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added analog heating tally for non-neutron particles

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liangjg 2019-04-04 15:26:05 -04:00
parent a034fb2e76
commit c91aa58e8e
1 changed files with 14 additions and 15 deletions
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29
src/tallies/tally_scoring.cpp
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@ -1151,7 +1151,6 @@ score_general_ce(Particle* p, int i_tally, int start_index,
case SCORE_HEATING:
if (p->type_ == Particle::Type::neutron) {
score_bin = NEUTRON_HEATING;
if (tally.estimator_ == ESTIMATOR_ANALOG) {
// Calculate material heating cross section
double macro_heating = 0.;
@ -1160,7 +1159,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
auto j_nuclide = material.nuclide_[i];
auto atom_density = material.atom_density_(i);
const auto& nuc {*data::nuclides[j_nuclide]};
auto m = nuc.reaction_index_[score_bin];
auto m = nuc.reaction_index_[NEUTRON_HEATING];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = p->neutron_xs_[j_nuclide].index_temp;
@ -1188,7 +1187,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
score = 0.;
if (i_nuclide >= 0) {
const auto& nuc {*data::nuclides[i_nuclide]};
auto m = nuc.reaction_index_[score_bin];
auto m = nuc.reaction_index_[NEUTRON_HEATING];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = p->neutron_xs_[i_nuclide].index_temp;
@ -1208,7 +1207,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
auto j_nuclide = material.nuclide_[i];
auto atom_density = material.atom_density_(i);
const auto& nuc {*data::nuclides[j_nuclide]};
auto m = nuc.reaction_index_[score_bin];
auto m = nuc.reaction_index_[NEUTRON_HEATING];
if (m == C_NONE) continue;
const auto& rxn {*nuc.reactions_[m]};
auto i_temp = p->neutron_xs_[j_nuclide].index_temp;
@ -1226,18 +1225,19 @@ score_general_ce(Particle* p, int i_tally, int start_index,
}
}
}
} else if (p->type_ == Particle::Type::photon) {
} else {
if (tally.estimator_ == ESTIMATOR_ANALOG) {
// Use photon energy lost for heating deposition
if (settings::survival_biasing) {
// We need to account for the fact that some weight was already
// absorbed
score = p->wgt_last_ + p->wgt_absorb_;
} else {
score = p->wgt_last_;
// Score direct energy deposition in the collision
score = E - p->E_;
// We need to substract the energy of the secondary particles since
// they will be transported individually later
for (auto i = 0; i < p->n_bank_second_; ++i) {
auto i_bank = simulation::secondary_bank.size() - p->n_bank_second_ + i;
const auto& bank = simulation::secondary_bank[i_bank];
score -= bank.E;
}
score *= (E - p->E_) * flux;
} else {
score *= p->wgt_last_ * flux;
} else if (p->type_ == Particle::Type::photon) {
// Calculate photon heating cross section on-the-fly
score = 0.;
if (i_nuclide >= 0) {
@ -1267,7 +1267,6 @@ score_general_ce(Particle* p, int i_tally, int start_index,
}
}
}
// Nuclear heating of any other particles not implmented
break;
default: