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Aesthetic changes. Rename sum_xs, rename SUM_XS -> XS constants
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Paul Romano
parent
ac29b7c719
commit
d2d1703e76
2 changed files with 37 additions and 38 deletions
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@ -233,7 +233,7 @@ contains
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if (f > prn()) i_temp = i_temp + 1
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end select
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associate (grid => nuc % grid(i_temp), xs => nuc % sum_xs(i_temp))
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associate (grid => nuc % grid(i_temp), xs => nuc % xs(i_temp))
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! Determine the energy grid index using a logarithmic mapping to
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! reduce the energy range over which a binary search needs to be
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! performed
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@ -266,29 +266,29 @@ contains
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micro_xs(i_nuclide) % interp_factor = f
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! Calculate microscopic nuclide total cross section
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micro_xs(i_nuclide) % total = (ONE - f) * xs % value(SUM_XS_TOTAL,i_grid) &
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+ f * xs % value(SUM_XS_TOTAL,i_grid + 1)
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micro_xs(i_nuclide) % total = (ONE - f) * xs % value(XS_TOTAL,i_grid) &
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+ f * xs % value(XS_TOTAL,i_grid + 1)
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! Calculate microscopic nuclide elastic cross section
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micro_xs(i_nuclide) % elastic = (ONE - f) * xs % value(SUM_XS_ELASTIC,i_grid) &
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+ f * xs % value(SUM_XS_ELASTIC,i_grid + 1)
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micro_xs(i_nuclide) % elastic = (ONE - f) * xs % value(XS_ELASTIC,i_grid) &
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+ f * xs % value(XS_ELASTIC,i_grid + 1)
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if (nuc % fissionable) then
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! Calculate microscopic nuclide total cross section
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micro_xs(i_nuclide) % fission = (ONE - f) * xs % value(SUM_XS_FISSION,i_grid) &
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+ f * xs % value(SUM_XS_FISSION,i_grid + 1)
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micro_xs(i_nuclide) % fission = (ONE - f) * xs % value(XS_FISSION,i_grid) &
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+ f * xs % value(XS_FISSION,i_grid + 1)
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! Calculate microscopic nuclide nu-fission cross section
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micro_xs(i_nuclide) % nu_fission = (ONE - f) * xs % value(SUM_XS_NU_FISSION, &
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i_grid) + f * xs % value(SUM_XS_NU_FISSION,i_grid + 1)
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micro_xs(i_nuclide) % nu_fission = (ONE - f) * xs % value(XS_NU_FISSION, &
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i_grid) + f * xs % value(XS_NU_FISSION,i_grid + 1)
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else
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micro_xs(i_nuclide) % fission = ZERO
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micro_xs(i_nuclide) % nu_fission = ZERO
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end if
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! Calculate microscopic nuclide absorption cross section
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micro_xs(i_nuclide) % absorption = (ONE - f) * xs % value(SUM_XS_ABSORPTION, &
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i_grid) + f * xs % value(SUM_XS_ABSORPTION,i_grid + 1)
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micro_xs(i_nuclide) % absorption = (ONE - f) * xs % value(XS_ABSORPTION, &
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i_grid) + f * xs % value(XS_ABSORPTION,i_grid + 1)
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end associate
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! Depletion-related reactions
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@ -36,22 +36,20 @@ module nuclide_header
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real(8), allocatable :: energy(:) ! energy values corresponding to xs
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end type EnergyGrid
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! Positions for first dimension of Nuclide % xs
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integer, parameter :: &
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SUM_XS_TOTAL = 1, &
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SUM_XS_ELASTIC = 2, &
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SUM_XS_FISSION = 3, &
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SUM_XS_NU_FISSION = 4, &
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SUM_XS_ABSORPTION = 5, &
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SUM_XS_HEATING = 6
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XS_TOTAL = 1, &
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XS_ELASTIC = 2, &
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XS_FISSION = 3, &
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XS_NU_FISSION = 4, &
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XS_ABSORPTION = 5, &
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XS_HEATING = 6
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! The array within SumXS is of shape (6, n_energy) where the first dimension
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! corresponds to the following values: 1) total, 2) elastic scattering, 3)
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! fission, 4) neutron production, 5) absorption (MT > 100), 6) heating
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type SumXS
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real(8), allocatable :: value(:,:)
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!!$ real(8), allocatable :: total(:) ! total cross section
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!!$ real(8), allocatable :: elastic(:) ! elastic scattering
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!!$ real(8), allocatable :: fission(:) ! fission
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!!$ real(8), allocatable :: nu_fission(:) ! neutron production
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!!$ real(8), allocatable :: absorption(:) ! absorption (MT > 100)
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!!$ real(8), allocatable :: heating(:) ! heating
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end type SumXS
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type :: Nuclide
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@ -70,7 +68,7 @@ module nuclide_header
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type(EnergyGrid), allocatable :: grid(:)
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! Microscopic cross sections
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type(SumXS), allocatable :: sum_xs(:)
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type(SumXS), allocatable :: xs(:)
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! Resonance scattering info
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logical :: resonant = .false. ! resonant scatterer?
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@ -575,13 +573,13 @@ contains
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type(VectorInt) :: MTs
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n_temperature = size(this % kTs)
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allocate(this % sum_xs(n_temperature))
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allocate(this % xs(n_temperature))
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this % reaction_index(:) = 0
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do i = 1, n_temperature
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! Allocate and initialize derived cross sections
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n_grid = size(this % grid(i) % energy)
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allocate(this % sum_xs(i) % value(6,n_grid))
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this % sum_xs(i) % value(:,:) = ZERO
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allocate(this % xs(i) % value(6,n_grid))
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this % xs(i) % value(:,:) = ZERO
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end do
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i_fission = 0
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@ -609,17 +607,17 @@ contains
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n = size(rx % xs(t) % value)
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! Copy elastic
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if (rx % MT == ELASTIC) this % sum_xs(t) % value(SUM_XS_ELASTIC,:) = &
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if (rx % MT == ELASTIC) this % xs(t) % value(XS_ELASTIC,:) = &
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rx % xs(t) % value
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! Add contribution to total cross section
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this % sum_xs(t) % value(SUM_XS_TOTAL,j:j+n-1) = this % sum_xs(t) % &
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value(SUM_XS_TOTAL,j:j+n-1) + rx % xs(t) % value
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this % xs(t) % value(XS_TOTAL,j:j+n-1) = this % xs(t) % &
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value(XS_TOTAL,j:j+n-1) + rx % xs(t) % value
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! Add contribution to absorption cross section
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if (is_disappearance(rx % MT)) then
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this % sum_xs(t) % value(SUM_XS_ABSORPTION,j:j+n-1) = this % sum_xs(t) % &
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value(SUM_XS_ABSORPTION,j:j+n-1) + rx % xs(t) % value
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this % xs(t) % value(XS_ABSORPTION,j:j+n-1) = this % xs(t) % &
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value(XS_ABSORPTION,j:j+n-1) + rx % xs(t) % value
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end if
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! Information about fission reactions
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@ -635,12 +633,12 @@ contains
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! Add contribution to fission cross section
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if (is_fission(rx % MT)) then
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this % fissionable = .true.
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this % sum_xs(t) % value(SUM_XS_FISSION,j:j+n-1) = this % sum_xs(t) % &
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value(SUM_XS_FISSION,j:j+n-1) + rx % xs(t) % value
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this % xs(t) % value(XS_FISSION,j:j+n-1) = this % xs(t) % &
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value(XS_FISSION,j:j+n-1) + rx % xs(t) % value
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! Also need to add fission cross sections to absorption
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this % sum_xs(t) % value(SUM_XS_ABSORPTION,j:j+n-1) = this % sum_xs(t) % &
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value(SUM_XS_ABSORPTION,j:j+n-1) + rx % xs(t) % value
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this % xs(t) % value(XS_ABSORPTION,j:j+n-1) = this % xs(t) % &
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value(XS_ABSORPTION,j:j+n-1) + rx % xs(t) % value
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! If total fission reaction is present, there's no need to store the
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! reaction cross-section since it was copied to this % fission
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@ -692,8 +690,9 @@ contains
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do t = 1, n_temperature
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if (this % fissionable) then
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do i = 1, n_grid
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this % sum_xs(t) % value(SUM_XS_NU_FISSION,i) = this % nu(this % grid(t) % energy(i), &
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EMISSION_TOTAL) * this % sum_xs(t) % value(SUM_XS_FISSION,i)
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this % xs(t) % value(XS_NU_FISSION,i) = &
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this % nu(this % grid(t) % energy(i), EMISSION_TOTAL) * &
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this % xs(t) % value(XS_FISSION,i)
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end do
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end if
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end do
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