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fixed neutron balance routine
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parent
fec5a1a9b5
commit
3576a53140
2 changed files with 7 additions and 7 deletions
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@ -126,7 +126,7 @@ contains
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XLOOP: do i = 1,nx
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INGROUP: do h = 1,ng
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OUTGROUP: do h = 1,ng
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! begin with first tally
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t => tallies(1)
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@ -167,7 +167,7 @@ contains
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& cmfd % p1scattxs(h,i,j,k)))
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! begin loop to get energy out tallies
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OUTGROUP: do g = 1,ng
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INGROUP: do g = 1,ng
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! associate tally pointer to energy out tally object
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t => tallies(2)
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@ -183,8 +183,8 @@ contains
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! get nu-fission
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cmfd % nfissxs(h,g,i,j,k) = t % scores(score_index,2) % val / flux
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print *,h,g,i,j,k,t % scores(score_index,2) % val
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end do OUTGROUP
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end do INGROUP
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! extract surface currents
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t => tallies(3)
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@ -247,7 +247,7 @@ contains
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score_index = sum((bins - 1) * t % stride) + 1 ! outgoing
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cmfd % current(12,h,i,j,k) = t % scores(score_index,1) % val
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end do INGROUP
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end do OUTGROUP
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end do XLOOP
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@ -384,10 +384,10 @@ contains
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GROUPH: do h = 1,ng
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scattering = scattering + cmfd % scattxs(h,g,i,j,k) * &
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& cmfd % flux(g,i,j,k)
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& cmfd % flux(h,i,j,k)
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fission = fission + cmfd % nfissxs(h,g,i,j,k) * &
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& cmfd % flux(g,i,j,k)
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& cmfd % flux(h,i,j,k)
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end do GROUPH
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