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Fixed up comments in collision subroutine.

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This commit is contained in:
Paul Romano 2011-09-30 20:17:15 -04:00
parent c9b2967c64
commit ff045a5049
1 changed files with 25 additions and 18 deletions
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43
src/physics.f90
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@ -274,16 +274,15 @@ contains
type(Particle), pointer :: p
integer :: i ! index over nuclides in a material
integer :: index_nuclide
integer :: IE ! index on nuclide energy grid
real(8) :: f ! interpolation factor
real(8) :: sigma ! microscopic total xs for nuclide
real(8) :: total ! total macroscopic xs for material
real(8) :: prob ! cumulative probability
real(8) :: cutoff ! random number
real(8) :: atom_density ! atom density of nuclide in atom/b-cm
logical :: scatter ! was this a scattering reaction?
integer :: i ! index over nuclides in a material
integer :: index_nuclide ! index in nuclides array
integer :: IE ! index on nuclide energy grid
real(8) :: f ! interpolation factor
real(8) :: sigma ! microscopic total xs for nuclide
real(8) :: prob ! cumulative probability
real(8) :: cutoff ! random number
real(8) :: atom_density ! atom density of nuclide in atom/b-cm
logical :: scatter ! was this a scattering reaction?
character(MAX_LINE_LEN) :: msg ! output/error message
type(Material), pointer :: mat
type(Nuclide), pointer :: nuc
@ -302,10 +301,11 @@ contains
! Get pointer to current material
mat => materials(p % material)
! sample nuclide
! ==========================================================================
! SAMPLE NUCLIDE WITHIN THE MATERIAL
i = 0
total = material_xs % total
cutoff = rang() * total
cutoff = rang() * material_xs % total
prob = ZERO
do while (prob < cutoff)
i = i + 1
@ -325,7 +325,9 @@ contains
IE = micro_xs(index_nuclide) % index_grid
f = micro_xs(index_nuclide) % interp_factor
! sample reaction channel
! ==========================================================================
! SAMPLE REACTION WITHIN THE NUCLIDE
cutoff = rang() * sigma / atom_density
prob = ZERO
do i = 1, nuc % n_reaction
@ -351,14 +353,16 @@ contains
call message(msg)
end if
! call appropriate subroutine
! ==========================================================================
! PERFORM APPROPRIATE COLLISION PHYSICS
select case (rxn % MT)
case (ELASTIC)
call elastic_scatter(p, nuc, rxn)
scatter = .true.
case (N_NA, N_N3A, N_NP, N_N2A, N_ND, N_NT, N_N3HE, N_NT2A, N_N2P, &
N_NPA, N_N1 : N_NC, N_2ND, N_2N, N_3N, N_2NA, N_3NA, N_2N2A, &
N_4N, N_2NP, N_3NP)
N_4N, N_2NP, N_3NP, MISC)
call inelastic_scatter(p, nuc, rxn)
scatter = .true.
case (N_FISSION, N_F, N_NF, N_2NF, N_3NF)
@ -377,8 +381,11 @@ contains
! call warning(msg)
end if
! Score collision estimator tallies for any macro tallies -- we can do this
! before sampling the nuclide since
! Score collision estimator tallies for any macro tallies -- this is done
! after a collision has occurred rather than before because we need
! information on the outgoing energy for any tallies with an outgoing energy
! filter
if (tallies_on) then
call score_tally(p, scatter)
end if