total P2 0.0 0.0 +7 6 2 1 total P3 0.0 0.0 +0 6 2 2 total P0 0.0 0.0 +1 6 2 2 total P1 0.0 0.0 +2 6 2 2 total P2 0.0 0.0 +3 6 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev. +1 6 1 total 0.0 0.0 +0 6 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +12 7 1 1 total P0 0.0 0.0 +13 7 1 1 total P1 0.0 0.0 +14 7 1 1 total P2 0.0 0.0 +15 7 1 1 total P3 0.0 0.0 +8 7 1 2 total P0 0.0 0.0 +9 7 1 2 total P1 0.0 0.0 +10 7 1 2 total P2 0.0 0.0 +11 7 1 2 total P3 0.0 0.0 +4 7 2 1 total P0 0.0 0.0 +5 7 2 1 total P1 0.0 0.0 +6 7 2 1 total P2 0.0 0.0 +7 7 2 1 total P3 0.0 0.0 +0 7 2 2 total P0 0.0 0.0 +1 7 2 2 total P1 0.0 0.0 +2 7 2 2 total P2 0.0 0.0 +3 7 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev. +1 7 1 total 0.0 0.0 +0 7 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. +12 8 1 1 total P0 0.0 0.0 +13 8 1 1 total P1 0.0 0.0 +14 8 1 1 total P2 0.0 0.0 +15 8 1 1 total P3 0.0 0.0 +8 8 1 2 total P0 0.0 0.0 +9 8 1 2 total P1 0.0 0.0 +10 8 1 2 total P2 0.0 0.0 +11 8 1 2 total P3 0.0 0.0 +4 8 2 1 total P0 0.0 0.0 +5 8 2 1 total P1 0.0 0.0 +6 8 2 1 total P2 0.0 0.0 +7 8 2 1 total P3 0.0 0.0 +0 8 2 2 total P0 0.0 0.0 +1 8 2 2 total P1 0.0 0.0 +2 8 2 2 total P2 0.0 0.0 +3 8 2 2 total P3 0.0 0.0 material group out nuclide mean std. dev. +1 8 1 total 0.0 0.0 +0 8 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 9 1 total 0.600536 0.748875 0 9 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 9 1 total 0 0 -0 9 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 9 1 total 0.0 0.0 +0 9 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 9 1 1 total P0 0.720380 0.771015 13 9 1 1 total P1 0.119844 0.184691 14 9 1 1 total P2 0.038522 0.064485 @@ -195,12 +195,12 @@ 1 9 2 2 total P1 0.000000 0.000000 2 9 2 2 total P2 0.000000 0.000000 3 9 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev. -1 9 1 total 0 0 -0 9 2 total 0 0 material group in nuclide mean std. dev. +1 9 1 total 0.0 0.0 +0 9 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 10 1 total 0.235515 0.613974 0 10 2 total 0.000000 0.000000 material group in nuclide mean std. dev. -1 10 1 total 0 0 -0 10 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 10 1 total 0.0 0.0 +0 10 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 10 1 1 total P0 0.501009 0.708534 13 10 1 1 total P1 0.265494 0.375465 14 10 1 1 total P2 0.141979 0.200788 @@ -217,12 +217,12 @@ 1 10 2 2 total P1 0.000000 0.000000 2 10 2 2 total P2 0.000000 0.000000 3 10 2 2 total P3 0.000000 0.000000 material group out nuclide mean std. dev. -1 10 1 total 0 0 -0 10 2 total 0 0 material group in nuclide mean std. dev. +1 10 1 total 0.0 0.0 +0 10 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 11 1 total 0.186324 0.632129 0 11 2 total 0.945986 1.591133 material group in nuclide mean std. dev. -1 11 1 total 0 0 -0 11 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 11 1 total 0.0 0.0 +0 11 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 11 1 1 total P0 0.478128 0.676174 13 11 1 1 total P1 0.323679 0.457751 14 11 1 1 total P2 0.143375 0.202763 @@ -239,12 +239,12 @@ 1 11 2 2 total P1 0.286611 0.405329 2 11 2 2 total P2 0.218191 0.308569 3 11 2 2 total P3 -0.048514 0.068609 material group out nuclide mean std. dev. -1 11 1 total 0 0 -0 11 2 total 0 0 material group in nuclide mean std. dev. +1 11 1 total 0.0 0.0 +0 11 2 total 0.0 0.0 material group in nuclide mean std. dev. 1 12 1 total 0.213292 0.271444 0 12 2 total 1.390975 2.137346 material group in nuclide mean std. dev. -1 12 1 total 0 0 -0 12 2 total 0 0 material group in group out nuclide moment mean std. dev. +1 12 1 total 0.0 0.0 +0 12 2 total 0.0 0.0 material group in group out nuclide moment mean std. dev. 12 12 1 1 total P0 0.408594 0.278123 13 12 1 1 total P1 0.222541 0.145776 14 12 1 1 total P2 0.090972 0.069626 @@ -261,5 +261,5 @@ 1 12 2 2 total P1 0.229748 0.324913 2 12 2 2 total P2 0.014178 0.020051 3 12 2 2 total P3 0.038997 0.055150 material group out nuclide mean std. dev. -1 12 1 total 0 0 -0 12 2 total 0 0 \ No newline at end of file +1 12 1 total 0.0 0.0 +0 12 2 total 0.0 0.0 \ No newline at end of file diff --git a/tests/test_mgxs_library_nuclides/results_true.dat b/tests/test_mgxs_library_nuclides/results_true.dat index 1fcfe4aef..06f838206 100644 --- a/tests/test_mgxs_library_nuclides/results_true.dat +++ b/tests/test_mgxs_library_nuclides/results_true.dat @@ -1 +1 @@ -002a4c91c4b4288dbac2cba267175c4560cca43685bfd5d415775e9fc1635866c1f9c3396a44d01dd29f734a0432e132408d36c9f7c4e34783cc295f2d9dc393 \ No newline at end of file +1ee58383dc8ac46c5e0d72321cbc34b0dba531435d5e0e632cbbf9572eb7d669c8c8ad9f370345325afa0bdeb2f818b0f5204b7c4a7c4aaf58ded7acbd715ef8 \ No newline at end of file From fc1734e75a545b2017f9423ba5010da4c4a3852c Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 14 May 2016 10:52:35 -0400 Subject: [PATCH 133/147] Now import warnings module in openmc.statepoint --- openmc/statepoint.py | 2 ++ 1 file changed, 2 insertions(+) diff --git a/openmc/statepoint.py b/openmc/statepoint.py index 19aa3dbaf..d5dd7bc1e 100644 --- a/openmc/statepoint.py +++ b/openmc/statepoint.py @@ -1,6 +1,8 @@ import sys import re import os +import warnings + import numpy as np import openmc From 132fd870d8f8803bc54a851079ec8f92dfea9980 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 14 May 2016 10:57:47 -0400 Subject: [PATCH 134/147] Now expand Legendre scores for ScatterMatrix for all orders --- openmc/mgxs/mgxs.py | 7 +++---- 1 file changed, 3 insertions(+), 4 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index c1255f609..2f9247d18 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1821,10 +1821,9 @@ class ScatterMatrixXS(MGXS): # Expand scores to match the format in the statepoint # e.g., "scatter-P2" -> "scatter-0", "scatter-1", "scatter-2" - if self.legendre_order != 0: - tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) - self.tallies[tally_key].scores = \ - [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] + tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) + self.tallies[tally_key].scores = \ + [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] super(ScatterMatrixXS, self).load_from_statepoint(statepoint) From 87dfd97e5c5beb162678b4a0858f4373ae3063f6 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 14 May 2016 12:33:02 -0400 Subject: [PATCH 135/147] Fixed issue with order=0 ScatterMatrixXS statepoint loading when not using P0 correction --- .../pythonapi/examples/mgxs-part-iii.ipynb | 34 +++++++++---------- openmc/mgxs/mgxs.py | 7 ++-- 2 files changed, 21 insertions(+), 20 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb index ece33e3f5..bc2f96414 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iii.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iii.ipynb @@ -459,7 +459,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -727,7 +727,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 47ef320ad517612376e181ec6a6bc42ca0db98ce\n", - " Date/Time: 2016-05-13 13:14:08\n", + " Date/Time: 2016-05-14 12:29:07\n", " MPI Processes: 1\n", "\n", " ===========================================================================\n", @@ -814,20 +814,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 7.4900E-01 seconds\n", - " Reading cross sections = 2.6400E-01 seconds\n", - " Total time in simulation = 8.0114E+01 seconds\n", - " Time in transport only = 8.0033E+01 seconds\n", - " Time in inactive batches = 6.5120E+00 seconds\n", - " Time in active batches = 7.3602E+01 seconds\n", - " Time synchronizing fission bank = 3.2000E-02 seconds\n", - " Sampling source sites = 3.0000E-03 seconds\n", - " SEND/RECV source sites = 2.8000E-02 seconds\n", - " Time accumulating tallies = 2.0000E-03 seconds\n", + " Total time for initialization = 5.7700E-01 seconds\n", + " Reading cross sections = 1.3400E-01 seconds\n", + " Total time in simulation = 8.0461E+01 seconds\n", + " Time in transport only = 8.0422E+01 seconds\n", + " Time in inactive batches = 6.4060E+00 seconds\n", + " Time in active batches = 7.4055E+01 seconds\n", + " Time synchronizing fission bank = 6.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 3.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 8.0892E+01 seconds\n", - " Calculation Rate (inactive) = 3839.07 neutrons/second\n", - " Calculation Rate (active) = 1358.66 neutrons/second\n", + " Total time elapsed = 8.1067E+01 seconds\n", + " Calculation Rate (inactive) = 3902.59 neutrons/second\n", + " Calculation Rate (active) = 1350.35 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1559,7 +1559,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 43, @@ -1570,7 +1570,7 @@ "data": { "image/png": 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LwOXDO9vT701ffYEZcxn+ZcZs6GBPxNqmg32+8nV3hzgXM8Tk3IcHB7c162x7tuzzNs8x\nYxan28+pt31aNLZ0sS8Cr+PtzwJfbGptxtwmz9gdSrZRsRe1GGJPXrBpfke7jX72ucH76tjbvH43\nOweOLLDPn/+6jz0JQrMVdlvbejcwY4pQw4zRfnZbe1fY52Bn7bfPLS8O8Tk3+wH7PPZtb7QLDmgM\n4I/RF/GTNhGRQ1i0iYgcwqJNROQQFm0iIoewaBMROYRFm4jIISzaREQOYdEmInJIQgbX9Jf5gct7\nr55trmNJoT3IBOvtk+zbNA8xKOY2O+TUm5eYMasf6WXG7GhwUuDy8560B87IYDMEvZ+3n7fssdej\n79vbWELsqiky3IxJR4gLzidZl6GLYi5rgw3m42WLvV/21LG3+cEQEy7UX2u31anInmwk65UjZoxM\ntvvT4vrdZkzdq/bbKwrxvA4etFeDuvZ2znrJbqtn2lIzZuPQbwKX5yATBTGW8ZM2EZFDWLSJiBzC\nok1E5BAWbSIih7BoExE5hEWbiMghLNpERA5h0SYickilBteISCGA3QBKABxR1X7R4jpO3xS4nt8O\nuctuLMceaJH+Z/vE9wfG3GvG5J863oxZ/WWI97ve9mwZ2Qg+yV562+3oIbsd3GjPyqEP2m0djLqH\ny6pd395XW/EHMybEs6o2YXN77Z7YM/m8l3Wu3dAwe1tldQ0xK806e2vJdjsHsn4dIq8X223p+3Zb\nco7dVuaSIns9O+xt2LRJiOdlTCYDALjMbmuS2jPy5OxZF7g8Oz12aa7siMgSAHmququS6yFKNcxt\nSkmVPTwiVbAOolTE3KaUVNmkVADviMhCEbmpKjpElCKY25SSKnt4ZICqbhGRpvASfJWq2ld/Ikp9\nzG1KSZUq2qq6xf9/u4hMA9APwHGJrS+POfZH11zIGXmVaZa+x3bO/AQ7Z66o9nbC5vaRcQ8fvZ02\ncADSB4W4xCFRFMUfzkbJbO+qnmvSYh8EqXDRFpG6ANJUdZ+I1ANwAYAxUWOvya9oM0RlNMo7A43y\nzjj699oxf6vyNuLJ7Rr33l3l7dP3U/qggUgfNBAA0D49A2vH/S5qXGU+aTcHME1E1F/PZFWdUYn1\nEaUK5jalrAoXbVVdB6BHFfaFKCUwtymViWqImVwq04CIYlXwCenFjewZIwY3fd2M2YMsM+Ygapsx\ni58ZaMbcfPsTZsyfl99uxtRuuzNw+XfFTc11yCQzBCVz7QERC149w4zpv2y5GfPv3e2BM22x3oy5\nb0P0r4dl5NSCqiZlHI6IKJbGzu1nu48013GmzjNjjqCmGdO56DMzpv5v7AEvcx+236sy1F5Pvx6f\nmDELltn5VqR2bTjrHnummL3j7M+nn6d3MmMyYM/aMw9nmjG3L58YuDy3HlDQMS1qbvM8VCIih7Bo\nExE5hEWbiMghLNpERA5h0SYicgiLNhGRQ1i0iYgcwqJNROSQyl7lL5zJwYufH/tjcxX/3Hm5GZNR\naJ/0n9vrLTNGDtkDjhZJHzNmTrdeZkz/WcGDVf5x9jnmOi7u+YEZ85s7HzBj7j/8oBkzq3tfM+Y/\n8JQZc/r9wTN3AMB9pz9mxiRb124LYy7bq5nm47sv/sKM2drbngklc6o9wwtid/WoDNivof4j7AFW\nY+2xNXggxHrmv9DNjElbaL9es6bag2JOHv6VGdNi8W4zZkafC8yYLt0WBS7PQSYKYizjJ20iIoew\naBMROYRFm4jIISzaREQOYdEmInIIizYRkUNYtImIHMKiTUTkkMQMrhkRfPJ7zRCzQaQ1sk/6Lx5n\nz3KxpNdpZgzuDJ5pBwD6qz1zTf8r7cED8mrw87q4d4j31SvsiVvGnWNPrqzfRZ27towPatqDffIx\n3oy5+EF7JiKMSMqENHFZ+WnsQVZDT7/SXkFvO9darAiRAy+F2FYfhBg4081ua8xKu638ErutsQEz\njpf6r6X2KB1dZm9DucRuq3nXPWZMmP11mbY1Y0Z9+mTg8iZ1Yy/jJ20iIoewaBMROYRFm4jIISza\nREQOYdEmInIIizYRkUNYtImIHMKiTUTkkIQMrrmv/f2Byw9JTXMdt6s9i8k1j/Q0Y/5HbjFj7tV2\nZkxjud6M+WZqwBnypeuZFDwg6L3FA+x14BszpoFmmzGnmBHAKWLPOLOqxN5+/5q1NkRrqa/L6bFn\nIJmOIebjf7XIHhD2dZ8sM6bFtfbAkJIf2m0tWGbPFJP/E3vQ2Jh0u618+yWE+S+cYcb0D/G89Ca7\nra+72jMNNQuxv/7e93YzJihvAM5cQ0R0wmDRJiJyCIs2EZFDWLSJiBzCok1E5BAWbSIih7BoExE5\nhEWbiMgh5uAaEZkA4BIA21S1m39fQwB/A9AWQCGAq1V1d8x1IHjmmlsLXjA7+sfcn5gx9bDfjHlc\n7zBjGj550IyZdMcIM2aYTDNjGg9ZGbj8NKwy19Hq/Z1mDILHNwEApsy1B4P8eOqrZkzfK2MNC4jQ\n0A7J+IM9YKTor/Z6YqmK3F6xvG/M9Wd2f8bswyd92psxh1HLjKl79WdmTOaSIjOmKM0ePDL/LyEG\n4CyzB+CEWU8R7P6gd3B9AYA9V9cwYzZKazNma5/DZkym7jVjVi6PPeMRADSpF3tZmE/aEwFcWO6+\nUQDeVdXOAN4HcG+I9RClGuY2Occs2qo6G8CucncPBVD68fgFAJdVcb+Iqh1zm1xU0WPazVR1GwCo\n6lYAzaquS0RJxdymlFZVP0TaB5WI3MTcppRS0av8bROR5qq6TURaAPg6KLhg9IdHb7fNa4OcPHuK\neaJoSuZ8CJ0zuzqbiCu38dzoY7f75AF986qxa3RCWzgTWDQTAFAYcOHTsEVb/H+l3gAwEsDvAIwA\nMD3owbmjB4VshihY2oBBwIBj+VT0yPjKrrJSuY1bR1e2fSJP37yjb/o59YD1T42NGmYeHhGRlwDM\nBdBJRDaIyE8BjAdwvoh8BuBc/28ipzC3yUXmJ21VvTbGovOquC9ECcXcJheJavX+ziIieoc+FBiz\nsCT2AIVSs+Vcu7HP7N9VNU3MGOlYbLe1OkRb/wjR1l3Bbb0L+9DSeVPnmjG4yn5Om9DEjGn1fPkz\n5KK4xW5rBnLNmGuKXzZjdtU4Gapqb+hqICJae9eOmMsLG9hzATVDzHE7x/Szc61knb0J0raHyOtf\nh8jrxSHy+v0QbZ0Toq2+Idp62G5Lm4Y456JdiLbm2219jQZmTNvdhYHLB6Vn4N2sBlFzm8PYiYgc\nwqJNROQQFm0iIoewaBMROYRFm4jIISzaREQOYdEmInIIizYRkUMqesGouEw6NDJw+e9r3WWuY2XJ\nLWZM16ftvkhHezBRyUv2bBkT8q8zYw6das84cn1x7cDlOzIuMtex66qAq8v4Gj5hP6dW7ext88Yt\n55sxlz5kt/X0fVPMmEHps+z+mBHVq32DtTGX3YA/m49/83V7W+37xO7HgUP2vmvS1G7ru612Sch6\nxZ4BRy8NMePMzXbIvqvs9dRrYsfsCDG5U5199jasP81u66eXTzVjOjRYE7i8FTJjLuMnbSIih7Bo\nExE5hEWbiMghLNpERA5h0SYicgiLNhGRQ1i0iYgcwqJNROSQhMxcg44lgTE15u0x13NDo4lmzHO4\nw+7P6BDvUyEmE9EQE3NMe8oeGHOargpcfrc8bK5jDPLNmMNqD8DZo1lmzPliD3iZg95mzIAFH5sx\nm/o3MmNay86kzlyDv8fO7ZZDggdQAMCm+Z3shvrbyba3jp3XmWfYTS1a0MWMaY2NZkzzFfZremtX\ne4aXr3CyGdOn70ozZs8KO0WyDoR4US+wt3N2vy/NmK1vtAtcntsYKBiUxplriIhcx6JNROQQFm0i\nIoewaBMROYRFm4jIISzaREQOYdEmInIIizYRkUMSMnONFOwPXH7kr/agjoO/sAeH6EZ7VomX84ea\nMdfINDNmTJr9ftfwmbfNmGHFwSf0v7HJbkf/aQ8ckBvtgQPvpJ1txrxYcrUZM3LVIjPm8n6TzZgw\ngziA+0LEVKPxsbf9ljHtzYenD7VngSmGndf1J4cYX3S5nQM1YQ/2abZor91Wn+ABdQDQYrGd29t6\nN7PbWmi3lTUtxOvoI3s7p79tt4V/t0NQ29hfPWMv4idtIiKHsGgTETmERZuIyCEs2kREDmHRJiJy\nCIs2EZFDWLSJiBzCok1E5BBzcI2ITABwCYBtqtrNvy8fwE0AvvbDfqOqb8VaR2bD4JPx95xa1+zo\nZrQyYzKm2gMVpt1pzyajve2T7NeUPG/GNNHtZszh3cFt3Zhtt3PgxjpmTC5uMmOWqT1w5tXDV5ox\n2tP+LPDaL683Y9o9bM9IUpnBNVWR2/hodEAL55l9UAwwY1o98LkZ0xNLzZg/w54pZq4MM2Pe7nOh\nGTMUbc2Y6b1vN2MyxR7I01Lt5/XTYa+aMR9rDzMGt9khWDo7RNB7wYtrxd5+YT5pTwQQbS89pqq9\n/H+xk5oodTG3yTlm0VbV2QB2RVmUlHn5iKoKc5tcVJlj2j8XkaUi8r8iYn8/IXIHc5tSVkUvGPUs\ngLGqqiLyWwCPAfhZrOCDv330WINnn4WMs8+qYLP0fXdg5kIcmLmwOpuIK7eBmRG3c/x/RBVR6P8D\nCgtjf1aoUNFWLfML258AvBkUX/v+X1WkGaLj1Mnrizp5fY/+/e2Y56p0/fHmNpBXpe3T91kOSt/0\nc3LaYv36N6JGhT08Iog4ziciLSKWXQ5gRQV6SJQKmNvklDCn/L0E7+NEYxHZACAfwDki0gNACbzP\n87dUYx+JqgVzm1xkFm1VvTbK3ROroS9ECcXcJheJqlZvAyKKT4zZHs4KcYbVO3Y/L+przzjz9o2X\nmTHjJtxhxty74VE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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 2f9247d18..34a5b88b5 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -1821,9 +1821,10 @@ class ScatterMatrixXS(MGXS): # Expand scores to match the format in the statepoint # e.g., "scatter-P2" -> "scatter-0", "scatter-1", "scatter-2" - tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) - self.tallies[tally_key].scores = \ - [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] + if self.correction != 'P0' or self.legendre_order != 0: + tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order) + self.tallies[tally_key].scores = \ + [self.rxn_type + '-{}'.format(i) for i in range(self.legendre_order+1)] super(ScatterMatrixXS, self).load_from_statepoint(statepoint) From 4bec584ddb7d07be7d92ad9d037e8363b2f25614 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 14 May 2016 13:04:27 -0400 Subject: [PATCH 136/147] Removed *_id setting in example notebook IV, since they are not needed, just as @wbinventor said. I owe this man a beer. --- .../pythonapi/examples/mgxs-part-iv.ipynb | 94 +++++++++---------- 1 file changed, 47 insertions(+), 47 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index b81e8f06b..d15f265d4 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -83,19 +83,19 @@ "outputs": [], "source": [ "# 1.6 enriched fuel\n", - "fuel = openmc.Material(name='1.6% Fuel', material_id=1)\n", + "fuel = openmc.Material(name='1.6% Fuel')\n", "fuel.set_density('g/cm3', 10.31341)\n", "fuel.add_nuclide(u235, 3.7503e-4)\n", "fuel.add_nuclide(u238, 2.2625e-2)\n", "fuel.add_nuclide(o16, 4.6007e-2)\n", "\n", "# zircaloy\n", - "zircaloy = openmc.Material(name='Zircaloy', material_id=2)\n", + "zircaloy = openmc.Material(name='Zircaloy')\n", "zircaloy.set_density('g/cm3', 6.55)\n", "zircaloy.add_nuclide(zr90, 7.2758e-3)\n", "\n", "# borated water\n", - "water = openmc.Material(name='Borated Water', material_id=3)\n", + "water = openmc.Material(name='Borated Water')\n", "water.set_density('g/cm3', 0.740582)\n", "water.add_nuclide(h1, 4.9457e-2)\n", "water.add_nuclide(o16, 2.4732e-2)\n", @@ -169,22 +169,22 @@ "outputs": [], "source": [ "# Create a Universe to encapsulate a fuel pin\n", - "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin', universe_id=10)\n", + "fuel_pin_universe = openmc.Universe(name='1.6% Fuel Pin')\n", "\n", "# Create fuel Cell\n", - "fuel_cell = openmc.Cell(name='1.6% Fuel', cell_id=1)\n", + "fuel_cell = openmc.Cell(name='1.6% Fuel')\n", "fuel_cell.fill = fuel\n", "fuel_cell.region = -fuel_outer_radius\n", "fuel_pin_universe.add_cell(fuel_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='1.6% Clad', cell_id=2)\n", + "clad_cell = openmc.Cell(name='1.6% Clad')\n", "clad_cell.fill = zircaloy\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "fuel_pin_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='1.6% Moderator', cell_id=3)\n", + "moderator_cell = openmc.Cell(name='1.6% Moderator')\n", "moderator_cell.fill = water\n", "moderator_cell.region = +clad_outer_radius\n", "fuel_pin_universe.add_cell(moderator_cell)" @@ -206,22 +206,22 @@ "outputs": [], "source": [ "# Create a Universe to encapsulate a control rod guide tube\n", - "guide_tube_universe = openmc.Universe(name='Guide Tube', universe_id=20)\n", + "guide_tube_universe = openmc.Universe(name='Guide Tube')\n", "\n", "# Create guide tube Cell\n", - "guide_tube_cell = openmc.Cell(name='Guide Tube Water', cell_id=4)\n", + "guide_tube_cell = openmc.Cell(name='Guide Tube Water')\n", "guide_tube_cell.fill = water\n", "guide_tube_cell.region = -fuel_outer_radius\n", "guide_tube_universe.add_cell(guide_tube_cell)\n", "\n", "# Create a clad Cell\n", - "clad_cell = openmc.Cell(name='Guide Clad', cell_id=5)\n", + "clad_cell = openmc.Cell(name='Guide Clad')\n", "clad_cell.fill = zircaloy\n", "clad_cell.region = +fuel_outer_radius & -clad_outer_radius\n", "guide_tube_universe.add_cell(clad_cell)\n", "\n", "# Create a moderator Cell\n", - "moderator_cell = openmc.Cell(name='Guide Tube Moderator', cell_id=6)\n", + "moderator_cell = openmc.Cell(name='Guide Tube Moderator')\n", "moderator_cell.fill = water\n", "moderator_cell.region = +clad_outer_radius\n", "guide_tube_universe.add_cell(moderator_cell)" @@ -243,7 +243,7 @@ "outputs": [], "source": [ "# Create fuel assembly Lattice\n", - "assembly = openmc.RectLattice(name='1.6% Fuel Assembly', lattice_id=100)\n", + "assembly = openmc.RectLattice(name='1.6% Fuel Assembly')\n", "assembly.dimension = (17, 17)\n", "assembly.pitch = (1.26, 1.26)\n", "assembly.lower_left = [-1.26 * 17. / 2.0] * 2" @@ -297,14 +297,14 @@ "outputs": [], "source": [ "# Create root Cell\n", - "root_cell = openmc.Cell(name='root cell', cell_id=0)\n", + "root_cell = openmc.Cell(name='root cell')\n", "root_cell.fill = assembly\n", "\n", "# Add boundary planes\n", "root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z\n", "\n", "# Create root Universe\n", - "root_universe = openmc.Universe(universe_id=0, name='root universe')\n", + "root_universe = openmc.Universe(name='root universe')\n", "root_universe.add_cell(root_cell)" ] }, @@ -382,7 +382,7 @@ "outputs": [], "source": [ "# Instantiate a Plot\n", - "plot = openmc.Plot(plot_id=1)\n", + "plot = openmc.Plot()\n", "plot.filename = 'materials-xy'\n", "plot.origin = [0, 0, 0]\n", "plot.pixels = [250, 250]\n", @@ -433,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -637,7 +637,7 @@ "outputs": [], "source": [ "# Instantiate a tally Mesh\n", - "mesh = openmc.Mesh(mesh_id=1)\n", + "mesh = openmc.Mesh()\n", "mesh.type = 'regular'\n", "mesh.dimension = [17, 17]\n", "mesh.lower_left = [-10.71, -10.71]\n", @@ -696,7 +696,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-14 07:56:31\n", + " Date/Time: 2016-05-14 12:59:34\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -783,20 +783,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4930E+00 seconds\n", - " Reading cross sections = 1.1850E+00 seconds\n", - " Total time in simulation = 1.9053E+01 seconds\n", - " Time in transport only = 1.9002E+01 seconds\n", - " Time in inactive batches = 2.0890E+00 seconds\n", - " Time in active batches = 1.6964E+01 seconds\n", - " Time synchronizing fission bank = 6.0000E-03 seconds\n", - " Sampling source sites = 5.0000E-03 seconds\n", + " Total time for initialization = 1.4720E+00 seconds\n", + " Reading cross sections = 1.1730E+00 seconds\n", + " Total time in simulation = 1.9211E+01 seconds\n", + " Time in transport only = 1.9108E+01 seconds\n", + " Time in inactive batches = 2.1390E+00 seconds\n", + " Time in active batches = 1.7072E+01 seconds\n", + " Time synchronizing fission bank = 1.0000E-02 seconds\n", + " Sampling source sites = 9.0000E-03 seconds\n", " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.0556E+01 seconds\n", - " Calculation Rate (inactive) = 23934.9 neutrons/second\n", - " Calculation Rate (active) = 11789.7 neutrons/second\n", + " Total time elapsed = 2.0692E+01 seconds\n", + " Calculation Rate (inactive) = 23375.4 neutrons/second\n", + " Calculation Rate (active) = 11715.1 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -950,7 +950,7 @@ "source": [ "# Create a MGXS File which can then be written to disk\n", "mgxs_file = mgxs_lib.create_mg_library(xs_type='macro', domain_names=['fuel', 'zircaloy', 'water'],\n", - " xs_ids='2m')\n", + " xs_ids='2m')\n", "\n", "# Write the file to disk using the default filename of `mgxs.xml`\n", "mgxs_file.export_to_xml()" @@ -983,15 +983,15 @@ "# Now re-define our materials to use the Multi-Group macroscopic data\n", "# instead of the continuous-energy data.\n", "# 1.6 enriched fuel UO2\n", - "fuel = openmc.Material(name='UO2', material_id=1)\n", + "fuel = openmc.Material(name='UO2')\n", "fuel.add_macroscopic(fuel_macro)\n", "\n", "# cladding\n", - "zircaloy = openmc.Material(name='Clad', material_id=2)\n", + "zircaloy = openmc.Material(name='Clad')\n", "zircaloy.add_macroscopic(zircaloy_macro)\n", "\n", "# moderator\n", - "water = openmc.Material(name='Water', material_id=3)\n", + "water = openmc.Material(name='Water')\n", "water.add_macroscopic(water_macro)\n", "\n", "# Finally, instantiate our Materials object\n", @@ -1071,7 +1071,7 @@ " License: http://openmc.readthedocs.org/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-14 07:56:52\n", + " Date/Time: 2016-05-14 12:59:55\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1156,19 +1156,19 @@ " =======================> TIMING STATISTICS <=======================\n", "\n", " Total time for initialization = 4.0000E-02 seconds\n", - " Reading cross sections = 6.0000E-03 seconds\n", - " Total time in simulation = 1.2540E+01 seconds\n", - " Time in transport only = 1.2496E+01 seconds\n", - " Time in inactive batches = 1.1110E+00 seconds\n", - " Time in active batches = 1.1429E+01 seconds\n", - " Time synchronizing fission bank = 7.0000E-03 seconds\n", - " Sampling source sites = 5.0000E-03 seconds\n", - " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Reading cross sections = 3.0000E-03 seconds\n", + " Total time in simulation = 1.3223E+01 seconds\n", + " Time in transport only = 1.3175E+01 seconds\n", + " Time in inactive batches = 1.1160E+00 seconds\n", + " Time in active batches = 1.2107E+01 seconds\n", + " Time synchronizing fission bank = 9.0000E-03 seconds\n", + " Sampling source sites = 8.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.2589E+01 seconds\n", - " Calculation Rate (inactive) = 45004.5 neutrons/second\n", - " Calculation Rate (active) = 17499.3 neutrons/second\n", + " Total time elapsed = 1.3272E+01 seconds\n", + " Calculation Rate (inactive) = 44802.9 neutrons/second\n", + " Calculation Rate (active) = 16519.4 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1355,7 +1355,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 40, @@ -1366,7 +1366,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, From 2ea3466206f48b2e19c77bf216925542c522ec58 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Sat, 14 May 2016 22:29:38 -0400 Subject: [PATCH 137/147] Hotfix for making elements isotropic in lab through Material.make_isotropic_in_lab() method --- openmc/material.py | 2 +- 1 file changed, 1 insertion(+), 1 deletion(-) diff --git a/openmc/material.py b/openmc/material.py index e9a74f1e7..bf66cf11d 100644 --- a/openmc/material.py +++ b/openmc/material.py @@ -506,7 +506,7 @@ class Material(object): for nuclide_name in self._nuclides: self._nuclides[nuclide_name][0].scattering = 'iso-in-lab' for element_name in self._elements: - self._element[element_name][0].scattering = 'iso-in-lab' + self._elements[element_name][0].scattering = 'iso-in-lab' def get_all_nuclides(self): """Returns all nuclides in the material From 394d8385c3b814fe27ad1cc5872921719a1bd724 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Sun, 15 May 2016 11:24:25 -0500 Subject: [PATCH 138/147] Fix spaces around % as suggested by @smharper --- src/particle_restart.F90 | 28 ++++++++++++++-------------- src/state_point.F90 | 14 +++++++------- 2 files changed, 21 insertions(+), 21 deletions(-) diff --git a/src/particle_restart.F90 b/src/particle_restart.F90 index 4040a471a..e5cca17bf 100644 --- a/src/particle_restart.F90 +++ b/src/particle_restart.F90 @@ -34,7 +34,7 @@ contains verbosity = 10 ! Initialize the particle to be tracked - call p%initialize() + call p % initialize() ! Read in the restart information call read_particle_restart(p, previous_run_mode) @@ -46,9 +46,9 @@ contains select case (previous_run_mode) case (MODE_EIGENVALUE) particle_seed = ((current_batch - 1)*gen_per_batch + & - current_gen - 1)*n_particles + p%id + current_gen - 1)*n_particles + p % id case (MODE_FIXEDSOURCE) - particle_seed = p%id + particle_seed = p % id end select call set_particle_seed(particle_seed) @@ -94,19 +94,19 @@ contains case ('fixed source') previous_run_mode = MODE_FIXEDSOURCE end select - call read_dataset(p%id, file_id, 'id') - call read_dataset(p%wgt, file_id, 'weight') - call read_dataset(p%E, file_id, 'energy') - call read_dataset(p%g, file_id, 'energy_group') - call read_dataset(p%coord(1)%xyz, file_id, 'xyz') - call read_dataset(p%coord(1)%uvw, file_id, 'uvw') + call read_dataset(p % id, file_id, 'id') + call read_dataset(p % wgt, file_id, 'weight') + call read_dataset(p % E, file_id, 'energy') + call read_dataset(p % g, file_id, 'energy_group') + call read_dataset(p % coord(1) % xyz, file_id, 'xyz') + call read_dataset(p % coord(1) % uvw, file_id, 'uvw') ! Set particle last attributes - p%last_wgt = p%wgt - p%last_xyz = p%coord(1)%xyz - p%last_uvw = p%coord(1)%uvw - p%last_E = p%E - p%last_g = p%g + p % last_wgt = p % wgt + p % last_xyz = p % coord(1)%xyz + p % last_uvw = p % coord(1)%uvw + p % last_E = p % E + p % last_g = p % g ! Close hdf5 file call file_close(file_id) diff --git a/src/state_point.F90 b/src/state_point.F90 index 81abf0c1b..0006d3042 100644 --- a/src/state_point.F90 +++ b/src/state_point.F90 @@ -782,16 +782,16 @@ contains ! Read in CMFD info if (int_array(1) == 1) then cmfd_group = open_group(file_id, "cmfd") - call read_dataset(cmfd%indices, cmfd_group, "indices") - call read_dataset(cmfd%k_cmfd(1:restart_batch), cmfd_group, "k_cmfd") - call read_dataset(cmfd%cmfd_src, cmfd_group, "cmfd_src") - call read_dataset(cmfd%entropy(1:restart_batch), cmfd_group, & + call read_dataset(cmfd % indices, cmfd_group, "indices") + call read_dataset(cmfd % k_cmfd(1:restart_batch), cmfd_group, "k_cmfd") + call read_dataset(cmfd % cmfd_src, cmfd_group, "cmfd_src") + call read_dataset(cmfd % entropy(1:restart_batch), cmfd_group, & "cmfd_entropy") - call read_dataset(cmfd%balance(1:restart_batch), cmfd_group, & + call read_dataset(cmfd % balance(1:restart_batch), cmfd_group, & "cmfd_balance") - call read_dataset(cmfd%dom(1:restart_batch), cmfd_group, & + call read_dataset(cmfd % dom(1:restart_batch), cmfd_group, & "cmfd_dominance") - call read_dataset(cmfd%src_cmp(1:restart_batch), cmfd_group, & + call read_dataset(cmfd % src_cmp(1:restart_batch), cmfd_group, & "cmfd_srccmp") call close_group(cmfd_group) end if From 071e8d3e305532b9e53f747af6ac533ed01fc17d Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 15 May 2016 14:26:54 -0400 Subject: [PATCH 139/147] Forgot universe_id=0 for root in example nb (fixed), resolved comments from @paulromano, and made sure the example problem worked still (it did, but I simplified it a bit since data doesnt need to be numpy arrays anymore. --- .../pythonapi/examples/mgxs-part-iv.ipynb | 72 ++++++------ docs/source/usersguide/mgxs_library.rst | 6 +- .../python/pincell_multigroup/build-xml.py | 71 ++++++------ openmc/mgxs/library.py | 46 +++++--- openmc/mgxs/mgxs.py | 2 +- openmc/mgxs_library.py | 108 ++++++++++++------ 6 files changed, 172 insertions(+), 133 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index d15f265d4..4509f0fc8 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -304,7 +304,7 @@ "root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z\n", "\n", "# Create root Universe\n", - "root_universe = openmc.Universe(name='root universe')\n", + "root_universe = openmc.Universe(name='root universe', universe_id=0)\n", "root_universe.add_cell(root_cell)" ] }, @@ -319,7 +319,7 @@ "cell_type": "code", "execution_count": 11, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ @@ -433,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -693,10 +693,10 @@ " 888\n", "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", - " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-14 12:59:34\n", + " Git SHA1: 4bec584ddb7d07be7d92ad9d037e8363b2f25614\n", + " Date/Time: 2016-05-15 14:22:34\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -783,20 +783,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4720E+00 seconds\n", - " Reading cross sections = 1.1730E+00 seconds\n", - " Total time in simulation = 1.9211E+01 seconds\n", - " Time in transport only = 1.9108E+01 seconds\n", - " Time in inactive batches = 2.1390E+00 seconds\n", - " Time in active batches = 1.7072E+01 seconds\n", - " Time synchronizing fission bank = 1.0000E-02 seconds\n", - " Sampling source sites = 9.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", + " Total time for initialization = 1.4620E+00 seconds\n", + " Reading cross sections = 1.1520E+00 seconds\n", + " Total time in simulation = 2.1015E+01 seconds\n", + " Time in transport only = 2.0844E+01 seconds\n", + " Time in inactive batches = 2.2260E+00 seconds\n", + " Time in active batches = 1.8789E+01 seconds\n", + " Time synchronizing fission bank = 9.0000E-03 seconds\n", + " Sampling source sites = 5.0000E-03 seconds\n", + " SEND/RECV source sites = 4.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.0692E+01 seconds\n", - " Calculation Rate (inactive) = 23375.4 neutrons/second\n", - " Calculation Rate (active) = 11715.1 neutrons/second\n", + " Total time elapsed = 2.2491E+01 seconds\n", + " Calculation Rate (inactive) = 22461.8 neutrons/second\n", + " Calculation Rate (active) = 10644.5 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -949,7 +949,7 @@ ], "source": [ "# Create a MGXS File which can then be written to disk\n", - "mgxs_file = mgxs_lib.create_mg_library(xs_type='macro', domain_names=['fuel', 'zircaloy', 'water'],\n", + "mgxs_file = mgxs_lib.create_mg_library(xs_type='macro', xsdata_names=['fuel', 'zircaloy', 'water'],\n", " xs_ids='2m')\n", "\n", "# Write the file to disk using the default filename of `mgxs.xml`\n", @@ -1068,10 +1068,10 @@ " 888\n", "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", - " License: http://openmc.readthedocs.org/en/latest/license.html\n", + " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: c779ca42c41a062a6a813e03f2add2d182ca9190\n", - " Date/Time: 2016-05-14 12:59:55\n", + " Git SHA1: 4bec584ddb7d07be7d92ad9d037e8363b2f25614\n", + " Date/Time: 2016-05-15 14:22:57\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1155,20 +1155,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.0000E-02 seconds\n", + " Total time for initialization = 3.5000E-02 seconds\n", " Reading cross sections = 3.0000E-03 seconds\n", - " Total time in simulation = 1.3223E+01 seconds\n", - " Time in transport only = 1.3175E+01 seconds\n", - " Time in inactive batches = 1.1160E+00 seconds\n", - " Time in active batches = 1.2107E+01 seconds\n", - " Time synchronizing fission bank = 9.0000E-03 seconds\n", - " Sampling source sites = 8.0000E-03 seconds\n", + " Total time in simulation = 1.2599E+01 seconds\n", + " Time in transport only = 1.2565E+01 seconds\n", + " Time in inactive batches = 1.1220E+00 seconds\n", + " Time in active batches = 1.1477E+01 seconds\n", + " Time synchronizing fission bank = 6.0000E-03 seconds\n", + " Sampling source sites = 5.0000E-03 seconds\n", " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.3272E+01 seconds\n", - " Calculation Rate (inactive) = 44802.9 neutrons/second\n", - " Calculation Rate (active) = 16519.4 neutrons/second\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for finalization = 1.0000E-03 seconds\n", + " Total time elapsed = 1.2644E+01 seconds\n", + " Calculation Rate (inactive) = 44563.3 neutrons/second\n", + " Calculation Rate (active) = 17426.2 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1355,7 +1355,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 40, @@ -1366,7 +1366,7 @@ "data": { "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/docs/source/usersguide/mgxs_library.rst b/docs/source/usersguide/mgxs_library.rst index 8628bef4e..98a9e8485 100644 --- a/docs/source/usersguide/mgxs_library.rst +++ b/docs/source/usersguide/mgxs_library.rst @@ -22,9 +22,9 @@ materials. .. _XML: http://www.w3.org/XML/ ------------------------------------------------- +-------------------------------------- MGXS Library Specification -- mgxs.xml ------------------------------------------------- +-------------------------------------- The multi-group library meta-data is contained within the groups_, group_structure_, and inverse_velocities_ elements. @@ -33,7 +33,7 @@ The actual multi-group data itself is contained within the xsdata_ element. .. _groups: ```` Element ----------------------------------- +-------------------- The ```` element has no attributes and simply provides the number of energy groups contained within the library. diff --git a/examples/python/pincell_multigroup/build-xml.py b/examples/python/pincell_multigroup/build-xml.py index c7d6dfc8b..5ac5b376a 100644 --- a/examples/python/pincell_multigroup/build-xml.py +++ b/examples/python/pincell_multigroup/build-xml.py @@ -1,4 +1,3 @@ -import numpy as np import openmc import openmc.mgxs @@ -12,7 +11,7 @@ inactive = 10 particles = 1000 ############################################################################### -# Exporting to OpenMC mg_cross_sections.xml file +# Exporting to OpenMC mgxs.xml file ############################################################################### # Instantiate the energy group data @@ -22,45 +21,43 @@ groups = openmc.mgxs.EnergyGroups(group_edges=[1E-11, 0.0635E-6, 10.0E-6, # Instantiate the 7-group (C5G7) cross section data uo2_xsdata = openmc.XSdata('UO2.300K', groups) uo2_xsdata.order = 0 -uo2_xsdata.total = np.array([0.1779492, 0.3298048, 0.4803882, 0.5543674, - 0.3118013, 0.3951678, 0.5644058]) -uo2_xsdata.absorption = np.array([8.0248E-03, 3.7174E-03, 2.6769E-02, 9.6236E-02, - 3.0020E-02, 1.1126E-01, 2.8278E-01]) -scatter = [[[0.1275370, 0.0423780, 0.0000094, 0.0000000, 0.0000000, 0.0000000, 0.0000000], - [0.0000000, 0.3244560, 0.0016314, 0.0000000, 0.0000000, 0.0000000, 0.0000000], - [0.0000000, 0.0000000, 0.4509400, 0.0026792, 0.0000000, 0.0000000, 0.0000000], - [0.0000000, 0.0000000, 0.0000000, 0.4525650, 0.0055664, 0.0000000, 0.0000000], - [0.0000000, 0.0000000, 0.0000000, 0.0001253, 0.2714010, 0.0102550, 0.0000000], - [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0012968, 0.2658020, 0.0168090], - [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0085458, 0.2730800]]] -uo2_xsdata.scatter = np.array(scatter[:][:]) -uo2_xsdata.fission = np.array([7.21206E-03, 8.19301E-04, 6.45320E-03, - 1.85648E-02, 1.78084E-02, 8.30348E-02, - 2.16004E-01]) -uo2_xsdata.nu_fission = np.array([2.005998E-02, 2.027303E-03, 1.570599E-02, - 4.518301E-02, 4.334208E-02, 2.020901E-01, - 5.257105E-01]) -uo2_xsdata.chi = np.array([5.8791E-01, 4.1176E-01, 3.3906E-04, 1.1761E-07, - 0.0000E+00, 0.0000E+00, 0.0000E+00]) +uo2_xsdata.total = [0.1779492, 0.3298048, 0.4803882, 0.5543674, + 0.3118013, 0.3951678, 0.5644058] +uo2_xsdata.absorption = [8.0248E-03, 3.7174E-03, 2.6769E-02, 9.6236E-02, + 3.0020E-02, 1.1126E-01, 2.8278E-01] +uo2_xsdata.scatter = [[[0.1275370, 0.0423780, 0.0000094, 0.0000000, 0.0000000, 0.0000000, 0.0000000], + [0.0000000, 0.3244560, 0.0016314, 0.0000000, 0.0000000, 0.0000000, 0.0000000], + [0.0000000, 0.0000000, 0.4509400, 0.0026792, 0.0000000, 0.0000000, 0.0000000], + [0.0000000, 0.0000000, 0.0000000, 0.4525650, 0.0055664, 0.0000000, 0.0000000], + [0.0000000, 0.0000000, 0.0000000, 0.0001253, 0.2714010, 0.0102550, 0.0000000], + [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0012968, 0.2658020, 0.0168090], + [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0085458, 0.2730800]]] +uo2_xsdata.fission = [7.21206E-03, 8.19301E-04, 6.45320E-03, + 1.85648E-02, 1.78084E-02, 8.30348E-02, + 2.16004E-01] +uo2_xsdata.nu_fission = [2.005998E-02, 2.027303E-03, 1.570599E-02, + 4.518301E-02, 4.334208E-02, 2.020901E-01, + 5.257105E-01] +uo2_xsdata.chi = [5.8791E-01, 4.1176E-01, 3.3906E-04, 1.1761E-07, + 0.0000E+00, 0.0000E+00, 0.0000E+00] h2o_xsdata = openmc.XSdata('LWTR.300K', groups) h2o_xsdata.order = 0 -h2o_xsdata.total = np.array([0.15920605, 0.412969593, 0.59030986, 0.58435, - 0.718, 1.2544497, 2.650379]) -h2o_xsdata.absorption = np.array([6.0105E-04, 1.5793E-05, 3.3716E-04, - 1.9406E-03, 5.7416E-03, 1.5001E-02, - 3.7239E-02]) -scatter = [[[0.0444777, 0.1134000, 0.0007235, 0.0000037, 0.0000001, 0.0000000, 0.0000000], - [0.0000000, 0.2823340, 0.1299400, 0.0006234, 0.0000480, 0.0000074, 0.0000010], - [0.0000000, 0.0000000, 0.3452560, 0.2245700, 0.0169990, 0.0026443, 0.0005034], - [0.0000000, 0.0000000, 0.0000000, 0.0910284, 0.4155100, 0.0637320, 0.0121390], - [0.0000000, 0.0000000, 0.0000000, 0.0000714, 0.1391380, 0.5118200, 0.0612290], - [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0022157, 0.6999130, 0.5373200], - [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.1324400, 2.4807000]]] -h2o_xsdata.scatter = np.array(scatter) +h2o_xsdata.total = [0.15920605, 0.412969593, 0.59030986, 0.58435, + 0.718, 1.2544497, 2.650379] +h2o_xsdata.absorption = [6.0105E-04, 1.5793E-05, 3.3716E-04, + 1.9406E-03, 5.7416E-03, 1.5001E-02, + 3.7239E-02] +h2o_xsdata.scatter = [[[0.0444777, 0.1134000, 0.0007235, 0.0000037, 0.0000001, 0.0000000, 0.0000000], + [0.0000000, 0.2823340, 0.1299400, 0.0006234, 0.0000480, 0.0000074, 0.0000010], + [0.0000000, 0.0000000, 0.3452560, 0.2245700, 0.0169990, 0.0026443, 0.0005034], + [0.0000000, 0.0000000, 0.0000000, 0.0910284, 0.4155100, 0.0637320, 0.0121390], + [0.0000000, 0.0000000, 0.0000000, 0.0000714, 0.1391380, 0.5118200, 0.0612290], + [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0022157, 0.6999130, 0.5373200], + [0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.0000000, 0.1324400, 2.4807000]]] mg_cross_sections_file = openmc.MGXSLibrary(groups) -mg_cross_sections_file.add_xsdatas([uo2_xsdata,h2o_xsdata]) +mg_cross_sections_file.add_xsdatas([uo2_xsdata, h2o_xsdata]) mg_cross_sections_file.export_to_xml() @@ -134,7 +131,7 @@ geometry.export_to_xml() # Instantiate a Settings object, set all runtime parameters, and export to XML settings_file = openmc.Settings() settings_file.energy_mode = "multi-group" -settings_file.cross_sections = "./mg_cross_sections.xml" +settings_file.cross_sections = "./mgxs.xml" settings_file.batches = batches settings_file.inactive = inactive settings_file.particles = particles diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 44746e209..586302a4b 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -247,8 +247,7 @@ class Library(object): @domain_type.setter def domain_type(self, domain_type): - cv.check_value('domain type', domain_type, - tuple(openmc.mgxs.DOMAIN_TYPES)) + cv.check_value('domain type', domain_type, openmc.mgxs.DOMAIN_TYPES) self._domain_type = domain_type @domains.setter @@ -722,8 +721,8 @@ class Library(object): # Load and return pickled Library object return pickle.load(open(full_filename, 'rb')) - def get_xsdata(self, domain, domain_name, nuclide='total', xs_type='macro', - xs_id='1m', order=-1): + def get_xsdata(self, domain, xsdata_name, nuclide='total', xs_type='macro', + xs_id='1m', order=None): """Generates an openmc.XSdata object describing a multi-group cross section data set for eventual combination in to an openmc.MGXSLibrary object (i.e., the library). @@ -732,7 +731,7 @@ class Library(object): ---------- domain : openmc.Material or openmc.Cell or openmc.Universe The domain for spatial homogenization - domain_name : str + xsdata_name : str Name to apply to the "xsdata" entry produced by this method nuclide : str A nuclide name string (e.g., 'U-235'). Defaults to 'total' to @@ -743,7 +742,7 @@ class Library(object): nuclide this will be set to 'macro' regardless. xs_ids : str Cross section set identifier. Defaults to '1m'. - order : Scattering order for this dataset entry. Default is -1, + order : Scattering order for this dataset entry. Default is None, which will force the XSdata object to use whatever the maximum order available. @@ -766,11 +765,11 @@ class Library(object): cv.check_type('domain', domain, (openmc.Material, openmc.Cell, openmc.Cell)) - cv.check_type('domain_name', domain_name, basestring) + cv.check_type('xsdata_name', xsdata_name, basestring) cv.check_type('nuclide', nuclide, basestring) cv.check_value('xs_type', xs_type, ['macro', 'micro']) cv.check_type('xs_id', xs_id, basestring) - cv.check_type('order', order, Integral) + cv.check_type('order', order, (type(None), Integral)) cv.check_greater_than('order', order, -1, equality=True) # Make sure statepoint has been loaded @@ -784,12 +783,18 @@ class Library(object): xs_type = 'macro' # Build & add metadata to XSdata object - name = domain_name + name = xsdata_name if nuclide is not 'total': name += '_' + nuclide name += '.' + xs_id xsdata = openmc.XSdata(name, self.energy_groups) - xsdata.order = order + if order is 0: + xsdata.order = order + else: + msg = 'Generating anisotropic scattering from openmc.Library' \ + 'objects has not yet been implemented.' + raise NotImplementedError(msg) + if nuclide is not 'total': xsdata.zaid = self._nuclides[nuclide][0] xsdata.awr = self._nuclides[nuclide][1] @@ -852,7 +857,7 @@ class Library(object): return xsdata - def create_mg_library(self, xs_type='macro', domain_names=None, + def create_mg_library(self, xs_type='macro', xsdata_names=None, xs_ids=None): """Creates an openmc.MGXSLibrary object to contain the MGXS data for the Multi-Group mode of OpenMC. @@ -863,7 +868,7 @@ class Library(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. If the Library object is not tallied by nuclide this will be set to 'macro' regardless. - domain_names : Iterable of str + xsdata_names : Iterable of str List of names to apply to the "xsdata" entries in the resultant mgxs data file. Defaults to 'set1', 'set2', ... xs_ids : str or Iterable of str @@ -894,8 +899,8 @@ class Library(object): self.check_library_for_openmc_mgxs() cv.check_value('xs_type', xs_type, ['macro', 'micro']) - if domain_names is not None: - cv.check_iterable_type('domain_names', domain_names, basestring) + if xsdata_names is not None: + cv.check_iterable_type('xsdata_names', xsdata_names, basestring) if xs_ids is not None: if isinstance(xs_ids, basestring): # If we only have a string lets convert it now to a list @@ -927,14 +932,14 @@ class Library(object): nuclides = ['total'] for nuclide in nuclides: # Build & add metadata to XSdata object - if domain_names is None: - name = 'set' + str(i + 1) + if xsdata_names is None: + xsdata_name = 'set' + str(i + 1) else: - name = domain_names[i] + xsdata_name = xsdata_names[i] if nuclide is not 'total': - name += '_' + nuclide + xsdata_name += '_' + nuclide - xsdata = self.get_xsdata(domain, name, nuclide=nuclide, + xsdata = self.get_xsdata(domain, xsdata_name, nuclide=nuclide, xs_type=xs_type, xs_id=xs_ids[i], order=order) @@ -952,14 +957,17 @@ class Library(object): The rules to check include: - Either total or transport should be present. + - Both can be available if one wants, but we should use whatever corresponds to Library.correction (if P0: transport) + - Absorption and total (or transport) are required. - A nu-fission cross section and chi values are not required as a fixed source problem could be the target. - Fission and kappa-fission are not required as they are only needed to support tallies the user may wish to request. - A nu-scatter matrix is required. + - Having both nu-scatter (of any order) and scatter (at least isotropic) matrices is preferred - If only nu-scatter, need total (not transport), to diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index f8a712f68..7cfec2f54 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -283,7 +283,7 @@ class MGXS(object): @domain_type.setter def domain_type(self, domain_type): - cv.check_value('domain type', domain_type, tuple(DOMAIN_TYPES)) + cv.check_value('domain type', domain_type, DOMAIN_TYPES) self._domain_type = domain_type @energy_groups.setter diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index e59ef2d61..b7c61595f 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -346,6 +346,16 @@ class XSdata(object): self.energy_groups.num_groups, self.energy_groups.num_groups) + @property + def pn_matrix_shape(self): + if self.representation is 'isotropic': + return (self.num_orders, self.energy_groups.num_groups, + self.energy_groups.num_groups) + elif self.representation is 'angle': + return (self.num_polar, self.num_azimuthal, self.num_orders, + self.energy_groups.num_groups, + self.energy_groups.num_groups) + @name.setter def name(self, name): check_type('name for XSdata', name, basestring) @@ -449,38 +459,49 @@ class XSdata(object): @total.setter def total(self, total): - check_type('total', total, np.ndarray, expected_iter_type=Real) - check_value('total shape', total.shape, self.vector_shape) + check_type('total', total, Iterable, expected_iter_type=Real) + # Convert to a numpy array so we can easily get the shape for + # checking + nptotal = np.array(total) + check_value('total shape', nptotal.shape, [self.vector_shape]) - self._total = total + self._total = nptotal @absorption.setter def absorption(self, absorption): - check_type('absorption', absorption, np.ndarray, - expected_iter_type=Real) - check_value('absorption shape', absorption.shape, self.vector_shape) + check_type('absorption', absorption, Iterable, expected_iter_type=Real) + # Convert to a numpy array so we can easily get the shape for + # checking + npabsorption = np.array(absorption) + check_value('absorption shape', npabsorption.shape, + [self.vector_shape]) - self._absorption = absorption + self._absorption = npabsorption @fission.setter def fission(self, fission): - check_type('fission', fission, np.ndarray, - expected_iter_type=Real) - check_value('fission shape', fission.shape, self.vector_shape) + check_type('fission', fission, Iterable, expected_iter_type=Real) + # Convert to a numpy array so we can easily get the shape for + # checking + npfission = np.array(fission) + check_value('fission shape', npfission.shape, [self.vector_shape]) - self._fission = fission + self._fission = npfission if np.sum(self._fission) > 0.0: self._fissionable = True @kappa_fission.setter def kappa_fission(self, kappa_fission): - check_type('kappa_fission', kappa_fission, np.ndarray, + check_type('kappa_fission', kappa_fission, Iterable, expected_iter_type=Real) - check_value('kappa fission shape', kappa_fission.shape, - self.vector_shape) + # Convert to a numpy array so we can easily get the shape for + # checking + npkappa_fission = np.array(kappa_fission) + check_value('kappa fission shape', npkappa_fission.shape, + [self.vector_shape]) - self._kappa_fission = kappa_fission + self._kappa_fission = npkappa_fission if np.sum(self._kappa_fission) > 0.0: self._fissionable = True @@ -493,30 +514,39 @@ class XSdata(object): 'matrix' raise ValueError(msg) - check_type('chi', chi, np.ndarray, expected_iter_type=Real) - check_value('chi shape', chi.shape, self.vector_shape) + check_type('chi', chi, Iterable, expected_iter_type=Real) + # Convert to a numpy array so we can easily get the shape for + # checking + npchi = np.array(chi) + check_value('chi shape', npchi.shape, [self.vector_shape]) - self._chi = chi + self._chi = npchi if self._use_chi is not None: self._use_chi = True @scatter.setter def scatter(self, scatter): - check_type('scatter', scatter, np.ndarray, expected_iter_type=Real, - max_depth=len(scatter.shape)) - check_value('scatter shape', scatter.shape, self.pn_matrix_shape) + # Convert to a numpy array so we can easily get the shape for + # checking + npscatter = np.array(scatter) + check_iterable_type('scatter', npscatter, Real, + max_depth=len(npscatter.shape)) + check_value('scatter shape', npscatter.shape, [self.pn_matrix_shape]) - self._scatter = scatter + self._scatter = npscatter @multiplicity.setter def multiplicity(self, multiplicity): - check_type('multiplicity', multiplicity, np.ndarray, - expected_iter_type=Real, max_depth=len(multiplicity.shape)) - check_value('multiplicity shape', multiplicity.shape, - self.matrix_shape) + # Convert to a numpy array so we can easily get the shape for + # checking + npmultiplicity = np.array(multiplicity) + check_iterable_type('multiplicity', npmultiplicity, Real, + max_depth=len(npmultiplicity.shape)) + check_value('multiplicity shape', npmultiplicity.shape, + [self.matrix_shape]) - self._multiplicity = multiplicity + self._multiplicity = npmultiplicity @nu_fission.setter def nu_fission(self, nu_fission): @@ -530,27 +560,31 @@ class XSdata(object): # chi already has been set. If not, we just check that this is OK # and set the use_chi flag accordingly - check_type('nu_fission', nu_fission, np.ndarray, - expected_iter_type=Real, max_depth=len(nu_fission.shape)) + # Convert to a numpy array so we can easily get the shape for + # checking + npnu_fission = np.array(nu_fission) + + check_iterable_type('nu_fission', npnu_fission, Real, + max_depth=len(npnu_fission.shape)) if self._use_chi is not None: if self._use_chi: - check_value('nu_fission shape', nu_fission.shape, - self.vector_shape) + check_value('nu_fission shape', npnu_fission.shape, + [self.vector_shape]) else: - check_value('nu_fission shape', nu_fission.shape, - self.matrix_shape) + check_value('nu_fission shape', npnu_fission.shape, + [self.matrix_shape]) else: - check_value('nu_fission shape', nu_fission.shape, - (self.vector_shape, self.matrix_shape)) + check_value('nu_fission shape', npnu_fission.shape, + [self.vector_shape, self.matrix_shape]) # Find out if we have a nu-fission matrix or vector # and set a flag to allow other methods to check this later. - if nu_fission.shape == self.vector_shape: + if npnu_fission.shape == self.vector_shape: self._use_chi = True else: self._use_chi = False - self._nu_fission = nu_fission + self._nu_fission = npnu_fission if np.sum(self._nu_fission) > 0.0: self._fissionable = True From 142033c2607f400fbd365bd79a8b2f1a07177b22 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 15 May 2016 14:56:00 -0400 Subject: [PATCH 140/147] minor edits per @paulromano comments --- openmc/mgxs/library.py | 1 + openmc/mgxs_library.py | 24 ++++++++++++------------ 2 files changed, 13 insertions(+), 12 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 586302a4b..45b502be4 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -956,6 +956,7 @@ class Library(object): a MGXS Library for OpenMC's Multi-Group mode. The rules to check include: + - Either total or transport should be present. - Both can be available if one wants, but we should diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index b7c61595f..7a2c0e7b7 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -103,7 +103,7 @@ class XSdata(object): 1000*(atomic number) + mass number. As an example, the zaid of U-235 would be 92235. awr : float - Atomic-weight-ratio of an isotope. That is, the ratio of the mass + Atomic weight ratio of an isotope. That is, the ratio of the mass of the isotope to the mass of a single neutron. kT : float Temperature (in units of MeV). @@ -390,14 +390,14 @@ class XSdata(object): def zaid(self, zaid): # Check type and value check_type('zaid', zaid, Integral) - check_greater_than('zaid', zaid, 0, equality=False) + check_greater_than('zaid', zaid, 0) self._zaid = zaid @awr.setter def awr(self, awr): # Check validity of type and that the awr value is > 0 check_type('awr', awr, Real) - check_greater_than('awr', awr, 0.0, equality=False) + check_greater_than('awr', awr, 0.0) self._awr = awr @kT.setter @@ -462,7 +462,7 @@ class XSdata(object): check_type('total', total, Iterable, expected_iter_type=Real) # Convert to a numpy array so we can easily get the shape for # checking - nptotal = np.array(total) + nptotal = np.asarray(total) check_value('total shape', nptotal.shape, [self.vector_shape]) self._total = nptotal @@ -472,7 +472,7 @@ class XSdata(object): check_type('absorption', absorption, Iterable, expected_iter_type=Real) # Convert to a numpy array so we can easily get the shape for # checking - npabsorption = np.array(absorption) + npabsorption = np.asarray(absorption) check_value('absorption shape', npabsorption.shape, [self.vector_shape]) @@ -483,7 +483,7 @@ class XSdata(object): check_type('fission', fission, Iterable, expected_iter_type=Real) # Convert to a numpy array so we can easily get the shape for # checking - npfission = np.array(fission) + npfission = np.asarray(fission) check_value('fission shape', npfission.shape, [self.vector_shape]) self._fission = npfission @@ -497,7 +497,7 @@ class XSdata(object): expected_iter_type=Real) # Convert to a numpy array so we can easily get the shape for # checking - npkappa_fission = np.array(kappa_fission) + npkappa_fission = np.asarray(kappa_fission) check_value('kappa fission shape', npkappa_fission.shape, [self.vector_shape]) @@ -517,7 +517,7 @@ class XSdata(object): check_type('chi', chi, Iterable, expected_iter_type=Real) # Convert to a numpy array so we can easily get the shape for # checking - npchi = np.array(chi) + npchi = np.asarray(chi) check_value('chi shape', npchi.shape, [self.vector_shape]) self._chi = npchi @@ -529,7 +529,7 @@ class XSdata(object): def scatter(self, scatter): # Convert to a numpy array so we can easily get the shape for # checking - npscatter = np.array(scatter) + npscatter = np.asarray(scatter) check_iterable_type('scatter', npscatter, Real, max_depth=len(npscatter.shape)) check_value('scatter shape', npscatter.shape, [self.pn_matrix_shape]) @@ -540,7 +540,7 @@ class XSdata(object): def multiplicity(self, multiplicity): # Convert to a numpy array so we can easily get the shape for # checking - npmultiplicity = np.array(multiplicity) + npmultiplicity = np.asarray(multiplicity) check_iterable_type('multiplicity', npmultiplicity, Real, max_depth=len(npmultiplicity.shape)) check_value('multiplicity shape', npmultiplicity.shape, @@ -562,7 +562,7 @@ class XSdata(object): # Convert to a numpy array so we can easily get the shape for # checking - npnu_fission = np.array(nu_fission) + npnu_fission = np.asarray(nu_fission) check_iterable_type('nu_fission', npnu_fission, Real, max_depth=len(npnu_fission.shape)) @@ -595,7 +595,7 @@ class XSdata(object): Parameters ---------- - total: {openmc.mgxs.TotalXS, openmc.mgxs.TransportXS} + total: openmc.mgxs.TotalXS or openmc.mgxs.TransportXS MGXS Object containing the total or transport cross section for the domain of interest. nuclide : str From e13bd5c853b4251ef5ef8f46f0c1221fdde0442f Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sun, 15 May 2016 19:13:22 -0400 Subject: [PATCH 141/147] Fixed per @paulromano comments --- openmc/mgxs/library.py | 18 +++++++--------- openmc/mgxs_library.py | 47 ++++++++++++++++++++++++++++++++++++++++-- src/summary.F90 | 2 +- 3 files changed, 53 insertions(+), 14 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 45b502be4..baa4d6304 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -4,9 +4,10 @@ import copy import pickle from numbers import Integral from collections import OrderedDict -import numpy as np from warnings import warn +import numpy as np + import openmc import openmc.mgxs import openmc.checkvalue as cv @@ -759,7 +760,7 @@ class Library(object): See also -------- - Library.create_mg_library(...) + Library.create_mg_library() """ @@ -890,7 +891,7 @@ class Library(object): See also -------- - Library.dump_to_file(mgxs_lib, filename, directory) + Library.dump_to_file() """ @@ -922,9 +923,7 @@ class Library(object): # support for higher orders are included in openmc.mgxs order = 0 - # Build storage for our XSdata objects - xsdatas = [] - + # Create the xsdata object and add it to the mgxs_file for i, domain in enumerate(self.domains): if self.by_nuclide: nuclides = list(domain.get_all_nuclides().keys()) @@ -943,10 +942,7 @@ class Library(object): xs_type=xs_type, xs_id=xs_ids[i], order=order) - xsdatas.append(xsdata) - - # Add XSdatas to file - mgxs_file.add_xsdatas(xsdatas) + mgxs_file.add_xsdata(xsdata) return mgxs_file @@ -977,7 +973,7 @@ class Library(object): See also -------- - Library.create_mg_library(...) + Library.create_mg_library() """ diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 7a2c0e7b7..408175f43 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -367,7 +367,7 @@ class XSdata(object): check_type('energy_groups', energy_groups, openmc.mgxs.EnergyGroups) if energy_group.group_edges is None: - msg = 'Unable to assign an EnergyGroups object ' + \ + msg = 'Unable to assign an EnergyGroups object ' \ 'with uninitialized group edges' raise ValueError(msg) self._energy_groups = energy_groups @@ -518,7 +518,10 @@ class XSdata(object): # Convert to a numpy array so we can easily get the shape for # checking npchi = np.asarray(chi) - check_value('chi shape', npchi.shape, [self.vector_shape]) + # Check the shape + if npchi.shape != self.vector_shape: + msg = 'Provided chi iterable does not have the expected shape.' + raise ValueError(msg) self._chi = npchi @@ -605,6 +608,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('total', total, (openmc.mgxs.TotalXS, @@ -636,6 +644,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('absorption', absorption, openmc.mgxs.AbsorptionXS) @@ -667,6 +680,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('fission', fission, openmc.mgxs.FissionXS) @@ -699,6 +717,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ # The NuFissionXS class does not have the capability to produce @@ -740,6 +763,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('k_fission', k_fission, openmc.mgxs.KappaFissionXS) @@ -770,6 +798,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ if self._use_chi is not None: @@ -810,6 +843,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('scatter', scatter, openmc.mgxs.ScatterMatrixXS) @@ -851,6 +889,11 @@ class XSdata(object): Provide the macro or micro cross section in units of cm^-1 or barns. Defaults to 'macro'. + See also + -------- + openmc.mgxs.Library.create_mg_library() + openmc.mgxs.Library.get_xsdata + """ check_type('nuscatter', nuscatter, openmc.mgxs.NuScatterMatrixXS) diff --git a/src/summary.F90 b/src/summary.F90 index 9defcc92f..aabf6c22b 100644 --- a/src/summary.F90 +++ b/src/summary.F90 @@ -118,7 +118,7 @@ contains real(8), allocatable :: awrs(:) integer, allocatable :: zaids(:) - ! Use H5LT interface to write useful data from nuclide objects + ! Write useful data from nuclide objects nuclide_group = create_group(file_id, "nuclides") call write_dataset(nuclide_group, "n_nuclides_total", n_nuclides_total) From 704022dccc43f19744db123c5d4e0fdb7cea7ff9 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 16 May 2016 11:32:55 -0400 Subject: [PATCH 142/147] Removed docstring on MGXS.xs_tally to eliminate sphinx cross-reference issues --- openmc/mgxs/mgxs.py | 2 -- 1 file changed, 2 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 3e24f16bc..09f1de3aa 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -297,8 +297,6 @@ class MGXS(object): @property def xs_tally(self): - """Computes multi-group cross section using OpenMC tally arithmetic.""" - if self._xs_tally is None: if self.tallies is None: msg = 'Unable to get xs_tally since tallies have ' \ From 1e86848ac62a7aa44fdccecbba9d4a12269fa81b Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 16 May 2016 11:59:12 -0400 Subject: [PATCH 143/147] Removed docstrings on MGXS.tallies and Chi.xs_tally to eliminate sphinx issues --- openmc/mgxs/mgxs.py | 2 -- 1 file changed, 2 deletions(-) diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 09f1de3aa..56bb9ea89 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -248,7 +248,6 @@ class MGXS(object): @property def tallies(self): - """Construct the OpenMC tallies needed to compute the cross section.""" # Instantiate tallies if they do not exist if self._tallies is None: @@ -3298,7 +3297,6 @@ class Chi(MGXS): @property def xs_tally(self): - """Computes chi fission spectrum using OpenMC tally arithmetic.""" if self._xs_tally is None: nu_fission_in = self.tallies['nu-fission-in'] From 970cc4130a6ff85ecfd3757b2d0e818144bdd39e Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Mon, 16 May 2016 16:28:57 -0500 Subject: [PATCH 144/147] Fix hexagon region orientation --- openmc/surface.py | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/openmc/surface.py b/openmc/surface.py index 84028c1af..52f0955f0 100644 --- a/openmc/surface.py +++ b/openmc/surface.py @@ -1527,7 +1527,7 @@ def make_hexagon_region(edge_length=1., orientation='y'): l = edge_length - if orientation == 'x': + if orientation == 'y': right = XPlane(x0=sqrt(3.)/2.*l) left = XPlane(x0=-sqrt(3.)/2.*l) c = sqrt(3.)/3. @@ -1537,7 +1537,7 @@ def make_hexagon_region(edge_length=1., orientation='y'): ll = Plane(A=c, B=1., D=-l) # y = -x/sqrt(3) - a return Intersection(-right, +left, -ur, -ul, +lr, +ll) - elif orientation == 'y': + elif orientation == 'x': top = YPlane(y0=sqrt(3.)/2.*l) bottom = YPlane(y0=-sqrt(3.)/2.*l) c = sqrt(3.) From 16886a41d95de450cbc0474833058601f17abc61 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 17 May 2016 05:35:55 -0400 Subject: [PATCH 145/147] Incorporating Legendre scattering to Library and Mgxs_library modules (and example nbook). --- .../pythonapi/examples/mgxs-part-iv.ipynb | 258 ++++++++++-------- openmc/mgxs/library.py | 40 ++- openmc/mgxs_library.py | 42 ++- 3 files changed, 198 insertions(+), 142 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index 4509f0fc8..e1d61cedc 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -433,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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"text/plain": [ "" ] @@ -512,7 +512,7 @@ "outputs": [], "source": [ "# Specify multi-group cross section types to compute\n", - "mgxs_lib.mgxs_types = ['transport', 'absorption', 'nu-fission', 'fission',\n", + "mgxs_lib.mgxs_types = ['total', 'absorption', 'nu-fission', 'fission',\n", " 'nu-scatter matrix', 'scatter matrix', 'chi']" ] }, @@ -565,7 +565,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "Now that the `Library` has been setup, lets make sure it contains the types of cross sections which meet the needs of OpenMC's multi-group solver. Note that this step is done automatically when writing the Multi-Group Library file later in the process (as part of the `mgxs_lib.write_mg_library()`), but it is a good practice to also run this before spending all the time running OpenMC to generate the cross sections." + "Now we will set the scattering order that we wish to use. For this problem we will use P3 scattering." ] }, { @@ -574,6 +574,34 @@ "metadata": { "collapsed": false }, + "outputs": [ + { + "name": "stderr", + "output_type": "stream", + "text": [ + "/home/nelsonag/git/openmc/openmc/mgxs/library.py:320: RuntimeWarning: The P0 correction will be ignored since the scattering order 0 is greater than zero\n", + " warnings.warn(msg, RuntimeWarning)\n" + ] + } + ], + "source": [ + "# Set the Legendre order to 3 for P3 scattering\n", + "mgxs_lib.legendre_order = 3" + ] + }, + { + "cell_type": "markdown", + "metadata": {}, + "source": [ + "Now that the `Library` has been setup, lets make sure it contains the types of cross sections which meet the needs of OpenMC's multi-group solver. Note that this step is done automatically when writing the Multi-Group Library file later in the process (as part of the `mgxs_lib.write_mg_library()`), but it is a good practice to also run this before spending all the time running OpenMC to generate the cross sections." + ] + }, + { + "cell_type": "code", + "execution_count": 22, + "metadata": { + "collapsed": false + }, "outputs": [], "source": [ "# Check the library - if no errors are raised, then the library is satisfactory.\n", @@ -589,9 +617,9 @@ }, { "cell_type": "code", - "execution_count": 22, + "execution_count": 23, "metadata": { - "collapsed": true + "collapsed": false }, "outputs": [], "source": [ @@ -610,7 +638,7 @@ }, { "cell_type": "code", - "execution_count": 23, + "execution_count": 24, "metadata": { "collapsed": true }, @@ -630,7 +658,7 @@ }, { "cell_type": "code", - "execution_count": 24, + "execution_count": 25, "metadata": { "collapsed": true }, @@ -658,7 +686,7 @@ }, { "cell_type": "code", - "execution_count": 25, + "execution_count": 26, "metadata": { "collapsed": true }, @@ -670,7 +698,7 @@ }, { "cell_type": "code", - "execution_count": 26, + "execution_count": 27, "metadata": { "collapsed": false }, @@ -695,8 +723,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 4bec584ddb7d07be7d92ad9d037e8363b2f25614\n", - " Date/Time: 2016-05-15 14:22:34\n", + " Git SHA1: 058ba68895a2f880402fda3d58cfb14b162931d9\n", + " Date/Time: 2016-05-17 05:32:34\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -783,20 +811,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4620E+00 seconds\n", - " Reading cross sections = 1.1520E+00 seconds\n", - " Total time in simulation = 2.1015E+01 seconds\n", - " Time in transport only = 2.0844E+01 seconds\n", - " Time in inactive batches = 2.2260E+00 seconds\n", - " Time in active batches = 1.8789E+01 seconds\n", - " Time synchronizing fission bank = 9.0000E-03 seconds\n", - " Sampling source sites = 5.0000E-03 seconds\n", - " SEND/RECV source sites = 4.0000E-03 seconds\n", - " Time accumulating tallies = 0.0000E+00 seconds\n", + " Total time for initialization = 1.4400E+00 seconds\n", + " Reading cross sections = 1.1340E+00 seconds\n", + " Total time in simulation = 1.8207E+01 seconds\n", + " Time in transport only = 1.8125E+01 seconds\n", + " Time in inactive batches = 2.1170E+00 seconds\n", + " Time in active batches = 1.6090E+01 seconds\n", + " Time synchronizing fission bank = 3.0000E-03 seconds\n", + " Sampling source sites = 2.0000E-03 seconds\n", + " SEND/RECV source sites = 1.0000E-03 seconds\n", + " Time accumulating tallies = 1.0000E-03 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.2491E+01 seconds\n", - " Calculation Rate (inactive) = 22461.8 neutrons/second\n", - " Calculation Rate (active) = 10644.5 neutrons/second\n", + " Total time elapsed = 1.9657E+01 seconds\n", + " Calculation Rate (inactive) = 23618.3 neutrons/second\n", + " Calculation Rate (active) = 12430.1 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -814,7 +842,7 @@ "0" ] }, - "execution_count": 26, + "execution_count": 27, "metadata": {}, "output_type": "execute_result" } @@ -833,7 +861,7 @@ }, { "cell_type": "code", - "execution_count": 27, + "execution_count": 28, "metadata": { "collapsed": false }, @@ -858,7 +886,7 @@ }, { "cell_type": "code", - "execution_count": 28, + "execution_count": 29, "metadata": { "collapsed": false }, @@ -877,7 +905,7 @@ }, { "cell_type": "code", - "execution_count": 29, + "execution_count": 30, "metadata": { "collapsed": false }, @@ -896,7 +924,7 @@ }, { "cell_type": "code", - "execution_count": 30, + "execution_count": 31, "metadata": { "collapsed": false }, @@ -929,7 +957,7 @@ }, { "cell_type": "code", - "execution_count": 31, + "execution_count": 32, "metadata": { "collapsed": false }, @@ -969,7 +997,7 @@ }, { "cell_type": "code", - "execution_count": 32, + "execution_count": 33, "metadata": { "collapsed": false }, @@ -1019,7 +1047,7 @@ }, { "cell_type": "code", - "execution_count": 33, + "execution_count": 34, "metadata": { "collapsed": true }, @@ -1044,7 +1072,7 @@ }, { "cell_type": "code", - "execution_count": 34, + "execution_count": 35, "metadata": { "collapsed": false, "scrolled": true @@ -1070,8 +1098,8 @@ " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", - " Git SHA1: 4bec584ddb7d07be7d92ad9d037e8363b2f25614\n", - " Date/Time: 2016-05-15 14:22:57\n", + " Git SHA1: 058ba68895a2f880402fda3d58cfb14b162931d9\n", + " Date/Time: 2016-05-17 05:32:54\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1096,56 +1124,56 @@ "\n", " Bat./Gen. k Average k \n", " ========= ======== ==================== \n", - " 1/1 1.02073 \n", - " 2/1 1.04004 \n", - " 3/1 1.02324 \n", - " 4/1 1.01690 \n", - " 5/1 1.03702 \n", - " 6/1 1.01796 \n", - " 7/1 1.01779 \n", - " 8/1 1.02764 \n", - " 9/1 1.03324 \n", - " 10/1 1.01465 \n", - " 11/1 1.02268 \n", - " 12/1 1.01598 1.01933 +/- 0.00335\n", - " 13/1 1.01993 1.01953 +/- 0.00194\n", - " 14/1 1.01779 1.01910 +/- 0.00144\n", - " 15/1 1.01014 1.01731 +/- 0.00211\n", - " 16/1 1.04059 1.02119 +/- 0.00425\n", - " 17/1 1.04877 1.02513 +/- 0.00533\n", - " 18/1 1.05504 1.02887 +/- 0.00594\n", - " 19/1 1.02601 1.02855 +/- 0.00525\n", - " 20/1 1.04347 1.03004 +/- 0.00493\n", - " 21/1 1.01703 1.02886 +/- 0.00461\n", - " 22/1 1.02628 1.02864 +/- 0.00421\n", - " 23/1 1.02598 1.02844 +/- 0.00388\n", - " 24/1 1.05341 1.03022 +/- 0.00401\n", - " 25/1 1.02201 1.02967 +/- 0.00377\n", - " 26/1 1.00758 1.02829 +/- 0.00379\n", - " 27/1 1.00720 1.02705 +/- 0.00377\n", - " 28/1 1.03098 1.02727 +/- 0.00356\n", - " 29/1 1.03022 1.02743 +/- 0.00337\n", - " 30/1 1.01694 1.02690 +/- 0.00324\n", - " 31/1 0.99064 1.02518 +/- 0.00353\n", - " 32/1 0.99495 1.02380 +/- 0.00364\n", - " 33/1 1.03220 1.02417 +/- 0.00350\n", - " 34/1 1.02399 1.02416 +/- 0.00335\n", - " 35/1 1.03048 1.02441 +/- 0.00322\n", - " 36/1 1.05360 1.02553 +/- 0.00329\n", - " 37/1 1.05030 1.02645 +/- 0.00330\n", - " 38/1 1.04167 1.02699 +/- 0.00322\n", - " 39/1 1.04406 1.02758 +/- 0.00317\n", - " 40/1 1.01169 1.02705 +/- 0.00310\n", - " 41/1 1.00191 1.02624 +/- 0.00311\n", - " 42/1 1.02729 1.02628 +/- 0.00301\n", - " 43/1 1.02263 1.02616 +/- 0.00292\n", - " 44/1 1.05344 1.02697 +/- 0.00295\n", - " 45/1 1.03607 1.02723 +/- 0.00287\n", - " 46/1 1.00357 1.02657 +/- 0.00287\n", - " 47/1 1.03353 1.02676 +/- 0.00279\n", - " 48/1 1.03817 1.02706 +/- 0.00274\n", - " 49/1 1.01454 1.02674 +/- 0.00269\n", - " 50/1 0.99860 1.02603 +/- 0.00271\n", + " 1/1 1.02235 \n", + " 2/1 1.01108 \n", + " 3/1 1.02801 \n", + " 4/1 1.01404 \n", + " 5/1 1.03423 \n", + " 6/1 1.03282 \n", + " 7/1 1.04060 \n", + " 8/1 1.01152 \n", + " 9/1 1.02063 \n", + " 10/1 1.02604 \n", + " 11/1 1.02137 \n", + " 12/1 1.01416 1.01776 +/- 0.00360\n", + " 13/1 1.00239 1.01264 +/- 0.00553\n", + " 14/1 1.04293 1.02021 +/- 0.00852\n", + " 15/1 1.02029 1.02023 +/- 0.00660\n", + " 16/1 1.01512 1.01938 +/- 0.00546\n", + " 17/1 1.02098 1.01960 +/- 0.00462\n", + " 18/1 1.05954 1.02460 +/- 0.00640\n", + " 19/1 1.02347 1.02447 +/- 0.00564\n", + " 20/1 1.03063 1.02509 +/- 0.00508\n", + " 21/1 1.04679 1.02706 +/- 0.00500\n", + " 22/1 1.01301 1.02589 +/- 0.00472\n", + " 23/1 1.00936 1.02462 +/- 0.00452\n", + " 24/1 1.01030 1.02360 +/- 0.00431\n", + " 25/1 1.03799 1.02456 +/- 0.00412\n", + " 26/1 1.00404 1.02327 +/- 0.00406\n", + " 27/1 1.02987 1.02366 +/- 0.00384\n", + " 28/1 1.00107 1.02241 +/- 0.00383\n", + " 29/1 1.01460 1.02200 +/- 0.00365\n", + " 30/1 1.01433 1.02161 +/- 0.00348\n", + " 31/1 1.01566 1.02133 +/- 0.00332\n", + " 32/1 1.03339 1.02188 +/- 0.00321\n", + " 33/1 1.03974 1.02265 +/- 0.00317\n", + " 34/1 1.03136 1.02302 +/- 0.00306\n", + " 35/1 1.05175 1.02417 +/- 0.00315\n", + " 36/1 1.05444 1.02533 +/- 0.00324\n", + " 37/1 1.02432 1.02529 +/- 0.00312\n", + " 38/1 1.01464 1.02491 +/- 0.00303\n", + " 39/1 1.01086 1.02443 +/- 0.00296\n", + " 40/1 1.02492 1.02444 +/- 0.00286\n", + " 41/1 1.02882 1.02459 +/- 0.00277\n", + " 42/1 1.00377 1.02394 +/- 0.00276\n", + " 43/1 0.97480 1.02245 +/- 0.00306\n", + " 44/1 1.03623 1.02285 +/- 0.00300\n", + " 45/1 1.02606 1.02294 +/- 0.00291\n", + " 46/1 1.01771 1.02280 +/- 0.00284\n", + " 47/1 1.05400 1.02364 +/- 0.00288\n", + " 48/1 1.01844 1.02350 +/- 0.00281\n", + " 49/1 1.00754 1.02309 +/- 0.00277\n", + " 50/1 1.02902 1.02324 +/- 0.00270\n", " Creating state point statepoint.50.h5...\n", "\n", " ===========================================================================\n", @@ -1155,27 +1183,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.5000E-02 seconds\n", - " Reading cross sections = 3.0000E-03 seconds\n", - " Total time in simulation = 1.2599E+01 seconds\n", - " Time in transport only = 1.2565E+01 seconds\n", - " Time in inactive batches = 1.1220E+00 seconds\n", - " Time in active batches = 1.1477E+01 seconds\n", - " Time synchronizing fission bank = 6.0000E-03 seconds\n", - " Sampling source sites = 5.0000E-03 seconds\n", + " Total time for initialization = 4.7000E-02 seconds\n", + " Reading cross sections = 6.0000E-03 seconds\n", + " Total time in simulation = 1.4145E+01 seconds\n", + " Time in transport only = 1.4098E+01 seconds\n", + " Time in inactive batches = 1.2400E+00 seconds\n", + " Time in active batches = 1.2905E+01 seconds\n", + " Time synchronizing fission bank = 4.0000E-03 seconds\n", + " Sampling source sites = 3.0000E-03 seconds\n", " SEND/RECV source sites = 1.0000E-03 seconds\n", " Time accumulating tallies = 1.0000E-03 seconds\n", - " Total time for finalization = 1.0000E-03 seconds\n", - " Total time elapsed = 1.2644E+01 seconds\n", - " Calculation Rate (inactive) = 44563.3 neutrons/second\n", - " Calculation Rate (active) = 17426.2 neutrons/second\n", + " Total time for finalization = 0.0000E+00 seconds\n", + " Total time elapsed = 1.4201E+01 seconds\n", + " Calculation Rate (inactive) = 40322.6 neutrons/second\n", + " Calculation Rate (active) = 15497.9 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02471 +/- 0.00243\n", - " k-effective (Track-length) = 1.02603 +/- 0.00271\n", - " k-effective (Absorption) = 1.02312 +/- 0.00182\n", - " Combined k-effective = 1.02387 +/- 0.00172\n", + " k-effective (Collision) = 1.02379 +/- 0.00230\n", + " k-effective (Track-length) = 1.02324 +/- 0.00270\n", + " k-effective (Absorption) = 1.02813 +/- 0.00172\n", + " Combined k-effective = 1.02680 +/- 0.00165\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -1186,7 +1214,7 @@ "0" ] }, - "execution_count": 34, + "execution_count": 35, "metadata": {}, "output_type": "execute_result" } @@ -1209,7 +1237,7 @@ }, { "cell_type": "code", - "execution_count": 35, + "execution_count": 36, "metadata": { "collapsed": false }, @@ -1229,7 +1257,7 @@ }, { "cell_type": "code", - "execution_count": 36, + "execution_count": 37, "metadata": { "collapsed": true }, @@ -1247,7 +1275,7 @@ }, { "cell_type": "code", - "execution_count": 37, + "execution_count": 38, "metadata": { "collapsed": false }, @@ -1257,8 +1285,8 @@ "output_type": "stream", "text": [ "Continuous-Energy keff = 1.024295\n", - "Multi-Group keff = 1.023875\n", - "bias [pcm]: 42.0\n" + "Multi-Group keff = 1.026805\n", + "bias [pcm]: -251.0\n" ] } ], @@ -1274,7 +1302,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "We see quite good agreement with only a 42 pcm difference between the two methods. Due to the high degree of approximations inherent in practical application of multi-group theory, one should not expect results of such high fidelity always for multi-group Monte Carlo calculations." + "This shows a 251 pcm bias between the two methods. Some degree of mismatch is expected simply to the very few histories being used in these example problems. An additional mismatch is always inherent in the practical application of multi-group theory due to the high degree of approximations inherent in that method." ] }, { @@ -1295,7 +1323,7 @@ }, { "cell_type": "code", - "execution_count": 38, + "execution_count": 39, "metadata": { "collapsed": false }, @@ -1321,7 +1349,7 @@ }, { "cell_type": "code", - "execution_count": 39, + "execution_count": 40, "metadata": { "collapsed": false }, @@ -1347,7 +1375,7 @@ }, { "cell_type": "code", - "execution_count": 40, + "execution_count": 41, "metadata": { "collapsed": false }, @@ -1355,18 +1383,18 @@ { "data": { "text/plain": [ - "" + "" ] }, - "execution_count": 40, + "execution_count": 41, "metadata": {}, "output_type": "execute_result" }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index bc643ed3e..e5728a812 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -460,7 +460,7 @@ class Library(object): ---------- domain : Material or Cell or Universe or Integral The material, cell, or universe object of interest (or its ID) - mgxs_type : {'total', 'transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'} + mgxs_type : {'total', 'transport', 'nu-transport', 'absorption', 'capture', 'fission', 'nu-fission', 'kappa-fission', 'scatter', 'nu-scatter', 'scatter matrix', 'nu-scatter matrix', 'chi'} The type of multi-group cross section object to return Returns @@ -773,9 +773,9 @@ class Library(object): nuclide this will be set to 'macro' regardless. xs_ids : str Cross section set identifier. Defaults to '1m'. - order : Scattering order for this dataset entry. Default is None, - which will force the XSdata object to use whatever the maximum - order available. + order : Scattering order for this data entry. Default is None, + which will force the XSdata object to use whatever the order of the + Library object is. Returns ------- @@ -801,7 +801,8 @@ class Library(object): cv.check_value('xs_type', xs_type, ['macro', 'micro']) cv.check_type('xs_id', xs_id, basestring) cv.check_type('order', order, (type(None), Integral)) - cv.check_greater_than('order', order, -1, equality=True) + if order is not None: + cv.check_greater_than('order', order, 0, equality=True) # Make sure statepoint has been loaded if self._sp_filename is None: @@ -819,20 +820,22 @@ class Library(object): name += '_' + nuclide name += '.' + xs_id xsdata = openmc.XSdata(name, self.energy_groups) - if order is 0: - xsdata.order = order + + if order is None: + # Set the order to the Library's order (the defualt behavior) + xsdata.order = self.legendre_order else: - msg = 'Generating anisotropic scattering from openmc.Library' \ - 'objects has not yet been implemented.' - raise NotImplementedError(msg) + # Set the order of the xsdata object to the minimum of + # the provided order or the Library's order. + xsdata.order = min(order, self.legendre_order) if nuclide is not 'total': xsdata.zaid = self._nuclides[nuclide][0] xsdata.awr = self._nuclides[nuclide][1] # Now get xs data itself - if 'transport' in self.mgxs_types: - mymgxs = self.get_mgxs(domain, 'transport') + if ('nu-transport' in self.mgxs_types) and (self.correction == 'P0'): + mymgxs = self.get_mgxs(domain, 'nu-transport') xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide]) elif 'total' in self.mgxs_types: mymgxs = self.get_mgxs(domain, 'total') @@ -949,10 +952,6 @@ class Library(object): # Initialize file mgxs_file = openmc.MGXSLibrary(self.energy_groups) - # Set the scattering order as isotropic until - # support for higher orders are included in openmc.mgxs - order = 0 - # Create the xsdata object and add it to the mgxs_file for i, domain in enumerate(self.domains): if self.by_nuclide: @@ -969,8 +968,7 @@ class Library(object): xsdata_name += '_' + nuclide xsdata = self.get_xsdata(domain, xsdata_name, nuclide=nuclide, - xs_type=xs_type, xs_id=xs_ids[i], - order=order) + xs_type=xs_type, xs_id=xs_ids[i]) mgxs_file.add_xsdata(xsdata) @@ -1031,10 +1029,10 @@ class Library(object): # Total or transport can be present, but if using # self.correction=="P0", then we should use transport. if (((self.correction is "P0") and - ('transport' not in self.mgxs_types))): + ('nu-transport' not in self.mgxs_types))): error_flag = True - msg = 'Transport MGXS type is required since a "P0" correction ' \ - 'is applied, but a Transport MGXS is not provided.' + msg = 'NuTransport MGXS type is required since a "P0" correction' \ + ' is applied, but a Transport MGXS is not provided.' warn(msg) elif (((self.correction is None) and ('total' not in self.mgxs_types))): diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 408175f43..99942361b 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -829,7 +829,8 @@ class XSdata(object): def set_scatter_mgxs(self, scatter, nuclide='total', xs_type='macro'): """This method allows for an openmc.mgxs.ScatterMatrixXS to be used to set the scatter matrix cross section for this XSdata - object. + object. If the XsData.order attribute has not yet been set, then + it will be set based on the properties of scatter. Parameters ---------- @@ -856,9 +857,35 @@ class XSdata(object): check_value('domain_type', scatter.domain_type, ['universe', 'cell', 'material']) + # Methods of representing anisotropic scattering besides + # Legendre expansions have not been implemented yet in openmc.mgxs. + # Therefore check to make sure the XsData has been set to + # legendre scattering. + if (self.scatt_type != 'legendre'): + msg = 'Anisotrpic scattering representations other than ' \ + 'Legendre expansions have not yet been implemented in ' \ + 'openmc.mgxs.' + raise ValueError(msg) + + # If the user has not defined XsData.order, then we will set + # the order based on the data within scatter. + # Otherwise, we will check to see that XsData.order to match + # the order of scatter + if self.order is None: + self.order = scatter.legendre_order + else: + check_value('legendre_order', scatter.legendre_order, + [self.order]) + if self._representation is 'isotropic': - self._scatter = np.array([scatter.get_xs(nuclides=nuclide, - xs_type=xs_type)]) + # Get the scattering orders in the outermost dimension + self._scatter = np.zeros((self.num_orders, + self.energy_groups.num_groups, + self.energy_groups.num_groups)) + for moment in range(self.num_orders): + self._scatter[moment, :, :] = scatter.get_xs(nuclides=nuclide, + xs_type=xs_type, + moment=moment) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' @@ -908,10 +935,12 @@ class XSdata(object): ['universe', 'cell', 'material']) if self._representation is 'isotropic': + # import pdb; pdb.set_trace() + nuscatt = nuscatter.get_xs(nuclides=nuclide, - xs_type=xs_type) + xs_type=xs_type, moment=0) scatt = scatter.get_xs(nuclides=nuclide, - xs_type=xs_type) + xs_type=xs_type, moment=0) self._multiplicity = np.divide(nuscatt, scatt) elif self._representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' @@ -969,7 +998,8 @@ class XSdata(object): if self._tabular_legendre is not None: subelement = ET.SubElement(element, 'tabular_legendre') subelement.set('enable', str(self._tabular_legendre['enable'])) - subelement.set('num_points', str(self._tabular_legendre['num_points'])) + subelement.set('num_points', + str(self._tabular_legendre['num_points'])) if self._total is not None: subelement = ET.SubElement(element, 'total') From b1516c91849989f40ac011e77af659409d34de94 Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Tue, 17 May 2016 21:24:03 -0400 Subject: [PATCH 146/147] Updated per minor edits from @wbinventor and added a routine to calculate the mgxs_library and Materials objects --- .../pythonapi/examples/mgxs-part-iv.ipynb | 178 +++++++++--------- openmc/mgxs/library.py | 118 +++++++++++- openmc/mgxs_library.py | 50 +++-- 3 files changed, 222 insertions(+), 124 deletions(-) diff --git a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb index e1d61cedc..4b73cf3ca 100644 --- a/docs/source/pythonapi/examples/mgxs-part-iv.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-iv.ipynb @@ -433,7 +433,7 @@ "outputs": [ { "data": { - "image/png": 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+ "image/png": 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"text/plain": [ "" ] @@ -724,7 +724,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 058ba68895a2f880402fda3d58cfb14b162931d9\n", - " Date/Time: 2016-05-17 05:32:34\n", + " Date/Time: 2016-05-17 21:14:05\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -811,20 +811,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 1.4400E+00 seconds\n", - " Reading cross sections = 1.1340E+00 seconds\n", - " Total time in simulation = 1.8207E+01 seconds\n", - " Time in transport only = 1.8125E+01 seconds\n", - " Time in inactive batches = 2.1170E+00 seconds\n", - " Time in active batches = 1.6090E+01 seconds\n", - " Time synchronizing fission bank = 3.0000E-03 seconds\n", - " Sampling source sites = 2.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for initialization = 1.4530E+00 seconds\n", + " Reading cross sections = 1.1470E+00 seconds\n", + " Total time in simulation = 1.8747E+01 seconds\n", + " Time in transport only = 1.8639E+01 seconds\n", + " Time in inactive batches = 2.1690E+00 seconds\n", + " Time in active batches = 1.6578E+01 seconds\n", + " Time synchronizing fission bank = 6.0000E-03 seconds\n", + " Sampling source sites = 4.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.9657E+01 seconds\n", - " Calculation Rate (inactive) = 23618.3 neutrons/second\n", - " Calculation Rate (active) = 12430.1 neutrons/second\n", + " Total time elapsed = 2.0209E+01 seconds\n", + " Calculation Rate (inactive) = 23052.1 neutrons/second\n", + " Calculation Rate (active) = 12064.2 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", @@ -1099,7 +1099,7 @@ " License: http://openmc.readthedocs.io/en/latest/license.html\n", " Version: 0.7.1\n", " Git SHA1: 058ba68895a2f880402fda3d58cfb14b162931d9\n", - " Date/Time: 2016-05-17 05:32:54\n", + " Date/Time: 2016-05-17 21:14:26\n", " OpenMP Threads: 4\n", "\n", " ===========================================================================\n", @@ -1124,56 +1124,56 @@ "\n", " Bat./Gen. k Average k \n", " ========= ======== ==================== \n", - " 1/1 1.02235 \n", - " 2/1 1.01108 \n", - " 3/1 1.02801 \n", - " 4/1 1.01404 \n", - " 5/1 1.03423 \n", - " 6/1 1.03282 \n", - " 7/1 1.04060 \n", - " 8/1 1.01152 \n", - " 9/1 1.02063 \n", - " 10/1 1.02604 \n", - " 11/1 1.02137 \n", - " 12/1 1.01416 1.01776 +/- 0.00360\n", - " 13/1 1.00239 1.01264 +/- 0.00553\n", - " 14/1 1.04293 1.02021 +/- 0.00852\n", - " 15/1 1.02029 1.02023 +/- 0.00660\n", - " 16/1 1.01512 1.01938 +/- 0.00546\n", - " 17/1 1.02098 1.01960 +/- 0.00462\n", - " 18/1 1.05954 1.02460 +/- 0.00640\n", - " 19/1 1.02347 1.02447 +/- 0.00564\n", - " 20/1 1.03063 1.02509 +/- 0.00508\n", - " 21/1 1.04679 1.02706 +/- 0.00500\n", - " 22/1 1.01301 1.02589 +/- 0.00472\n", - " 23/1 1.00936 1.02462 +/- 0.00452\n", - " 24/1 1.01030 1.02360 +/- 0.00431\n", - " 25/1 1.03799 1.02456 +/- 0.00412\n", - " 26/1 1.00404 1.02327 +/- 0.00406\n", - " 27/1 1.02987 1.02366 +/- 0.00384\n", - " 28/1 1.00107 1.02241 +/- 0.00383\n", - " 29/1 1.01460 1.02200 +/- 0.00365\n", - " 30/1 1.01433 1.02161 +/- 0.00348\n", - " 31/1 1.01566 1.02133 +/- 0.00332\n", - " 32/1 1.03339 1.02188 +/- 0.00321\n", - " 33/1 1.03974 1.02265 +/- 0.00317\n", - " 34/1 1.03136 1.02302 +/- 0.00306\n", - " 35/1 1.05175 1.02417 +/- 0.00315\n", - " 36/1 1.05444 1.02533 +/- 0.00324\n", - " 37/1 1.02432 1.02529 +/- 0.00312\n", - " 38/1 1.01464 1.02491 +/- 0.00303\n", - " 39/1 1.01086 1.02443 +/- 0.00296\n", - " 40/1 1.02492 1.02444 +/- 0.00286\n", - " 41/1 1.02882 1.02459 +/- 0.00277\n", - " 42/1 1.00377 1.02394 +/- 0.00276\n", - " 43/1 0.97480 1.02245 +/- 0.00306\n", - " 44/1 1.03623 1.02285 +/- 0.00300\n", - " 45/1 1.02606 1.02294 +/- 0.00291\n", - " 46/1 1.01771 1.02280 +/- 0.00284\n", - " 47/1 1.05400 1.02364 +/- 0.00288\n", - " 48/1 1.01844 1.02350 +/- 0.00281\n", - " 49/1 1.00754 1.02309 +/- 0.00277\n", - " 50/1 1.02902 1.02324 +/- 0.00270\n", + " 1/1 1.06913 \n", + " 2/1 1.04067 \n", + " 3/1 1.01854 \n", + " 4/1 1.00203 \n", + " 5/1 1.03243 \n", + " 6/1 1.02688 \n", + " 7/1 1.06855 \n", + " 8/1 1.03420 \n", + " 9/1 1.01657 \n", + " 10/1 1.02795 \n", + " 11/1 1.01796 \n", + " 12/1 1.03372 1.02584 +/- 0.00788\n", + " 13/1 1.02433 1.02534 +/- 0.00458\n", + " 14/1 1.01147 1.02187 +/- 0.00474\n", + " 15/1 1.01215 1.01993 +/- 0.00416\n", + " 16/1 1.04088 1.02342 +/- 0.00487\n", + " 17/1 1.04033 1.02583 +/- 0.00477\n", + " 18/1 1.04483 1.02821 +/- 0.00477\n", + " 19/1 1.02870 1.02826 +/- 0.00420\n", + " 20/1 1.01339 1.02678 +/- 0.00404\n", + " 21/1 1.03389 1.02742 +/- 0.00371\n", + " 22/1 1.02535 1.02725 +/- 0.00340\n", + " 23/1 1.00225 1.02533 +/- 0.00367\n", + " 24/1 0.99938 1.02347 +/- 0.00387\n", + " 25/1 1.01620 1.02299 +/- 0.00363\n", + " 26/1 1.03393 1.02367 +/- 0.00347\n", + " 27/1 1.01875 1.02338 +/- 0.00327\n", + " 28/1 1.00305 1.02225 +/- 0.00328\n", + " 29/1 1.01453 1.02185 +/- 0.00313\n", + " 30/1 1.02891 1.02220 +/- 0.00299\n", + " 31/1 0.99612 1.02096 +/- 0.00311\n", + " 32/1 1.04911 1.02224 +/- 0.00323\n", + " 33/1 1.01410 1.02188 +/- 0.00310\n", + " 34/1 0.98979 1.02055 +/- 0.00326\n", + " 35/1 1.00938 1.02010 +/- 0.00316\n", + " 36/1 1.02857 1.02043 +/- 0.00305\n", + " 37/1 1.04095 1.02119 +/- 0.00303\n", + " 38/1 1.02033 1.02115 +/- 0.00292\n", + " 39/1 1.02104 1.02115 +/- 0.00282\n", + " 40/1 1.00854 1.02073 +/- 0.00276\n", + " 41/1 1.00932 1.02036 +/- 0.00269\n", + " 42/1 1.00284 1.01982 +/- 0.00266\n", + " 43/1 1.02489 1.01997 +/- 0.00258\n", + " 44/1 1.03981 1.02055 +/- 0.00257\n", + " 45/1 1.02630 1.02072 +/- 0.00251\n", + " 46/1 1.00133 1.02018 +/- 0.00249\n", + " 47/1 1.02409 1.02028 +/- 0.00243\n", + " 48/1 1.03928 1.02078 +/- 0.00241\n", + " 49/1 1.01226 1.02057 +/- 0.00236\n", + " 50/1 1.03536 1.02094 +/- 0.00233\n", " Creating state point statepoint.50.h5...\n", "\n", " ===========================================================================\n", @@ -1183,27 +1183,27 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 4.7000E-02 seconds\n", - " Reading cross sections = 6.0000E-03 seconds\n", - " Total time in simulation = 1.4145E+01 seconds\n", - " Time in transport only = 1.4098E+01 seconds\n", - " Time in inactive batches = 1.2400E+00 seconds\n", - " Time in active batches = 1.2905E+01 seconds\n", - " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 3.0000E-03 seconds\n", - " SEND/RECV source sites = 1.0000E-03 seconds\n", - " Time accumulating tallies = 1.0000E-03 seconds\n", + " Total time for initialization = 4.6000E-02 seconds\n", + " Reading cross sections = 8.0000E-03 seconds\n", + " Total time in simulation = 1.4524E+01 seconds\n", + " Time in transport only = 1.4457E+01 seconds\n", + " Time in inactive batches = 1.3350E+00 seconds\n", + " Time in active batches = 1.3189E+01 seconds\n", + " Time synchronizing fission bank = 7.0000E-03 seconds\n", + " Sampling source sites = 5.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", + " Time accumulating tallies = 0.0000E+00 seconds\n", " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 1.4201E+01 seconds\n", - " Calculation Rate (inactive) = 40322.6 neutrons/second\n", - " Calculation Rate (active) = 15497.9 neutrons/second\n", + " Total time elapsed = 1.4579E+01 seconds\n", + " Calculation Rate (inactive) = 37453.2 neutrons/second\n", + " Calculation Rate (active) = 15164.2 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", - " k-effective (Collision) = 1.02379 +/- 0.00230\n", - " k-effective (Track-length) = 1.02324 +/- 0.00270\n", - " k-effective (Absorption) = 1.02813 +/- 0.00172\n", - " Combined k-effective = 1.02680 +/- 0.00165\n", + " k-effective (Collision) = 1.02358 +/- 0.00231\n", + " k-effective (Track-length) = 1.02094 +/- 0.00233\n", + " k-effective (Absorption) = 1.02682 +/- 0.00152\n", + " Combined k-effective = 1.02527 +/- 0.00153\n", " Leakage Fraction = 0.00000 +/- 0.00000\n", "\n" ] @@ -1285,8 +1285,8 @@ "output_type": "stream", "text": [ "Continuous-Energy keff = 1.024295\n", - "Multi-Group keff = 1.026805\n", - "bias [pcm]: -251.0\n" + "Multi-Group keff = 1.025274\n", + "bias [pcm]: -97.9\n" ] } ], @@ -1302,7 +1302,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "This shows a 251 pcm bias between the two methods. Some degree of mismatch is expected simply to the very few histories being used in these example problems. An additional mismatch is always inherent in the practical application of multi-group theory due to the high degree of approximations inherent in that method." + "This shows a nontrivial pcm bias between the two methods. Some degree of mismatch is expected simply to the very few histories being used in these example problems. An additional mismatch is always inherent in the practical application of multi-group theory due to the high degree of approximations inherent in that method." ] }, { @@ -1383,7 +1383,7 @@ { "data": { "text/plain": [ - "" + "" ] }, "execution_count": 41, @@ -1392,9 +1392,9 @@ }, { "data": { - "image/png": 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"text/plain": [ - "" + "" ] }, "metadata": {}, diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index e5728a812..20302b624 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -774,8 +774,8 @@ class Library(object): xs_ids : str Cross section set identifier. Defaults to '1m'. order : Scattering order for this data entry. Default is None, - which will force the XSdata object to use whatever the order of the - Library object is. + which will set the XSdata object to use the order of the + Library. Returns ------- @@ -803,6 +803,7 @@ class Library(object): cv.check_type('order', order, (type(None), Integral)) if order is not None: cv.check_greater_than('order', order, 0, equality=True) + cv.check_less_than('order', order, 10, equality=True) # Make sure statepoint has been loaded if self._sp_filename is None: @@ -834,7 +835,7 @@ class Library(object): xsdata.awr = self._nuclides[nuclide][1] # Now get xs data itself - if ('nu-transport' in self.mgxs_types) and (self.correction == 'P0'): + if 'nu-transport' in self.mgxs_types and self.correction == 'P0': mymgxs = self.get_mgxs(domain, 'nu-transport') xsdata.set_total_mgxs(mymgxs, xs_type=xs_type, nuclide=[nuclide]) elif 'total' in self.mgxs_types: @@ -974,6 +975,104 @@ class Library(object): return mgxs_file + def create_mg_library_and_materials(self, xsdata_names=None, xs_ids=None, + material_ids=None): + """Creates an openmc.MGXSLibrary object to contain the MGXS data for the + Multi-Group mode of OpenMC as well as the associated openmc.Materials + objects. This method cannot be used for Library objects with + `Library.by_nuclide == True` since the materials to output would be + problem dependent and thus any Materials object produced by this method + would not be useful. + + Parameters + ---------- + xsdata_names : Iterable of str + List of names to apply to the "xsdata" entries in the + resultant mgxs data file. Defaults to 'set1', 'set2', ... + xs_ids : str or Iterable of str + Cross section set identifier (i.e., '71c') for all + data sets (if only str) or for each individual one + (if iterable of str). Defaults to '1m'. + material_ids : None or Iterable of Integral + An optional list of material IDs to pass to the materials in + materials_file. Defaults to `None` implying the materials will be + given an ID number which matches the index of the domain in + `self.domains` + + Returns + ------- + mgxs_file : openmc.MGXSLibrary + Multi-Group Cross Section File that is ready to be printed to the + file of choice by the user. + materials_file : openmc.Materials + Materials file ready to be printed with all the macroscopic data + present within this Library. + + Raises + ------ + ValueError + When the Library object is initialized with insufficient types of + cross sections for the Library. + + See also + -------- + Library.create_mg_library() + Library.dump_to_file() + + """ + + # Check to ensure the Library contains the correct + # multi-group cross section types + self.check_library_for_openmc_mgxs() + + if xsdata_names is not None: + cv.check_iterable_type('xsdata_names', xsdata_names, basestring) + if xs_ids is not None: + if isinstance(xs_ids, basestring): + # If we only have a string lets convert it now to a list + # of strings. + xs_ids = [xs_ids for i in range(len(self.domains))] + else: + cv.check_iterable_type('xs_ids', xs_ids, basestring) + else: + xs_ids = ['1m' for i in range(len(self.domains))] + if material_ids is not None: + cv.check_iterable_type('material_ids', material_ids, Integral) + xs_type = 'macro' + + # Initialize files + mgxs_file = openmc.MGXSLibrary(self.energy_groups) + + materials = [] + macroscopics = [] + nuclide = 'total' + # Create the xsdata object and add it to the mgxs_file + for i, domain in enumerate(self.domains): + # Build & add metadata to XSdata object + if xsdata_names is None: + xsdata_name = 'set' + str(i + 1) + else: + xsdata_name = xsdata_names[i] + + xsdata = self.get_xsdata(domain, xsdata_name, nuclide=nuclide, + xs_type=xs_type, xs_id=xs_ids[i]) + + mgxs_file.add_xsdata(xsdata) + + macroscopics.append(openmc.Macroscopic(name=xsdata_name, + xs=xs_ids[i])) + if material_ids is not None: + mat_id = material_ids[i] + else: + mat_id = i + materials.append(openmc.Material(name=xsdata_name + '.' + + xs_ids[i], material_id=mat_id)) + materials[-1].add_macroscopic(macroscopics[-1]) + + materials_file = openmc.Materials(materials) + + return (mgxs_file, materials_file) + def check_library_for_openmc_mgxs(self): """This routine will check the MGXS Types within a Library to ensure the MGXS types provided can be used to create @@ -1009,12 +1108,12 @@ class Library(object): # Ensure absorption is present if 'absorption' not in self.mgxs_types: error_flag = True - msg = 'Absorption MGXS type is required but not provided.' + msg = '"absorption" MGXS type is required but not provided.' warn(msg) # Ensure nu-scattering matrix is required if 'nu-scatter matrix' not in self.mgxs_types: error_flag = True - msg = 'Nu-Scatter Matrix MGXS type is required but not provided.' + msg = '"nu-scatter matrix" MGXS type is required but not provided.' warn(msg) else: # Ok, now see the status of scatter @@ -1023,7 +1122,7 @@ class Library(object): # we need total, and not transport. if 'total' not in self.mgxs_types: error_flag = True - msg = 'Total MGXS type is required if a ' \ + msg = '"total" MGXS type is required if a ' \ 'scattering matrix is not provided.' warn(msg) # Total or transport can be present, but if using @@ -1031,13 +1130,14 @@ class Library(object): if (((self.correction is "P0") and ('nu-transport' not in self.mgxs_types))): error_flag = True - msg = 'NuTransport MGXS type is required since a "P0" correction' \ - ' is applied, but a Transport MGXS is not provided.' + msg = 'A "nu-transport" MGXS type is required since a "P0" ' \ + 'correction is applied, but a "nu-transport" MGXS is ' \ + 'not provided.' warn(msg) elif (((self.correction is None) and ('total' not in self.mgxs_types))): error_flag = True - msg = 'Total MGXS type is required, but not provided.' + msg = '"total" MGXS type is required, but not provided.' warn(msg) if error_flag: diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 99942361b..88ae05808 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -137,6 +137,10 @@ class XSdata(object): ``representation``. matrix_shape : iterable of int Dimensionality of matrix multi-group cross sections (e.g., the + fission matrix cross section). The return result depends on the + value of ``representation``. + pn_matrix_shape : iterable of int + Dimensionality of scattering matrix data (e.g., the scattering matrix cross section). The return result depends on the value of ``representation``. total : numpy.ndarray @@ -621,9 +625,9 @@ class XSdata(object): check_value('domain_type', total.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._total = total.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -657,10 +661,10 @@ class XSdata(object): check_value('domain_type', absorption.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._absorption = absorption.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -693,10 +697,10 @@ class XSdata(object): check_value('domain_type', fission.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._fission = fission.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -733,10 +737,10 @@ class XSdata(object): check_value('domain_type', nu_fission.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._nu_fission = nu_fission.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -776,10 +780,10 @@ class XSdata(object): check_value('domain_type', k_fission.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._kappa_fission = k_fission.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -816,10 +820,10 @@ class XSdata(object): check_value('domain_type', chi.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': + if self.representation is 'isotropic': self._chi = chi.get_xs(nuclides=nuclide, xs_type=xs_type) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -829,7 +833,7 @@ class XSdata(object): def set_scatter_mgxs(self, scatter, nuclide='total', xs_type='macro'): """This method allows for an openmc.mgxs.ScatterMatrixXS to be used to set the scatter matrix cross section for this XSdata - object. If the XsData.order attribute has not yet been set, then + object. If the XSdata.order attribute has not yet been set, then it will be set based on the properties of scatter. Parameters @@ -857,19 +861,15 @@ class XSdata(object): check_value('domain_type', scatter.domain_type, ['universe', 'cell', 'material']) - # Methods of representing anisotropic scattering besides - # Legendre expansions have not been implemented yet in openmc.mgxs. - # Therefore check to make sure the XsData has been set to - # legendre scattering. if (self.scatt_type != 'legendre'): - msg = 'Anisotrpic scattering representations other than ' \ + msg = 'Anisotropic scattering representations other than ' \ 'Legendre expansions have not yet been implemented in ' \ 'openmc.mgxs.' raise ValueError(msg) - # If the user has not defined XsData.order, then we will set + # If the user has not defined XSdata.order, then we will set # the order based on the data within scatter. - # Otherwise, we will check to see that XsData.order to match + # Otherwise, we will check to see that XSdata.order to match # the order of scatter if self.order is None: self.order = scatter.legendre_order @@ -877,7 +877,7 @@ class XSdata(object): check_value('legendre_order', scatter.legendre_order, [self.order]) - if self._representation is 'isotropic': + if self.representation is 'isotropic': # Get the scattering orders in the outermost dimension self._scatter = np.zeros((self.num_orders, self.energy_groups.num_groups, @@ -887,7 +887,7 @@ class XSdata(object): xs_type=xs_type, moment=moment) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) @@ -934,15 +934,13 @@ class XSdata(object): check_value('domain_type', scatter.domain_type, ['universe', 'cell', 'material']) - if self._representation is 'isotropic': - # import pdb; pdb.set_trace() - + if self.representation is 'isotropic': nuscatt = nuscatter.get_xs(nuclides=nuclide, xs_type=xs_type, moment=0) scatt = scatter.get_xs(nuclides=nuclide, xs_type=xs_type, moment=0) self._multiplicity = np.divide(nuscatt, scatt) - elif self._representation is 'angle': + elif self.representation is 'angle': msg = 'Angular-Dependent MGXS have not yet been implemented' raise ValueError(msg) self._multiplicity = np.nan_to_num(self._multiplicity) From 5a9dc631357d5bdd7360b1bd22a1fe8f1576bd82 Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Thu, 19 May 2016 21:26:46 -0400 Subject: [PATCH 147/147] Use ACE data over WMP data where possible With this commit energy grid points and cross sections (including inelastic) will be unaffected by included WMP --- src/multipole.F90 | 239 +++++++++++++++----------- tests/test_multipole/results_true.dat | 2 +- 2 files changed, 135 insertions(+), 106 deletions(-) diff --git a/src/multipole.F90 b/src/multipole.F90 index caadab90f..59c7fed69 100644 --- a/src/multipole.F90 +++ b/src/multipole.F90 @@ -6,6 +6,7 @@ module multipole use hdf5_interface use multipole_header, only: MultipoleArray, FIT_T, FIT_A, FIT_F, & MP_FISS, FORM_MLBW, FORM_RM + use search, only: binary_search implicit none @@ -23,25 +24,28 @@ contains type(MultipoleArray), intent(out), target :: multipole ! The object to fill integer, intent(in) :: i_table ! index in nuclides/ ! sab_tables - integer(HID_T) :: file_id integer(HID_T) :: group_id - - ! Intermediate loading components - integer :: NMT - integer :: i, j - integer, allocatable :: MT(:) - logical :: accumulated_fission - character(len=24) :: MT_n ! Takes the form '/nuclide/reactions/MT???' integer :: is_fissionable + real(8) :: insert_pts(4) ! New points in the energy grid + integer :: cut1, cut2 ! Old indices just outside MP region + integer :: new_n_grid ! Number of points in new E grid + real(8), allocatable :: new_energy(:) ! New energy grid + real(8) :: f1, f2 ! Interpolation near cut1 & cut2 + real(8), allocatable :: new_xs(:) ! New cross sections + integer :: i + integer :: IE ! Reaction threshold associate (nuc => nuclides(i_table)) - ! Open file for reading and move into the /isotope group + !========================================================================= + ! Copy in data from the file. + + ! Open file for reading and move into the /isotope group. file_id = file_open(filename, 'r', parallel=.true.) group_id = open_group(file_id, "/nuclide") - ! Load in all the array size scalars + ! Load in all the array size scalars. call read_dataset(multipole % length, group_id, "length") call read_dataset(multipole % windows, group_id, "windows") call read_dataset(multipole % num_l, group_id, "num_l") @@ -60,10 +64,10 @@ contains call read_dataset(multipole % start_E, group_id, "start_E") call read_dataset(multipole % end_E, group_id, "end_E") - ! Allocate the multipole array components + ! Allocate the multipole array components. call multipole % allocate() - ! Read in arrays + ! Read in arrays. call read_dataset(multipole % data, group_id, "data") call read_dataset(multipole % pseudo_k0RS, group_id, "pseudo_K0RS") call read_dataset(multipole % l_value, group_id, "l_value") @@ -73,113 +77,138 @@ contains call read_dataset(multipole % curvefit, group_id, "curvefit") - ! Delete ACE pointwise data - call read_dataset(nuc % n_grid, group_id, "n_grid") - - deallocate(nuc % energy) - deallocate(nuc % total) - deallocate(nuc % elastic) - deallocate(nuc % fission) - deallocate(nuc % nu_fission) - deallocate(nuc % absorption) - - allocate(nuc % energy(nuc % n_grid)) - allocate(nuc % total(nuc % n_grid)) - allocate(nuc % elastic(nuc % n_grid)) - allocate(nuc % fission(nuc % n_grid)) - allocate(nuc % nu_fission(nuc % n_grid)) - allocate(nuc % absorption(nuc % n_grid)) - - nuc % total(:) = ZERO - nuc % absorption(:) = ZERO - nuc % fission(:) = ZERO - - ! Read in new energy axis (converting eV to MeV) - call read_dataset(nuc % energy, group_id, "energy_points") - nuc % energy = nuc % energy / 1.0e6_8 - - ! Get count and list of MT tables - call read_dataset(NMT, group_id, "MT_count") - allocate(MT(NMT)) - - call read_dataset(MT, group_id, "MT_list") - + ! Close the file. call close_group(group_id) + call file_close(file_id) - accumulated_fission = .false. + !========================================================================= + ! Remove the uneeded/inconsitent pointwise data. This step enforces the + ! assumption that no inelastic scattering reactions can occur in the + ! multipole region. The energy grid is replaced with one that removes all + ! energies covered by multiple and adds four new points. Two new points + ! mark the edges of the multipole region and cross sections will be + ! interpolated to these points. The other two points are used to zero the + ! cross sections inside the multipole region. - ! Loop over each MT entry and load it into a reaction. - do i = 1, NMT - write(MT_n, '(A, I3.3)') '/nuclide/reactions/MT', MT(i) + ! Define the four new inserted points. + insert_pts(:) = [multipole % start_E / 1e6_8, & + multipole % start_E / 1e6_8 + 1e-12_8, & + multipole % end_E / 1e6_8 - 1e-12_8, & + multipole % end_E / 1e6_8] - group_id = open_group(file_id, MT_n) + ! Find the points just outside the multipole region. + cut1 = binary_search(nuc % energy, nuc % n_grid, insert_pts(1)) + cut2 = binary_search(nuc % energy, nuc % n_grid, insert_pts(4)) + 1 + if (nuc % energy(cut1) == insert_pts(1)) cut1 = cut1 - 1 + if (nuc % energy(cut2) == insert_pts(4)) cut2 = cut2 + 1 - ! Each MT needs to be treated slightly differently. - select case (MT(i)) - case(ELASTIC) - call read_dataset(nuc % elastic, group_id, "MT_sigma") - nuc % total(:) = nuc % total + nuc % elastic - case(N_FISSION) - call read_dataset(nuc % fission, group_id, "MT_sigma") - nuc % total(:) = nuc % total + nuc % fission - nuc % absorption(:) = nuc % absorption + nuc % fission - accumulated_fission = .true. - case default - ! Search through all of our secondary reactions - do j = 1, nuc % n_reaction - if (nuc % reactions(j) % MT == MT(i)) then - ! Match found + ! Generate the new energy grid. + new_n_grid = nuc % n_grid - (cut2 - cut1 - 1) + 4 + allocate(new_energy(new_n_grid)) + new_energy(1:cut1) = nuc % energy(1:cut1) + new_energy(cut1+1:cut1+4) = insert_pts(:) + new_energy(cut1+5:new_n_grid) = nuc % energy(cut2:nuc % n_grid) - ! Individual Fission components exist, so remove the combined - ! fission cross section. - if ( (MT(i) == N_F .or. MT(i) == N_NF .or. MT(i) == N_2NF & - .or. MT(i) == N_3NF) .and. accumulated_fission) then - nuc % total(:) = nuc % total - nuc % fission - nuc % absorption(:) = nuc % absorption - nuc % fission - nuc % fission(:) = ZERO - accumulated_fission = .false. - end if + ! Compute interpolation factors for the new energy points. + f1 = (insert_pts(1) - nuc % energy(cut1)) & + / (nuc % energy(cut1+1) - nuc % energy(cut1)) + f2 = (insert_pts(4) - nuc % energy(cut2-1)) & + / (nuc % energy(cut2) - nuc % energy(cut2-1)) - deallocate(nuc % reactions(j) % sigma) - allocate(nuc % reactions(j) % sigma(nuc % n_grid)) + ! Adjust the total cross section. + allocate(new_xs(new_n_grid)) + new_xs(1:cut1) = nuc % total(1:cut1) + new_xs(cut1+1) = (ONE - f1) * nuc % total(cut1) & + + f1 * nuc % total(cut1+1) + new_xs(cut1+2:cut1+3) = ZERO + new_xs(cut1+4) = (ONE - f2) * nuc % total(cut2-1) & + + f2 * nuc % total(cut2) + new_xs(cut1+5:new_n_grid) = nuc % total(cut2:nuc % n_grid) + call move_alloc(new_xs, nuc % total) - call read_dataset(nuc % reactions(j) % sigma, & - group_id, "MT_sigma") - call read_dataset(nuc % reactions(j) % Q_value, & - group_id, "Q_value") - call read_dataset(nuc % reactions(j) % threshold, & - group_id, "threshold") - nuc % reactions(j) % threshold = 1 ! TODO: reconsider implications. - nuc % reactions(j) % Q_value = nuc % reactions(j) % Q_value & - / 1.0e6_8 + ! Adjust the elastic cross section. + allocate(new_xs(new_n_grid)) + new_xs(1:cut1) = nuc % elastic(1:cut1) + new_xs(cut1+1) = (ONE - f1) * nuc % elastic(cut1) & + + f1 * nuc % elastic(cut1+1) + new_xs(cut1+2:cut1+3) = ZERO + new_xs(cut1+4) = (ONE - f2) * nuc % elastic(cut2-1) & + + f2 * nuc % elastic(cut2) + new_xs(cut1+5:new_n_grid) = nuc % elastic(cut2:nuc % n_grid) + call move_alloc(new_xs, nuc % elastic) - ! Accumulate total - if (MT(i) /= N_LEVEL .and. MT(i) <= N_DA) then - nuc % total(:) = nuc % total + nuc % reactions(j) % sigma - end if + ! Adjust the fission cross section. + allocate(new_xs(new_n_grid)) + new_xs(1:cut1) = nuc % fission(1:cut1) + new_xs(cut1+1) = (ONE - f1) * nuc % fission(cut1) & + + f1 * nuc % fission(cut1+1) + new_xs(cut1+2:cut1+3) = ZERO + new_xs(cut1+4) = (ONE - f2) * nuc % fission(cut2-1) & + + f2 * nuc % fission(cut2) + new_xs(cut1+5:new_n_grid) = nuc % fission(cut2:nuc % n_grid) + call move_alloc(new_xs, nuc % fission) - ! Accumulate absorption - if (MT(i) >= N_GAMMA .and. MT(i) <= N_DA) then - nuc % absorption(:) = nuc % absorption & - + nuc % reactions(j) % sigma - end if + ! Adjust the nu-fission cross section. + allocate(new_xs(new_n_grid)) + new_xs(1:cut1) = nuc % nu_fission(1:cut1) + new_xs(cut1+1) = (ONE - f1) * nuc % nu_fission(cut1) & + + f1 * nuc % nu_fission(cut1+1) + new_xs(cut1+2:cut1+3) = ZERO + new_xs(cut1+4) = (ONE - f2) * nuc % nu_fission(cut2-1) & + + f2 * nuc % nu_fission(cut2) + new_xs(cut1+5:new_n_grid) = nuc % nu_fission(cut2:nuc % n_grid) + call move_alloc(new_xs, nuc % nu_fission) - ! Accumulate fission (if needed) - if ( (MT(i) == N_F .or. MT(i) == N_NF .or. MT(i) == N_2NF & - .or. MT(i) == N_3NF) ) then - nuc % fission(:) = nuc % fission + nuc % reactions(j) % sigma - nuc % absorption(:) = nuc % absorption & - + nuc % reactions(j) % sigma - end if - end if - end do - end select + ! Adjust the absorption cross section. + allocate(new_xs(new_n_grid)) + new_xs(1:cut1) = nuc % absorption(1:cut1) + new_xs(cut1+1) = (ONE - f1) * nuc % absorption(cut1) & + + f1 * nuc % absorption(cut1+1) + new_xs(cut1+2:cut1+3) = ZERO + new_xs(cut1+4) = (ONE - f2) * nuc % absorption(cut2-1) & + + f2 * nuc % absorption(cut2) + new_xs(cut1+5:new_n_grid) = nuc % absorption(cut2:nuc % n_grid) + call move_alloc(new_xs, nuc % absorption) - call close_group(group_id) + ! Adjust other cross sections. + do i = 1, nuc % n_reaction + associate (rxn => nuc % reactions(i)) + if (.not. allocated(rxn % sigma)) cycle ! Skip unallocated reactions + IE = rxn % threshold + if (rxn % threshold >= cut2) then + ! The threshold is above the multipole range. All we need to do + ! is adjust the threshold index to match the new grid. + rxn % threshold = rxn % threshold - (cut2 - cut1 - 1) + 4 + else if (rxn % threshold <= cut1) then + ! The threhold is below the multipole range. Remove the multipole + ! region just like we did with the other reactions. + ! The new grid removed (cut2 - cut1 - 1) points and added 4. + allocate(new_xs(size(rxn % sigma) - (cut2 - cut1 - 1) + 4)) + new_xs(1:cut1-IE+1) = rxn % sigma(1:cut1-IE+1) + new_xs(cut1-IE+2) = (ONE - f1) * rxn % sigma(cut1-IE+1) & + + f1 * rxn % sigma(cut1-IE+2) + new_xs(cut1-IE+3:cut1-IE+4) = ZERO + new_xs(cut1-IE+5) = (ONE - f2) * rxn % sigma(cut2-IE) & + + f2 * rxn % sigma(cut2-IE+1) + new_xs(cut1-IE+6:size(new_xs)) = & + rxn % sigma(cut2-IE+1:size(rxn % sigma)) + call move_alloc(new_xs, rxn % sigma) + else + ! The threshold lies within the multipole range. Remove the first + ! cut2-IE points and add an interpolated point + allocate(new_xs(size(rxn % sigma) - (cut2-IE) + 1)) + new_xs(1) = (ONE - f2) * rxn % sigma(cut2-IE) & + + f2 * rxn % sigma(cut2-IE+1) + new_xs(2:size(new_xs)) = rxn % sigma(cut2-IE+1:size(rxn % sigma)) + call move_alloc(new_xs, rxn % sigma) + rxn % threshold = cut1 + 4 + end if + end associate end do - ! Close file - call file_close(file_id) + ! Apply the new energy grid. + nuc % n_grid = new_n_grid + call move_alloc(new_energy, nuc % energy) end associate diff --git a/tests/test_multipole/results_true.dat b/tests/test_multipole/results_true.dat index 83d7e762e..2c2b879fe 100644 --- a/tests/test_multipole/results_true.dat +++ b/tests/test_multipole/results_true.dat @@ -1,5 +1,5 @@ k-combined: -1.457760E+00 1.119659E-02 +1.457760E+00 1.119656E-02 Cell ID = 11 Name =