fixed neutron balance routine

This commit is contained in:
Bryan Herman 2011-12-23 10:48:18 -08:00
parent fec5a1a9b5
commit 3576a53140
2 changed files with 7 additions and 7 deletions

View file

@ -126,7 +126,7 @@ contains
XLOOP: do i = 1,nx
INGROUP: do h = 1,ng
OUTGROUP: do h = 1,ng
! begin with first tally
t => tallies(1)
@ -167,7 +167,7 @@ contains
& cmfd % p1scattxs(h,i,j,k)))
! begin loop to get energy out tallies
OUTGROUP: do g = 1,ng
INGROUP: do g = 1,ng
! associate tally pointer to energy out tally object
t => tallies(2)
@ -183,8 +183,8 @@ contains
! get nu-fission
cmfd % nfissxs(h,g,i,j,k) = t % scores(score_index,2) % val / flux
print *,h,g,i,j,k,t % scores(score_index,2) % val
end do OUTGROUP
end do INGROUP
! extract surface currents
t => tallies(3)
@ -247,7 +247,7 @@ contains
score_index = sum((bins - 1) * t % stride) + 1 ! outgoing
cmfd % current(12,h,i,j,k) = t % scores(score_index,1) % val
end do INGROUP
end do OUTGROUP
end do XLOOP

View file

@ -384,10 +384,10 @@ contains
GROUPH: do h = 1,ng
scattering = scattering + cmfd % scattxs(h,g,i,j,k) * &
& cmfd % flux(g,i,j,k)
& cmfd % flux(h,i,j,k)
fission = fission + cmfd % nfissxs(h,g,i,j,k) * &
& cmfd % flux(g,i,j,k)
& cmfd % flux(h,i,j,k)
end do GROUPH