crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Merge pull request #220 from walshjon/sab_recalc

Browse source 
Prevent unnecessary S(a,b) recalculations
This commit is contained in:
Paul Romano 2013-11-14 18:05:40 -08:00
commit 35cec7dd24
2 changed files with 7 additions and 9 deletions
Download patch file Download diff file Expand all files Collapse all files

5
src/ace_header.F90
View file

@ -214,8 +214,9 @@ module ace_header
real(8) :: kappa_fission ! microscopic energy-released from fission
! Information for S(a,b) use
integer :: index_sab ! index in sab_tables (zero means no table)
real(8) :: elastic_sab ! microscopic elastic scattering on S(a,b) table
integer :: index_sab ! index in sab_tables (zero means no table)
integer :: last_index_sab = 0 ! index in sab_tables last used by this nuclide
real(8) :: elastic_sab ! microscopic elastic scattering on S(a,b) table
! Information for URR probability table use
logical :: use_ptable ! in URR range with probability tables?

11
src/cross_section.F90
View file

@ -93,6 +93,8 @@ contains
! Calculate microscopic cross section for this nuclide
if (p % E /= micro_xs(i_nuclide) % last_E) then
call calculate_nuclide_xs(i_nuclide, i_sab, p % E)
else if (i_sab /= micro_xs(i_nuclide) % last_index_sab) then
call calculate_nuclide_xs(i_nuclide, i_sab, p % E)
end if
! ========================================================================
@ -235,13 +237,8 @@ contains
end if
end if
! Set last evaluated energy -- if we're in S(a,b) region, force
! re-calculation of cross-section
if (i_sab == 0) then
micro_xs(i_nuclide) % last_E = E
else
micro_xs(i_nuclide) % last_E = ZERO
end if
micro_xs(i_nuclide) % last_E = E
micro_xs(i_nuclide) % last_index_sab = i_sab
end subroutine calculate_nuclide_xs