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photon heating tally with analog estimator works now

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This commit is contained in:
liangjg 2019-04-05 22:18:22 -04:00
parent ec49c32a61
commit f4541ab1c8
1 changed files with 32 additions and 29 deletions
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61
src/tallies/tally_scoring.cpp
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@ -1150,6 +1150,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
case SCORE_HEATING:
score = 0.;
if (p->type_ == Particle::Type::neutron) {
if (tally.estimator_ == ESTIMATOR_ANALOG) {
// Calculate material heating cross section
@ -1184,7 +1185,6 @@ score_general_ce(Particle* p, int i_tally, int start_index,
score *= macro_heating * flux / p->macro_xs_.total;
} else {
// Calculate neutron heating cross section on-the-fly
score = 0.;
if (i_nuclide >= 0) {
const auto& nuc {*data::nuclides[i_nuclide]};
auto m = nuc.reaction_index_[NEUTRON_HEATING];
@ -1225,7 +1225,7 @@ score_general_ce(Particle* p, int i_tally, int start_index,
}
}
}
} else {
} else if (p->type_ == Particle::Type::photon) {
if (tally.estimator_ == ESTIMATOR_ANALOG) {
// Score direct energy deposition in the collision
score = E - p->E_;
@ -1234,36 +1234,39 @@ score_general_ce(Particle* p, int i_tally, int start_index,
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;
if (bank.particle == Particle::Type::photon ||
bank.particle == Particle::Type::neutron) {
score -= bank.E;
} else if (bank.particle == Particle::Type::positron) {
// Annihilation of the positron will produce two new photons
score -= 2*MASS_ELECTRON_EV;
}
}
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) {
// Find the element corresponding to the nuclide
auto name = data::nuclides[i_nuclide]->name_;
int pos = name.find_first_of("0123456789");
std::string element = name.substr(0, pos);
int i_element = data::element_map[element];
auto& heating {data::elements[i_element].heating_};
auto i_grid = p->photon_xs_[i_element].index_grid;
auto f = p->photon_xs_[i_element].interp_factor;
score = std::exp(heating(i_grid) + f * (heating(i_grid+1) -
heating(i_grid))) * atom_density * flux;
} else {
if (p->material_ != MATERIAL_VOID) {
const Material& material {*model::materials[p->material_]};
for (auto i = 0; i < material.nuclide_.size(); ++i) {
auto i_element = material.element_[i];
auto atom_density = material.atom_density_(i);
auto& heating {data::elements[i_element].heating_};
auto i_grid = p->photon_xs_[i_element].index_grid;
auto f = p->photon_xs_[i_element].interp_factor;
score += std::exp(heating(i_grid) + f * (heating(i_grid+1) -
heating(i_grid))) * atom_density * flux;
}
// Calculate photon heating cross section on-the-fly
if (i_nuclide >= 0) {
// Find the element corresponding to the nuclide
auto name = data::nuclides[i_nuclide]->name_;
int pos = name.find_first_of("0123456789");
std::string element = name.substr(0, pos);
int i_element = data::element_map[element];
auto& heating {data::elements[i_element].heating_};
auto i_grid = p->photon_xs_[i_element].index_grid;
auto f = p->photon_xs_[i_element].interp_factor;
score = std::exp(heating(i_grid) + f * (heating(i_grid+1) -
heating(i_grid))) * atom_density * flux;
} else {
if (p->material_ != MATERIAL_VOID) {
const Material& material {*model::materials[p->material_]};
for (auto i = 0; i < material.nuclide_.size(); ++i) {
auto i_element = material.element_[i];
auto atom_density = material.atom_density_(i);
auto& heating {data::elements[i_element].heating_};
auto i_grid = p->photon_xs_[i_element].index_grid;
auto f = p->photon_xs_[i_element].interp_factor;
score += std::exp(heating(i_grid) + f * (heating(i_grid+1) -
heating(i_grid))) * atom_density * flux;
}
}
}