added user-defined fission source normalization constant

This commit is contained in:
Bryan Herman 2012-03-02 13:56:04 -08:00
parent 935c3bffa4
commit 73fd4449df
5 changed files with 17 additions and 5 deletions

View file

@ -266,7 +266,7 @@ contains
end do TAL
! normalize openmc source distribution
cmfd % openmc_src = cmfd % openmc_src/sum(cmfd % openmc_src)
cmfd % openmc_src = cmfd % openmc_src/sum(cmfd % openmc_src)*cmfd%norm
end subroutine compute_xs

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@ -191,6 +191,7 @@ contains
integer :: idx ! index in vector
real(8) :: hxyz(3) ! cell dimensions of current ijk cell
real(8) :: vol ! volume of cell
real(8) :: norm ! normalization factor for entropy
real(8),allocatable :: source(:,:,:,:) ! tmp source array for entropy
! get maximum of spatial and group indices
@ -235,12 +236,15 @@ contains
end do ZLOOP
! normalize source such that it sums to 1.0
cmfd%source = cmfd%source/sum(cmfd%source)
! normalize source such that it sums to 1.0 (1 group for now)
cmfd%source = cmfd%source/sum(cmfd%source)*cmfd%norm
! compute entropy
if (entropy_on) then
! compute normalization factor
norm = sum(cmfd%source)
! allocate tmp array
if (.not.allocated(source)) allocate(source(ng,nx,ny,nz))
@ -249,7 +253,7 @@ contains
! compute log
where (cmfd%source > 0.0_8)
source = cmfd%source*log(cmfd%source)/log(2.0)
source = cmfd%source/norm*log(cmfd%source/norm)/log(2.0)
end where
! sum that source

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@ -66,6 +66,9 @@ module cmfd_header
! openmc source
real(8), allocatable :: openmc_src(:,:,:,:)
! openmc source normalization factor
real(8) :: norm = 1.0_8
end type cmfd_obj
contains

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@ -69,9 +69,13 @@ contains
end if
! check for core map activation by printing note
if (cmfd_coremap .and. master) write(*,*)"Core Map Overlay Activated"
! check for normalization constant
if (norm_ > 0.0_8) then
cmfd % norm = norm_
end if
! create tally objects
call create_cmfd_tally()

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@ -13,5 +13,6 @@
</typedef>
<variable name="mesh_" tag="mesh" type="mesh_xml" />
<variable name="norm_" tag="norm" type="double" />
</template>