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Merged with latest changes and added interpolation to the MG library
This commit is contained in:
Adam Nelson
parent
8d35923405
commit
697dfb09c4
6 changed files with 321 additions and 229 deletions
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@ -94,7 +94,7 @@ module mgxs_header
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integer(HID_T), intent(in) :: xs_id ! Library data
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integer, intent(in) :: groups ! Number of Energy groups
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type(VectorReal), intent(in) :: temperature ! list of desired temperatures
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integer, intent(in) :: method ! Type of temperature access
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integer, intent(inout) :: method ! Type of temperature access
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real(8), intent(in) :: tolerance ! Tolerance on method
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logical, intent(in) :: get_kfiss ! Need Kappa-Fission?
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logical, intent(in) :: get_fiss ! Should we get fiss data?
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@ -206,7 +206,7 @@ module mgxs_header
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class(Mgxs), intent(inout) :: this ! Working Object
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integer(HID_T), intent(in) :: xs_id ! Group in H5 file
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type(VectorReal), intent(in) :: temperature ! list of desired temperatures
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integer, intent(in) :: method ! Type of temperature access
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integer, intent(inout) :: method ! Type of temperature access
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real(8), intent(in) :: tolerance ! Tolerance on method
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type(VectorInt), intent(out) :: temps_to_read ! Temperatures to read
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integer, intent(out) :: order_dim ! Scattering data order size
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@ -244,6 +244,16 @@ module mgxs_header
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! Convert MeV to Kelvin
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temps_available(i) = temps_available(i) / K_BOLTZMANN
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end do
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call sort(temps_available)
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! If only one temperature is available, revert to nearest temperature
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if (size(temps_available) == 1 .and. &
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method == TEMPERATURE_INTERPOLATION) then
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call warning("Cross sections for " // trim(this % name) // " are only &
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&available at one temperature. Reverting to nearest temperature &
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&method.")
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method = TEMPERATURE_NEAREST
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end if
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select case (method)
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case (TEMPERATURE_NEAREST)
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@ -264,8 +274,28 @@ module mgxs_header
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end do TEMP_LOOP
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case (TEMPERATURE_INTERPOLATION)
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! TODO: Get bounding temperatures
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call fatal_error("Temperature interpolation not yet implemented")
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! If temperature interpolation or multipole is selected, get a list of
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! bounding temperatures for each actual temperature present in the model
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TEMPS_LOOP: do i = 1, temperature % size()
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temp_desired = temperature % data(i)
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do j = 1, size(temps_available) - 1
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if (temps_available(j) <= temp_desired .and. &
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temp_desired < temps_available(j + 1)) then
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if (find(temps_to_read, nint(temps_available(j))) == -1) then
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call temps_to_read % push_back(nint(temps_available(j)))
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end if
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if (find(temps_to_read, nint(temps_available(j + 1))) == -1) then
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call temps_to_read % push_back(nint(temps_available(j + 1)))
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end if
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cycle TEMPS_LOOP
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end if
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end do
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call fatal_error("MGXS library does not contain cross sections &
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&for " // trim(this % name) // " at temperatures that bound " // &
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trim(to_str(nint(temp_desired))) // " K.")
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end do TEMPS_LOOP
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end select
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! Sort temperatures to read
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@ -369,7 +399,7 @@ module mgxs_header
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integer(HID_T), intent(in) :: xs_id ! Group in H5 file
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integer, intent(in) :: groups ! Number of Energy groups
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type(VectorReal), intent(in) :: temperature ! list of desired temperatures
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integer, intent(in) :: method ! Type of temperature access
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integer, intent(inout) :: method ! Type of temperature access
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real(8), intent(in) :: tolerance ! Tolerance on method
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logical, intent(in) :: get_kfiss ! Need Kappa-Fission?
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logical, intent(in) :: get_fiss ! Should we get fiss data?
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@ -660,7 +690,7 @@ module mgxs_header
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integer(HID_T), intent(in) :: xs_id ! Group in H5 file
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integer, intent(in) :: groups ! Number of Energy groups
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type(VectorReal), intent(in) :: temperature ! list of desired temperatures
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integer, intent(in) :: method ! Type of temperature access
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integer, intent(inout) :: method ! Type of temperature access
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real(8), intent(in) :: tolerance ! Tolerance on method
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logical, intent(in) :: get_kfiss ! Need Kappa-Fission?
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logical, intent(in) :: get_fiss ! Should we get fiss data?
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@ -1196,7 +1226,8 @@ module mgxs_header
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real(8), allocatable :: temp_mult(:, :), mult_num(:, :), mult_denom(:, :)
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real(8), allocatable :: scatt_coeffs(:, :, :)
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integer :: nuc_t
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real(8) :: temp_actual, temp_desired
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integer, allocatable :: nuc_ts(:)
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real(8) :: temp_actual, temp_desired, interp
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integer :: scatter_type
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type(Jagged2D), allocatable :: nuc_matrix(:)
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integer, allocatable :: gmin(:), gmax(:)
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@ -1243,12 +1274,16 @@ module mgxs_header
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! Add contribution from each nuclide in material
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NUC_LOOP: do i = 1, mat % n_nuclides
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associate(nuc => nuclides(mat % nuclide(i)) % obj)
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! Copy atom density of nuclide in material
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atom_density = mat % atom_density(i)
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select case (method)
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case (TEMPERATURE_NEAREST)
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! Determine actual temperatures to read
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temp_desired = temps % data(i)
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nuc_t = minloc(abs(nuc % kTs - temp_desired), dim=1)
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temp_actual = nuc % kTs(nuc_t)
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allocate(nuc_ts(1))
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nuc_ts(1) = minloc(abs(nuc % kTs - temp_desired), dim=1)
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temp_actual = nuc % kTs(nuc_ts(1))
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if (abs(temp_actual - temp_desired) >= tolerance) then
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call fatal_error("MGXS library does not contain cross sections &
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&for " // trim(this % name) // " at or near " // &
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@ -1256,80 +1291,106 @@ module mgxs_header
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end if
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case (TEMPERATURE_INTERPOLATION)
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! TODO: Get bounding temperatures
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call fatal_error("Temperature interpolation not yet implemented")
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end select
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! If temperature interpolation or multipole is selected, get a
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! list of bounding temperatures for each actual temperature
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! present in the model
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temp_desired = temps % data(i)
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allocate(nuc_ts(2))
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do j = 1, size(nuc % kTs) - 1
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if (nuc % kTs(j) <= temp_desired .and. &
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temp_desired < nuc % kTs(j + 1)) then
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nuc_ts(1) = j
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nuc_ts(2) = j + 1
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end if
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end do
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! Copy atom density of nuclide in material
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atom_density = mat % atom_density(i)
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call fatal_error("Nuclear data library does not contain cross sections &
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&for " // trim(this % name) // " at temperatures that bound " // &
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trim(to_str(nint(temp_desired))) // " K.")
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end select
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select type(nuc)
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type is (MgxsIso)
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! Perform our operations which depend upon the type
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! Add contributions to total, absorption, and fission data (if necessary)
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this % xs(t) % total = this % xs(t) % total + &
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atom_density * nuc % xs(nuc_t) % total
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this % xs(t) % absorption = this % xs(t) % absorption + &
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atom_density * nuc % xs(nuc_t) % absorption
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if (nuc % fissionable) then
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this % xs(t) % chi = this % xs(t) % chi + &
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atom_density * nuc % xs(nuc_t) % chi
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this % xs(t) % nu_fission = this % xs(t) % nu_fission + &
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atom_density * nuc % xs(nuc_t) % nu_fission
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if (allocated(nuc % xs(nuc_t) % fission)) then
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this % xs(t) % fission = this % xs(t) % fission + &
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atom_density * nuc % xs(nuc_t) % fission
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do j = 1, size(nuc_ts)
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nuc_t = nuc_ts(j)
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if (size(nuc_ts) == 1) then
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interp = ONE
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else if (j == 1) then
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interp = (ONE - (temp_desired - nuc % kTs(nuc_ts(1))) / &
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(nuc % kTs(nuc_ts(2)) - nuc % kTs(nuc_ts(1))))
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else
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interp = ONE - interp
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end if
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if (allocated(nuc % xs(nuc_t) % k_fission)) then
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this % xs(t) % k_fission = this % xs(t) % k_fission + &
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atom_density * nuc % xs(nuc_t) % k_fission
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end if
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end if
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! We will next gather the multiplicaity and scattering matrices.
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! To avoid multiple re-allocations as we resize the storage
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! matrix (and/or to avoidlots of duplicate code), we will use a
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! dense matrix for this storage, with a reduction to the sparse
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! format at the end.
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! Get the multiplicity matrix
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! To combine from nuclidic data we need to use the final relationship
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) /
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! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'}))
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! Developed as follows:
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! mult_{gg'} = nuScatt{g,g'} / Scatt{g,g'}
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / sum(N_i*scatt_{i,g,g'})
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) /
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! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'}))
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! nuscatt_{i,g,g'} can be reconstructed from scatter % energy and
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! scatter % scattxs
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do gin = 1, groups
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do gout = nuc % xs(nuc_t) % scatter % gmin(gin), nuc % xs(nuc_t) % scatter % gmax(gin)
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nuscatt = nuc % xs(nuc_t) % scatter % scattxs(gin) * &
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nuc % xs(nuc_t) % scatter % energy(gin) % data(gout)
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mult_num(gout, gin) = mult_num(gout, gin) + atom_density * &
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nuscatt
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if (nuc % xs(nuc_t) % scatter % mult(gin) % data(gout) > ZERO) then
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mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * &
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nuscatt / nuc % xs(nuc_t) % scatter % mult(gin) % data(gout)
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else
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! Avoid division by zero
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mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density
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! Perform our operations which depend upon the type
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! Add contributions to total, absorption, and fission data (if necessary)
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this % xs(t) % total = this % xs(t) % total + &
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atom_density * nuc % xs(nuc_t) % total * interp
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this % xs(t) % absorption = this % xs(t) % absorption + &
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atom_density * nuc % xs(nuc_t) % absorption * interp
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if (nuc % fissionable) then
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this % xs(t) % chi = this % xs(t) % chi + &
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atom_density * nuc % xs(nuc_t) % chi * interp
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this % xs(t) % nu_fission = this % xs(t) % nu_fission + &
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atom_density * nuc % xs(nuc_t) % nu_fission * interp
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if (allocated(nuc % xs(nuc_t) % fission)) then
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this % xs(t) % fission = this % xs(t) % fission + &
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atom_density * nuc % xs(nuc_t) % fission * interp
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end if
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end do
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end do
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if (allocated(nuc % xs(nuc_t) % k_fission)) then
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this % xs(t) % k_fission = this % xs(t) % k_fission + &
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atom_density * nuc % xs(nuc_t) % k_fission * interp
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end if
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end if
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! Get the complete scattering matrix
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nuc_order_dim = size(nuc % xs(nuc_t) % scatter % dist(1) % data, dim=1)
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nuc_order_dim = min(nuc_order_dim, order_dim)
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call nuc % xs(nuc_t) % scatter % get_matrix(nuc_order_dim, &
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nuc_matrix)
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do gin = 1, groups
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do gout = nuc % xs(nuc_t) % scatter % gmin(gin), &
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nuc % xs(nuc_t) % scatter % gmax(gin)
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scatt_coeffs(1:nuc_order_dim, gout, gin) = &
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scatt_coeffs(1: nuc_order_dim, gout, gin) + &
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atom_density * nuc_matrix(gin) % data(1:nuc_order_dim, gout)
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! We will next gather the multiplicaity and scattering matrices.
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! To avoid multiple re-allocations as we resize the storage
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! matrix (and/or to avoidlots of duplicate code), we will use a
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! dense matrix for this storage, with a reduction to the sparse
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! format at the end.
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! Get the multiplicity matrix
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! To combine from nuclidic data we need to use the final relationship
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) /
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! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'}))
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! Developed as follows:
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! mult_{gg'} = nuScatt{g,g'} / Scatt{g,g'}
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) / sum(N_i*scatt_{i,g,g'})
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! mult_{gg'} = sum_i(N_i*nuscatt_{i,g,g'}) /
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! sum_i(N_i*(nuscatt_{i,g,g'} / mult_{i,g,g'}))
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! nuscatt_{i,g,g'} can be reconstructed from scatter % energy and
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! scatter % scattxs
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do gin = 1, groups
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do gout = nuc % xs(nuc_t) % scatter % gmin(gin), nuc % xs(nuc_t) % scatter % gmax(gin)
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nuscatt = nuc % xs(nuc_t) % scatter % scattxs(gin) * &
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nuc % xs(nuc_t) % scatter % energy(gin) % data(gout)
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mult_num(gout, gin) = mult_num(gout, gin) + atom_density * &
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nuscatt * interp
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if (nuc % xs(nuc_t) % scatter % mult(gin) % data(gout) > ZERO) then
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mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * &
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nuscatt / nuc % xs(nuc_t) % scatter % mult(gin) % data(gout) * &
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interp
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else
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! Avoid division by zero
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mult_denom(gout, gin) = mult_denom(gout,gin) + atom_density * &
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interp
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end if
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end do
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end do
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! Get the complete scattering matrix
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nuc_order_dim = size(nuc % xs(nuc_t) % scatter % dist(1) % data, dim=1)
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nuc_order_dim = min(nuc_order_dim, order_dim)
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call nuc % xs(nuc_t) % scatter % get_matrix(nuc_order_dim, &
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nuc_matrix)
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do gin = 1, groups
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do gout = nuc % xs(nuc_t) % scatter % gmin(gin), &
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nuc % xs(nuc_t) % scatter % gmax(gin)
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scatt_coeffs(1:nuc_order_dim, gout, gin) = &
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scatt_coeffs(1: nuc_order_dim, gout, gin) + &
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atom_density * interp * &
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nuc_matrix(gin) % data(1:nuc_order_dim, gout)
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end do
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end do
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end do
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@ -1396,7 +1457,8 @@ module mgxs_header
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real(8), allocatable :: temp_mult(:, :, :, :), mult_num(:, :, :, :)
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real(8), allocatable :: mult_denom(:, :, :, :), scatt_coeffs(:, :, :, :, :)
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integer :: nuc_t
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real(8) :: temp_actual, temp_desired
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integer, allocatable :: nuc_ts(:)
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real(8) :: temp_actual, temp_desired, interp
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integer :: scatter_type
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type(Jagged2D), allocatable :: nuc_matrix(:)
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integer, allocatable :: gmin(:), gmax(:)
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@ -1472,107 +1534,137 @@ module mgxs_header
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! Add contribution from each nuclide in material
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NUC_LOOP: do i = 1, mat % n_nuclides
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associate(nuc => nuclides(mat % nuclide(i)) % obj)
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select case (method)
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case (TEMPERATURE_NEAREST)
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! Determine actual temperatures to read
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temp_desired = temps % data(i)
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nuc_t = minloc(abs(nuc % kTs - temp_desired), dim=1)
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temp_actual = nuc % kTs(nuc_t)
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if (abs(temp_actual - temp_desired) >= tolerance) then
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call fatal_error("MGXS library does not contain cross sections &
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&for " // trim(this % name) // " at or near " // &
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trim(to_str(nint(temp_desired / K_BOLTZMANN))) // " K.")
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end if
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case (TEMPERATURE_INTERPOLATION)
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! TODO: Get bounding temperatures
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call fatal_error("Temperature interpolation not yet implemented")
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end select
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select case (method)
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case (TEMPERATURE_NEAREST)
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! Determine actual temperatures to read
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temp_desired = temps % data(i)
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allocate(nuc_ts(1))
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nuc_ts(1) = minloc(abs(nuc % kTs - temp_desired), dim=1)
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temp_actual = nuc % kTs(nuc_ts(1))
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if (abs(temp_actual - temp_desired) >= tolerance) then
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call fatal_error("MGXS library does not contain cross sections &
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&for " // trim(this % name) // " at or near " // &
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trim(to_str(nint(temp_desired / K_BOLTZMANN))) // " K.")
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end if
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case (TEMPERATURE_INTERPOLATION)
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! If temperature interpolation or multipole is selected, get a
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! list of bounding temperatures for each actual temperature
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! present in the model
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temp_desired = temps % data(i)
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allocate(nuc_ts(2))
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do j = 1, size(nuc % kTs) - 1
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if (nuc % kTs(j) <= temp_desired .and. &
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temp_desired < nuc % kTs(j + 1)) then
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nuc_ts(1) = j
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nuc_ts(2) = j + 1
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end if
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end do
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call fatal_error("Nuclear data library does not contain cross sections &
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&for " // trim(this % name) // " at temperatures that bound " // &
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trim(to_str(nint(temp_desired))) // " K.")
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end select
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! Copy atom density of nuclide in material
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atom_density = mat % atom_density(i)
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select type(nuc)
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type is (MgxsAngle)
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! Perform our operations which depend upon the type
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! Add contributions to total, absorption, and fission data (if necessary)
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this % xs(t) % total = this % xs(t) % total + &
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atom_density * nuc % xs(nuc_t) % total
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this % xs(t) % absorption = this % xs(t) % absorption + &
|
||||
atom_density * nuc % xs(nuc_t) % absorption
|
||||
if (nuc % fissionable) then
|
||||
this % xs(t) % chi = this % xs(t) % chi + &
|
||||
atom_density * nuc % xs(nuc_t) % chi
|
||||
this % xs(t) % nu_fission = this % xs(t) % nu_fission + &
|
||||
atom_density * nuc % xs(nuc_t) % nu_fission
|
||||
if (allocated(nuc % xs(nuc_t) % fission)) then
|
||||
this % xs(t) % fission = this % xs(t) % fission + &
|
||||
atom_density * nuc % xs(nuc_t) % fission
|
||||
do j = 1, size(nuc_ts)
|
||||
nuc_t = nuc_ts(j)
|
||||
if (size(nuc_ts) == 1) then
|
||||
interp = ONE
|
||||
else if (j == 1) then
|
||||
interp = (ONE - (temp_desired - nuc % kTs(nuc_ts(1))) / &
|
||||
(nuc % kTs(nuc_ts(2)) - nuc % kTs(nuc_ts(1))))
|
||||
else
|
||||
interp = ONE - interp
|
||||
end if
|
||||
if (allocated(nuc % xs(nuc_t) % k_fission)) then
|
||||
this % xs(t) % k_fission = this % xs(t) % k_fission + &
|
||||
atom_density * nuc % xs(nuc_t) % k_fission
|
||||
! Perform our operations which depend upon the type
|
||||
! Add contributions to total, absorption, and fission data
|
||||
! (if necessary)
|
||||
this % xs(t) % total = this % xs(t) % total + &
|
||||
atom_density * nuc % xs(nuc_t) % total * interp
|
||||
this % xs(t) % absorption = this % xs(t) % absorption + &
|
||||
atom_density * nuc % xs(nuc_t) % absorption * interp
|
||||
if (nuc % fissionable) then
|
||||
this % xs(t) % chi = this % xs(t) % chi + &
|
||||
atom_density * nuc % xs(nuc_t) % chi * interp
|
||||
this % xs(t) % nu_fission = this % xs(t) % nu_fission + &
|
||||
atom_density * nuc % xs(nuc_t) % nu_fission * interp
|
||||
if (allocated(nuc % xs(nuc_t) % fission)) then
|
||||
this % xs(t) % fission = this % xs(t) % fission + &
|
||||
atom_density * nuc % xs(nuc_t) % fission * interp
|
||||
end if
|
||||
if (allocated(nuc % xs(nuc_t) % k_fission)) then
|
||||
this % xs(t) % k_fission = this % xs(t) % k_fission + &
|
||||
atom_density * nuc % xs(nuc_t) % k_fission * interp
|
||||
end if
|
||||
end if
|
||||
end if
|
||||
|
||||
! We will next gather the multiplicaity and scattering matrices.
|
||||
! To avoid multiple re-allocations as we resize the storage
|
||||
! matrix (and/or to avoidlots of duplicate code), we will use a
|
||||
! dense matrix for this storage, with a reduction to the sparse
|
||||
! format at the end.
|
||||
! We will next gather the multiplicaity and scattering matrices.
|
||||
! To avoid multiple re-allocations as we resize the storage
|
||||
! matrix (and/or to avoidlots of duplicate code), we will use a
|
||||
! dense matrix for this storage, with a reduction to the sparse
|
||||
! format at the end.
|
||||
|
||||
! Get the multiplicity 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 % xs(nuc_t) % scatter(iazi, ipol) %obj % gmin(gin), &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmax(gin)
|
||||
nuscatt = nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % scattxs(gin) * &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % energy(gin) % data(gout)
|
||||
mult_num(gout, gin, iazi, ipol) = &
|
||||
mult_num(gout, gin, iazi, ipol) + atom_density * &
|
||||
nuscatt
|
||||
if (nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % mult(gin) % data(gout) > ZERO) then
|
||||
mult_denom(gout, gin, iazi, ipol) = &
|
||||
mult_denom(gout, gin, iazi, ipol) + atom_density * &
|
||||
nuscatt / &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % mult(gin) % data(gout)
|
||||
else
|
||||
! Avoid division by zero
|
||||
mult_denom(gout, gin, iazi, ipol) = &
|
||||
mult_denom(gout, gin, iazi, ipol) + atom_density
|
||||
end if
|
||||
! Get the multiplicity 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 % xs(nuc_t) % scatter(iazi, ipol) %obj % gmin(gin), &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmax(gin)
|
||||
nuscatt = nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % scattxs(gin) * &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % energy(gin) % data(gout)
|
||||
mult_num(gout, gin, iazi, ipol) = &
|
||||
mult_num(gout, gin, iazi, ipol) + atom_density * &
|
||||
nuscatt * interp
|
||||
if (nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % mult(gin) % data(gout) > ZERO) then
|
||||
mult_denom(gout, gin, iazi, ipol) = &
|
||||
mult_denom(gout, gin, iazi, ipol) + atom_density * &
|
||||
interp * nuscatt / &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % mult(gin) % data(gout)
|
||||
else
|
||||
! Avoid division by zero
|
||||
mult_denom(gout, gin, iazi, ipol) = &
|
||||
mult_denom(gout, gin, iazi, ipol) + atom_density * &
|
||||
interp
|
||||
end if
|
||||
end do
|
||||
end do
|
||||
end do
|
||||
|
||||
! Get the complete scattering matrix
|
||||
nuc_order_dim = &
|
||||
size(nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % &
|
||||
dist(1) % data, dim=1)
|
||||
nuc_order_dim = min(nuc_order_dim, order_dim)
|
||||
call nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % &
|
||||
get_matrix(nuc_order_dim, nuc_matrix)
|
||||
do gin = 1, groups
|
||||
do gout = &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmin(gin), &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmax(gin)
|
||||
scatt_coeffs(1:nuc_order_dim, gout, gin, iazi, ipol) = &
|
||||
scatt_coeffs(1: nuc_order_dim, gout, gin, iazi, ipol) + &
|
||||
atom_density * nuc_matrix(gin) % data(1:nuc_order_dim, gout)
|
||||
end do ! gout
|
||||
end do ! gin
|
||||
end do ! iazi
|
||||
end do ! ipol
|
||||
! Get the complete scattering matrix
|
||||
nuc_order_dim = &
|
||||
size(nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % &
|
||||
dist(1) % data, dim=1)
|
||||
nuc_order_dim = min(nuc_order_dim, order_dim)
|
||||
call nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % &
|
||||
get_matrix(nuc_order_dim, nuc_matrix)
|
||||
do gin = 1, groups
|
||||
do gout = &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmin(gin), &
|
||||
nuc % xs(nuc_t) % scatter(iazi, ipol) % obj % gmax(gin)
|
||||
scatt_coeffs(1:nuc_order_dim, gout, gin, iazi, ipol) = &
|
||||
scatt_coeffs(1: nuc_order_dim, gout, gin, iazi, ipol) + &
|
||||
atom_density * interp * &
|
||||
nuc_matrix(gin) % data(1:nuc_order_dim, gout)
|
||||
end do ! gout
|
||||
end do ! gin
|
||||
end do ! iazi
|
||||
end do ! ipol
|
||||
end do
|
||||
type is (MgxsIso)
|
||||
call fatal_error("Invalid passing of MgxsIso to MgxsAngle object")
|
||||
end select
|
||||
|
|
|
|||
|
|
@ -61,13 +61,13 @@
|
|||
3 10000 4 1 total 0.002752 0.000240
|
||||
4 10000 5 1 total 0.001231 0.000105
|
||||
5 10000 6 1 total 0.000512 0.000044
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
0 10000 1 1 total 0.000000 0.000000
|
||||
1 10000 2 1 total 0.032739 0.028454
|
||||
2 10000 3 1 total 0.120780 0.170809
|
||||
3 10000 4 1 total 0.302780 0.109110
|
||||
4 10000 5 1 total 0.000000 0.000000
|
||||
5 10000 6 1 total 0.000000 0.000000
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
0 10000 1 1 total 0.000000e+00 0.000000e+00
|
||||
1 10000 2 1 total 3.273900e-10 2.845437e-10
|
||||
2 10000 3 1 total 1.207800e-09 1.708087e-09
|
||||
3 10000 4 1 total 3.027800e-09 1.091095e-09
|
||||
4 10000 5 1 total 0.000000e+00 0.000000e+00
|
||||
5 10000 6 1 total 0.000000e+00 0.000000e+00
|
||||
material group in nuclide mean std. dev.
|
||||
0 10001 1 total 0.311594 0.013793
|
||||
material group in nuclide mean std. dev.
|
||||
|
|
|
|||
|
|
@ -61,10 +61,10 @@
|
|||
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 4 1 total 0.002727 0.000135
|
||||
4 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 5 1 total 0.001210 0.000058
|
||||
5 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 6 1 total 0.000504 0.000024
|
||||
avg(distribcell) delayedgroup group in nuclide mean std. dev.
|
||||
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.000000 0.000000
|
||||
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 2 1 total 0.032739 0.046300
|
||||
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 3 1 total 0.120780 0.170809
|
||||
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 4 1 total 0.000000 0.000000
|
||||
4 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 5 1 total 0.000000 0.000000
|
||||
5 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 6 1 total 2.853000 4.034751
|
||||
avg(distribcell) delayedgroup group in nuclide mean std. dev.
|
||||
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total 0.000000e+00 0.000000e+00
|
||||
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 2 1 total 3.273900e-10 4.629994e-10
|
||||
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 3 1 total 1.207800e-09 1.708087e-09
|
||||
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 4 1 total 0.000000e+00 0.000000e+00
|
||||
4 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 5 1 total 0.000000e+00 0.000000e+00
|
||||
5 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 6 1 total 2.853000e-08 4.034751e-08
|
||||
|
|
|
|||
|
|
@ -112,18 +112,18 @@ domain=10000 type=beta
|
|||
[ 1.82980497e-04 4.50738567e-04]
|
||||
[ 7.48899920e-05 1.88812772e-04]]
|
||||
domain=10000 type=decay-rate
|
||||
[[ 0. 0. ]
|
||||
[ 0. 0.032739]
|
||||
[ 0. 0.12078 ]
|
||||
[ 0. 0.30278 ]
|
||||
[ 0. 0. ]
|
||||
[ 0. 0. ]]
|
||||
[[ 0. 0. ]
|
||||
[ 0. 0.02845437]
|
||||
[ 0. 0.17080871]
|
||||
[ 0. 0.10910951]
|
||||
[ 0. 0. ]
|
||||
[ 0. 0. ]]
|
||||
[[ 0.00000000e+00 0.00000000e+00]
|
||||
[ 0.00000000e+00 3.27390000e-10]
|
||||
[ 0.00000000e+00 1.20780000e-09]
|
||||
[ 0.00000000e+00 3.02780000e-09]
|
||||
[ 0.00000000e+00 0.00000000e+00]
|
||||
[ 0.00000000e+00 0.00000000e+00]]
|
||||
[[ 0.00000000e+00 0.00000000e+00]
|
||||
[ 0.00000000e+00 2.84543737e-10]
|
||||
[ 0.00000000e+00 1.70808714e-09]
|
||||
[ 0.00000000e+00 1.09109511e-09]
|
||||
[ 0.00000000e+00 0.00000000e+00]
|
||||
[ 0.00000000e+00 0.00000000e+00]]
|
||||
domain=10001 type=total
|
||||
[ 0.31373767 0.3008214 ]
|
||||
[ 0.0155819 0.02805245]
|
||||
|
|
|
|||
|
|
@ -208,29 +208,29 @@
|
|||
21 2 2 1 4 1 total 0.002143 0.001028
|
||||
22 2 2 1 5 1 total 0.001026 0.000492
|
||||
23 2 2 1 6 1 total 0.000408 0.000196
|
||||
mesh 1 delayedgroup group in nuclide mean std. dev.
|
||||
x y z
|
||||
0 1 1 1 1 1 total 0.00000 0.000000
|
||||
1 1 1 1 2 1 total 0.00000 0.000000
|
||||
2 1 1 1 3 1 total 0.00000 0.000000
|
||||
3 1 1 1 4 1 total 0.30278 0.428196
|
||||
4 1 1 1 5 1 total 0.00000 0.000000
|
||||
5 1 1 1 6 1 total 0.00000 0.000000
|
||||
6 1 2 1 1 1 total 0.00000 0.000000
|
||||
7 1 2 1 2 1 total 0.00000 0.000000
|
||||
8 1 2 1 3 1 total 0.00000 0.000000
|
||||
9 1 2 1 4 1 total 0.00000 0.000000
|
||||
10 1 2 1 5 1 total 0.00000 0.000000
|
||||
11 1 2 1 6 1 total 0.00000 0.000000
|
||||
12 2 1 1 1 1 total 0.00000 0.000000
|
||||
13 2 1 1 2 1 total 0.00000 0.000000
|
||||
14 2 1 1 3 1 total 0.00000 0.000000
|
||||
15 2 1 1 4 1 total 0.00000 0.000000
|
||||
16 2 1 1 5 1 total 0.00000 0.000000
|
||||
17 2 1 1 6 1 total 0.00000 0.000000
|
||||
18 2 2 1 1 1 total 0.00000 0.000000
|
||||
19 2 2 1 2 1 total 0.00000 0.000000
|
||||
20 2 2 1 3 1 total 0.00000 0.000000
|
||||
21 2 2 1 4 1 total 0.00000 0.000000
|
||||
22 2 2 1 5 1 total 0.00000 0.000000
|
||||
23 2 2 1 6 1 total 0.00000 0.000000
|
||||
mesh 1 delayedgroup group in nuclide mean std. dev.
|
||||
x y z
|
||||
0 1 1 1 1 1 total 0.000000e+00 0.000000e+00
|
||||
1 1 1 1 2 1 total 0.000000e+00 0.000000e+00
|
||||
2 1 1 1 3 1 total 0.000000e+00 0.000000e+00
|
||||
3 1 1 1 4 1 total 3.027800e-09 4.281956e-09
|
||||
4 1 1 1 5 1 total 0.000000e+00 0.000000e+00
|
||||
5 1 1 1 6 1 total 0.000000e+00 0.000000e+00
|
||||
6 1 2 1 1 1 total 0.000000e+00 0.000000e+00
|
||||
7 1 2 1 2 1 total 0.000000e+00 0.000000e+00
|
||||
8 1 2 1 3 1 total 0.000000e+00 0.000000e+00
|
||||
9 1 2 1 4 1 total 0.000000e+00 0.000000e+00
|
||||
10 1 2 1 5 1 total 0.000000e+00 0.000000e+00
|
||||
11 1 2 1 6 1 total 0.000000e+00 0.000000e+00
|
||||
12 2 1 1 1 1 total 0.000000e+00 0.000000e+00
|
||||
13 2 1 1 2 1 total 0.000000e+00 0.000000e+00
|
||||
14 2 1 1 3 1 total 0.000000e+00 0.000000e+00
|
||||
15 2 1 1 4 1 total 0.000000e+00 0.000000e+00
|
||||
16 2 1 1 5 1 total 0.000000e+00 0.000000e+00
|
||||
17 2 1 1 6 1 total 0.000000e+00 0.000000e+00
|
||||
18 2 2 1 1 1 total 0.000000e+00 0.000000e+00
|
||||
19 2 2 1 2 1 total 0.000000e+00 0.000000e+00
|
||||
20 2 2 1 3 1 total 0.000000e+00 0.000000e+00
|
||||
21 2 2 1 4 1 total 0.000000e+00 0.000000e+00
|
||||
22 2 2 1 5 1 total 0.000000e+00 0.000000e+00
|
||||
23 2 2 1 6 1 total 0.000000e+00 0.000000e+00
|
||||
|
|
|
|||
|
|
@ -123,19 +123,19 @@
|
|||
6 10000 4 2 total 0.011426 0.001099
|
||||
8 10000 5 2 total 0.004684 0.000451
|
||||
10 10000 6 2 total 0.001962 0.000189
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.000000 0.000000
|
||||
3 10000 2 1 total 0.000000 0.000000
|
||||
5 10000 3 1 total 0.000000 0.000000
|
||||
7 10000 4 1 total 0.000000 0.000000
|
||||
9 10000 5 1 total 0.000000 0.000000
|
||||
11 10000 6 1 total 0.000000 0.000000
|
||||
0 10000 1 2 total 0.000000 0.000000
|
||||
2 10000 2 2 total 0.032739 0.028454
|
||||
4 10000 3 2 total 0.120780 0.170809
|
||||
6 10000 4 2 total 0.302780 0.109110
|
||||
8 10000 5 2 total 0.000000 0.000000
|
||||
10 10000 6 2 total 0.000000 0.000000
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.000000e+00 0.000000e+00
|
||||
3 10000 2 1 total 0.000000e+00 0.000000e+00
|
||||
5 10000 3 1 total 0.000000e+00 0.000000e+00
|
||||
7 10000 4 1 total 0.000000e+00 0.000000e+00
|
||||
9 10000 5 1 total 0.000000e+00 0.000000e+00
|
||||
11 10000 6 1 total 0.000000e+00 0.000000e+00
|
||||
0 10000 1 2 total 0.000000e+00 0.000000e+00
|
||||
2 10000 2 2 total 3.273900e-10 2.845437e-10
|
||||
4 10000 3 2 total 1.207800e-09 1.708087e-09
|
||||
6 10000 4 2 total 3.027800e-09 1.091095e-09
|
||||
8 10000 5 2 total 0.000000e+00 0.000000e+00
|
||||
10 10000 6 2 total 0.000000e+00 0.000000e+00
|
||||
material group in nuclide mean std. dev.
|
||||
1 10001 1 total 0.313738 0.015582
|
||||
0 10001 2 total 0.300821 0.028052
|
||||
|
|
|
|||
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Reference in a new issue