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

added routine to extract accumulated fission src, temporarily hacked in

Browse source
This commit is contained in:
Bryan Herman 2012-04-13 14:47:04 -07:00
parent 6c2063a210
commit 13baf60cf8
3 changed files with 76 additions and 9 deletions
Download patch file Download diff file Expand all files Collapse all files

61
src/cmfd_data.F90
View file

@ -81,6 +81,7 @@ contains
! set flux object and source distribution to all zeros
cmfd % flux = 0.0_8
cmfd % openmc_cycle_src = 0.0_8
cmfd % openmc_src = 0.0_8
! associate tallies and mesh
@ -113,6 +114,9 @@ contains
end if
end if
! extract accumulated fission source
if (ital == 1) call extract_accum_fsrc(i,j,k)
! loop around energy groups
OUTGROUP: do h = 1,ng
@ -168,7 +172,7 @@ contains
bins = 1
! set ijk as mesh indices
ijk = (/ i, j, k /)
ijk = (/ i, j, k /)
! get bin number for mesh indices
bins(FILTER_MESH) = mesh_indices_to_bin(m,ijk)
@ -176,7 +180,6 @@ contains
! apply energy in filter
bins(FILTER_ENERGYIN) = ng - h + 1
! set energy out bin
bins(FILTER_ENERGYOUT) = ng - g + 1
@ -192,7 +195,7 @@ contains
& cmfd % flux(h,i,j,k)
! bank source
cmfd % openmc_src(g,i,j,k) = cmfd % openmc_src(g,i,j,k) + &
cmfd % openmc_cycle_src(g,i,j,k) = cmfd % openmc_cycle_src(g,i,j,k) + &
& t % scores(score_index,2) % sum
end do INGROUP
@ -271,6 +274,7 @@ contains
! normalize openmc source distribution
cmfd % openmc_src = cmfd % openmc_src/sum(cmfd % openmc_src)*cmfd%norm
cmfd % openmc_cycle_src = cmfd % openmc_cycle_src/sum(cmfd % openmc_cycle_src)*cmfd%norm
end subroutine compute_xs
@ -703,4 +707,55 @@ contains
end subroutine fix_2_grp
!==============================================================================
! EXTRACT_ACCUM_FSRC
!==============================================================================
subroutine extract_accum_fsrc(i,j,k)
use global
use mesh, only: mesh_indices_to_bin
use mesh_header, only: StructuredMesh
use tally_header, only: TallyObject, TallyScore
integer :: nx ! number of mesh cells in x direction
integer :: ny ! number of mesh cells in y direction
integer :: nz ! number of mesh cells in z direction
integer :: ng ! number of energy groups
integer :: i ! iteration counter for x
integer :: j ! iteration counter for y
integer :: k ! iteration counter for z
integer :: g ! iteration counter for g
integer :: h ! iteration counter for outgoing groups
integer :: ital ! tally object index
integer :: ijk(3) ! indices for mesh cell
integer :: score_index ! index to pull from tally object
integer :: bins(N_FILTER_TYPES) ! bins for filters
real(8) :: flux ! temp variable for flux
type(TallyObject), pointer :: t ! pointer for tally object
type(StructuredMesh), pointer :: m ! pointer for mesh object
! associate tallies and mesh
t => tallies(1)
m => meshes(t % mesh)
! reset all bins to 1
bins = 1
! set ijk as mesh indices
ijk = (/ i, j, k /)
! get bin number for mesh indices
bins(FILTER_MESH) = mesh_indices_to_bin(m,ijk)
! calculate score index from bins
score_index = sum((bins - 1) * t%stride) + 1
! bank source
cmfd % openmc_src(i,j,k) = t % scores(score_index,1) % sum
end subroutine extract_accum_fsrc
end module cmfd_data

7
src/cmfd_header.F90
View file

@ -68,7 +68,8 @@ module cmfd_header
real(8) :: entropy = 0.0_8
! openmc source
real(8), allocatable :: openmc_src(:,:,:,:)
real(8), allocatable :: openmc_src(:,:,:)
real(8), allocatable :: openmc_cycle_src(:,:,:,:)
! openmc source normalization factor
real(8) :: norm = 1.0_8
@ -119,7 +120,8 @@ contains
if (.not. allocated(this % current)) allocate(this % current(12,ng,nx,ny,nz))
! allocate openmc source distribution
if (.not. allocated(this % openmc_src)) allocate(this % openmc_src(ng,nx,ny,nz))
if (.not. allocated(this % openmc_src)) allocate(this % openmc_src(nx,ny,nz))
if (.not. allocated(this % openmc_cycle_src)) allocate(this % openmc_cycle_src(ng,nx,ny,nz))
end subroutine allocate_cmfd
@ -151,6 +153,7 @@ contains
if (allocated(this % sourcecounts)) deallocate(this % sourcecounts)
if (allocated(this % weightfactors)) deallocate(this % weightfactors)
if (allocated(this % openmc_src)) deallocate(this % openmc_src)
if (allocated(this % openmc_cycle_src)) deallocate(this % openmc_cycle_src)
end subroutine deallocate_cmfd

17
src/cmfd_output.F90
View file

@ -130,7 +130,7 @@ contains
integer(HID_T) :: dataspace_id ! Data space identifier
integer(HID_T) :: dataset_id ! Dataset identifier
integer(HSIZE_T), dimension(1) :: dim1 ! vector for hdf5 dimensions
! integer(HSIZE_T), dimension(3) :: dim3 ! vector for hdf5 dimensions
integer(HSIZE_T), dimension(3) :: dim3 ! vector for hdf5 dimensions
integer(HSIZE_T), dimension(4) :: dim4 ! vector for hdf5 dimensions
integer(HSIZE_T), dimension(5) :: dim5 ! vector for hdf5 dimensions
@ -354,11 +354,20 @@ contains
call h5dclose_f(dataset_id,hdf5_err)
! write out openmc source vector
dim4 = (/ng,nx,ny,nz/)
call h5screate_simple_f(4,dim4,dataspace_id,hdf5_err)
dim3 = (/nx,ny,nz/)
call h5screate_simple_f(3,dim4,dataspace_id,hdf5_err)
call h5dcreate_f(hdf5_output_file,trim(cycname)//"/openmc_src", &
& H5T_NATIVE_DOUBLE,dataspace_id,dataset_id,hdf5_err)
call h5dwrite_f(dataset_id,H5T_NATIVE_DOUBLE,cmfd%openmc_src,dim4,hdf5_err)
call h5dwrite_f(dataset_id,H5T_NATIVE_DOUBLE,cmfd%openmc_src,dim3,hdf5_err)
call h5sclose_f(dataspace_id,hdf5_err)
call h5dclose_f(dataset_id,hdf5_err)
! write out openmc source vector
dim4 = (/ng,nx,ny,nz/)
call h5screate_simple_f(4,dim4,dataspace_id,hdf5_err)
call h5dcreate_f(hdf5_output_file,trim(cycname)//"/openmc_cycle_src", &
& H5T_NATIVE_DOUBLE,dataspace_id,dataset_id,hdf5_err)
call h5dwrite_f(dataset_id,H5T_NATIVE_DOUBLE,cmfd%openmc_cycle_src,dim4,hdf5_err)
call h5sclose_f(dataspace_id,hdf5_err)
call h5dclose_f(dataset_id,hdf5_err)