From c571a4b12629699250f8c19c3a95f6ba2b15c6eb Mon Sep 17 00:00:00 2001 From: Adam Nelson Date: Sat, 7 Nov 2015 14:23:20 -0500 Subject: [PATCH] Got cmfd working, not sure about with feedback just yet --- examples/xml/multigroup/c5g7/2d/cmfd.xml | 6 +++--- examples/xml/multigroup/c5g7/2d/settings.xml | 4 ++-- src/tally.F90 | 15 ++++++++++++--- 3 files changed, 17 insertions(+), 8 deletions(-) diff --git a/examples/xml/multigroup/c5g7/2d/cmfd.xml b/examples/xml/multigroup/c5g7/2d/cmfd.xml index 22b1e9042..1b1e523b1 100644 --- a/examples/xml/multigroup/c5g7/2d/cmfd.xml +++ b/examples/xml/multigroup/c5g7/2d/cmfd.xml @@ -1,9 +1,9 @@ - 1 - true - jfnk + 2 + false + power 0.0 0.0 -100.0 64.26 64.26 100.0 diff --git a/examples/xml/multigroup/c5g7/2d/settings.xml b/examples/xml/multigroup/c5g7/2d/settings.xml index 189adc6c9..faed7cd7f 100644 --- a/examples/xml/multigroup/c5g7/2d/settings.xml +++ b/examples/xml/multigroup/c5g7/2d/settings.xml @@ -33,7 +33,7 @@ - 2000 + 2500 true @@ -43,7 +43,7 @@ true - false + true ../data.xml diff --git a/src/tally.F90 b/src/tally.F90 index 7ad701b16..6b3e7a793 100644 --- a/src/tally.F90 +++ b/src/tally.F90 @@ -966,8 +966,11 @@ contains ! For scattering production, we need to use the pre-collision ! weight times the multiplicity as the estimate for the number of ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = p % wgt + if (i_nuclide > 0) then + score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & p % last_uvw, p % mu) + end if case (SCORE_NU_SCATTER_PN) @@ -980,8 +983,11 @@ contains ! For scattering production, we need to use the pre-collision ! weight times the multiplicity as the estimate for the number of ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = p % wgt + if (i_nuclide > 0) then + score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & p % last_uvw, p % mu) + end if case (SCORE_NU_SCATTER_YN) @@ -994,8 +1000,11 @@ contains ! For scattering production, we need to use the pre-collision ! weight times the multiplicity as the estimate for the number of ! neutrons exiting a reaction with neutrons in the exit channel - score = p % wgt * nuc % get_xs(p % g, 'f_mu', p % last_g, & + score = p % wgt + if (i_nuclide > 0) then + score = score * nuc % get_xs(p % g, 'f_mu', p % last_g, & p % last_uvw, p % mu) + end if case (SCORE_TRANSPORT)