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update tally_scoring

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liangjg 2019-03-26 13:06:22 -04:00
parent cdde6b55b3
commit cfb11882a7
1 changed files with 11 additions and 11 deletions
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22
src/tallies/tally_scoring.cpp
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@ -1163,10 +1163,10 @@ score_general_ce(Particle* p, int i_tally, int start_index,
auto m = nuc.reaction_index_[score_bin];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = simulation::micro_xs[j_nuclide].index_temp;
auto i_temp = p->neutron_xs_[j_nuclide].index_temp;
if (i_temp >= 0) { // Can be false due to multipole
auto i_grid = simulation::micro_xs[j_nuclide].index_grid;
auto f = simulation::micro_xs[j_nuclide].interp_factor;
auto i_grid = p->neutron_xs_[j_nuclide].index_grid;
auto f = p->neutron_xs_[j_nuclide].interp_factor;
const auto& xs {rxn.xs_[i_temp]};
if (i_grid >= xs.threshold) {
macro_heating += ((1.0 - f) * xs.value[i_grid-xs.threshold]
@ -1182,7 +1182,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
} else {
score = p->wgt_last_;
}
score *= macro_heating * flux / simulation::material_xs.total;
score *= macro_heating * flux / p->macro_xs_.total;
} else {
// Calculate neutron heating cross section on-the-fly
score = 0.;
@ -1191,10 +1191,10 @@ score_general_ce(Particle* p, int i_tally, int start_index,
auto m = nuc.reaction_index_[score_bin];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = simulation::micro_xs[i_nuclide].index_temp;
auto i_temp = p->neutron_xs_[i_nuclide].index_temp;
if (i_temp >= 0) { // Can be false due to multipole
auto i_grid = simulation::micro_xs[i_nuclide].index_grid;
auto f = simulation::micro_xs[i_nuclide].interp_factor;
auto i_grid = p->neutron_xs_[i_nuclide].index_grid;
auto f = p->neutron_xs_[i_nuclide].interp_factor;
const auto& xs {rxn.xs_[i_temp]};
if (i_grid >= xs.threshold) {
score = ((1.0 - f) * xs.value[i_grid-xs.threshold]
@ -1211,10 +1211,10 @@ score_general_ce(Particle* p, int i_tally, int start_index,
auto m = nuc.reaction_index_[score_bin];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = simulation::micro_xs[j_nuclide].index_temp;
auto i_temp = p->neutron_xs_[j_nuclide].index_temp;
if (i_temp >= 0) { // Can be false due to multipole
auto i_grid = simulation::micro_xs[j_nuclide].index_grid;
auto f = simulation::micro_xs[j_nuclide].interp_factor;
auto i_grid = p->neutron_xs_[j_nuclide].index_grid;
auto f = p->neutron_xs_[j_nuclide].interp_factor;
const auto& xs {rxn.xs_[i_temp]};
if (i_grid >= xs.threshold) {
score += ((1.0 - f) * xs.value[i_grid-xs.threshold]
@ -1248,7 +1248,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
} else {
score = p->wgt_last_;
}
score *= macro_heating * flux / simulation::material_xs.total;
score *= macro_heating * flux / p->macro_xs_.total;
} else {
// Calculate photon heating cross section on-the-fly
score = 0.;