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Reduced calls to calculate_xs using last_material.

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This commit is contained in:
Paul Romano 2011-12-06 14:56:23 -05:00
parent 66ca324828
commit 8bf7b3f77e
2 changed files with 24 additions and 24 deletions
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1
src/geometry.f90
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@ -141,6 +141,7 @@ contains
! AT LOWEST UNIVERSE, TERMINATE SEARCH
! set material
p % last_material = p % material
p % material = c % material
elseif (c % type == CELL_FILL) then

47
src/physics.f90
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@ -37,7 +37,7 @@ contains
real(8) :: distance ! distance particle travels
logical :: found_cell ! found cell which particle is in?
logical :: lattice_crossed ! is surface crossing in lattice?
type(LocalCoord), pointer :: coord
type(LocalCoord), pointer :: coord => null()
if (p % coord % cell == NONE) then
call find_cell(p, found_cell)
@ -69,8 +69,11 @@ contains
! find energy index, interpolation factor
do while (p % alive)
! Calculate microscopic and macroscopic cross sections
call calculate_xs(p)
! Calculate microscopic and macroscopic cross sections -- note: if the
! material is the same as the last material and the energy of the
! particle hasn't changed, we don't need to lookup cross sections again.
if (p % material /= p % last_material) call calculate_xs(p)
! Find the distance to the nearest boundary
call distance_to_boundary(p, d_boundary, surface_crossed, lattice_crossed)
@ -106,6 +109,10 @@ contains
! Save coordinates at collision for tallying purposes
p % last_xyz = p % coord0 % xyz
! Set last material to none since cross sections will need to be
! re-evaluated
p % last_material = NONE
! Set all uvws to base level -- right now, after a collision, only the
! base level uvws are changed
coord => p % coord0
@ -137,18 +144,13 @@ contains
type(Particle), pointer :: p
integer :: i ! loop index over nuclides
integer :: index_nuclide ! index into nuclides array
integer :: index_sab
real(8) :: atom_density ! atom density of a nuclide
real(8) :: sab_threshold ! threshold for S(a,b) table
integer :: i ! loop index over nuclides
integer :: index_nuclide ! index into nuclides array
integer :: index_sab ! index into sab_tables array
real(8) :: atom_density ! atom density of a nuclide
real(8) :: sab_threshold ! threshold for S(a,b) table
type(Material), pointer :: mat => null() ! current material
! If the material is the same as the last material and the energy of the
! particle hasn't changed, we don't need to lookup cross sections again.
if (p % material == p % last_material) return
! Set all material macroscopic cross sections to zero
material_xs % total = ZERO
material_xs % elastic = ZERO
@ -223,14 +225,14 @@ contains
integer, intent(in) :: index_nuclide ! index into nuclides array
integer, intent(in) :: index_sab ! index into sab_tables array
integer :: i ! index into nuclides array
integer :: IE ! index on nuclide energy grid
integer :: IE_sab ! index on S(a,b) energy grid
real(8) :: f ! interp factor on nuclide energy grid
real(8) :: f_sab ! interp factor on S(a,b) energy grid
real(8) :: inelastic ! S(a,b) inelastic cross section
real(8) :: elastic ! S(a,b) elastic cross section
real(8) :: nu ! total # of neutrons emitted per fission
integer :: i ! index into nuclides array
integer :: IE ! index on nuclide energy grid
integer :: IE_sab ! index on S(a,b) energy grid
real(8) :: f ! interp factor on nuclide energy grid
real(8) :: f_sab ! interp factor on S(a,b) energy grid
real(8) :: inelastic ! S(a,b) inelastic cross section
real(8) :: elastic ! S(a,b) elastic cross section
real(8) :: nu ! total # of neutrons emitted per fission
type(Nuclide), pointer :: nuc => null()
type(SAB_Table), pointer :: sab => null()
@ -240,9 +242,6 @@ contains
! Set pointer to nuclide
nuc => nuclides(i)
! TODO: Check if last energy/temp combination is same as current. If so, we
! can return.
! TODO: If not using unionized energy grid, we need to find the index on the
! nuclide energy grid using lethargy mapping or whatever other technique