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Removed recalculate attribute from NuclideMicroXS.

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This commit is contained in:
Paul Romano 2012-01-04 19:45:31 -05:00
parent ac1927fa03
commit 8483b3fc2a
3 changed files with 3 additions and 17 deletions
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1
src/ace_header.F90
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@ -197,7 +197,6 @@ module ace_header
! Information for URR probability table use
logical :: use_ptable ! in URR range with probability tables?
logical :: recalculate ! indicate whether we need to recalculate ptables
end type NuclideMicroXS
!===============================================================================

12
src/cross_section.F90
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@ -168,11 +168,9 @@ contains
! probability tables, we need to determine cross sections from the table
if (urr_ptables_on .and. nuc % urr_present) then
if (micro_xs(index_nuclide) % recalculate) then
if (p % E > nuc % urr_data % energy(1) .and. &
p % E < nuc % urr_data % energy(nuc % urr_data % n_energy)) then
call calculate_urr_xs(p, index_nuclide)
end if
if (p % E > nuc % urr_data % energy(1) .and. &
p % E < nuc % urr_data % energy(nuc % urr_data % n_energy)) then
call calculate_urr_xs(p, index_nuclide)
end if
end if
@ -365,10 +363,6 @@ contains
micro_xs(index_nuclide) % fission
end if
! As long as the energy of the neutron doesn't change, we don't need to
! recalculate probability table data
micro_xs(index_nuclide) % recalculate = .false.
end subroutine calculate_urr_xs
!===============================================================================

7
src/physics.F90
View file

@ -66,9 +66,6 @@ contains
! Initialize number of events to zero
n_event = 0
! Set recalculate ptables to true by default
micro_xs(:) % recalculate = .true.
! find energy index, interpolation factor
do while (p % alive)
@ -200,10 +197,6 @@ contains
! Reset number of particles banked during collision
p % n_bank = 0
! Since a collision has occurred, we need to recalculate probability tables
! for any nuclide
micro_xs(:) % recalculate = .true.
end subroutine collision
!===============================================================================