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Fix MG mode bugs for inverse-vel and decay tallies

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This commit is contained in:
Sterling Harper 2019-02-07 23:48:54 -05:00
parent 3ff2410dfa
commit 66e2d1f63c
2 changed files with 5 additions and 5 deletions
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8
src/tallies/tally.F90
View file

@ -1349,11 +1349,11 @@ contains
if (i_nuclide > 0) then
score = score * flux * get_nuclide_xs_c(i_nuclide, &
MG_GET_XS_INVERSE_VELOCITY, p_g) / &
get_macro_xs_c(p % material, MG_GET_XS_ABSORPTION, p_g)
get_macro_xs_c(p % material, MG_GET_XS_TOTAL, p_g)
else
score = score * flux * get_macro_xs_c(p % material, &
MG_GET_XS_INVERSE_VELOCITY, p_g) / &
get_macro_xs_c(p % material, MG_GET_XS_ABSORPTION, p_g)
get_macro_xs_c(p % material, MG_GET_XS_TOTAL, p_g)
end if
else
@ -1843,13 +1843,13 @@ contains
if (i_nuclide > 0) then
score = score + keff * atom_density * &
fission_bank_wgt(n_bank - p % n_bank + k) * &
get_nuclide_xs_c(i_nuclide, MG_GET_XS_DECAY_RATE, p_g, DG=d) * &
get_nuclide_xs_c(i_nuclide, MG_GET_XS_DECAY_RATE, p_g, DG=g) * &
get_nuclide_xs_c(i_nuclide, MG_GET_XS_FISSION, p_g) / &
get_macro_xs_c(p % material, MG_GET_XS_FISSION, p_g) * flux
else
score = score + keff * &
fission_bank_wgt(n_bank - p % n_bank + k) * &
get_macro_xs_c(p % material, MG_GET_XS_DECAY_RATE, p_g, DG=d) * flux
get_macro_xs_c(p % material, MG_GET_XS_DECAY_RATE, p_g, DG=g) * flux
end if
! if the delayed group filter is present, tally to corresponding

2
src/xsdata.cpp
View file

@ -92,7 +92,7 @@ XsData::from_hdf5(hid_t xsdata_grp, bool fissionable, int scatter_format,
fission_from_hdf5(xsdata_grp, n_ang, is_isotropic);
}
// Get the non-fission-specific data
read_nd_vector(xsdata_grp, "decay_rate", decay_rate);
read_nd_vector(xsdata_grp, "decay rate", decay_rate);
read_nd_vector(xsdata_grp, "absorption", absorption, true);
read_nd_vector(xsdata_grp, "inverse-velocity", inverse_velocity);