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Separate fission-q scoring into separate function

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In order to reduce the amount of duplicated code in building
the energy deposition tally, the logic for scoring SCORE_FISS_Q_PROMPT
and SCORE_FISS_Q_RECOV has been pulled into a new function,
score_fission_q. The code is almost entirely copied over, with some
minor cleanup operations.
This commit is contained in:
Andrew Johnson 2019-08-30 15:29:00 -05:00
parent 99bff4f231
commit f2e14dc6be
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GPG key ID: 253418E91B7F6FEB
1 changed files with 52 additions and 45 deletions
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97
src/tallies/tally_scoring.cpp
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@ -187,6 +187,56 @@ double get_nuc_fission_q(const Nuclide& nuc, const Particle* p, int score_bin)
return 0.0;
}
double score_fission_q(const Particle* p, int score_bin, const Tally& tally,
double flux, int i_nuclide, double atom_density)
{
if (tally.estimator_ == ESTIMATOR_ANALOG) {
const Nuclide& nuc {*data::nuclides[p->event_nuclide_]};
if (settings::survival_biasing) {
// No fission events occur if survival biasing is on -- need to
// calculate fraction of absorptions that would have resulted in
// fission scaled by the Q-value
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
return p->wgt_absorb_ * get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[p->event_nuclide_].fission * flux
/ p->neutron_xs_[p->event_nuclide_].absorption;
}
} else {
// Skip any non-absorption events
if (p->event_ == EVENT_SCATTER) return 0.0;
// All fission events will contribute, so again we can use particle's
// weight entering the collision as the estimate for the fission
// reaction rate
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
return p->wgt_last_ * get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[p->event_nuclide_].fission * flux
/ p->neutron_xs_[p->event_nuclide_].absorption;
}
}
} else {
if (i_nuclide >= 0) {
const Nuclide& nuc {*data::nuclides[i_nuclide]};
return get_nuc_fission_q(nuc, p, score_bin) * atom_density * flux
* p->neutron_xs_[i_nuclide].fission;
} else {
if (p->material_ != MATERIAL_VOID) {
const Material& material {*model::materials[p->material_]};
double score {0.0};
for (auto i = 0; i < material.nuclide_.size(); ++i) {
auto j_nuclide = material.nuclide_[i];
auto atom_density = material.atom_density_(i);
const Nuclide& nuc {*data::nuclides[j_nuclide]};
score += get_nuc_fission_q(nuc, p, score_bin) * atom_density
* p->neutron_xs_[j_nuclide].fission;
}
return score * flux;
}
}
}
return 0.0;
}
//! Helper function for nu-fission tallies with energyout filters.
//
//! In this case, we may need to score to multiple bins if there were multiple
@ -339,7 +389,7 @@ void
score_general_ce(Particle* p, int i_tally, int start_index,
int filter_index, int i_nuclide, double atom_density, double flux)
{
auto& tally {*model::tallies[i_tally]};
Tally& tally {*model::tallies[i_tally]};
// Get the pre-collision energy of the particle.
auto E = p->E_last_;
@ -1048,51 +1098,8 @@ score_general_ce(Particle* p, int i_tally, int start_index,
case SCORE_FISS_Q_PROMPT:
case SCORE_FISS_Q_RECOV:
//continue;
if (p->macro_xs_.absorption == 0.) continue;
score = 0.;
if (tally.estimator_ == ESTIMATOR_ANALOG) {
if (settings::survival_biasing) {
// No fission events occur if survival biasing is on -- need to
// calculate fraction of absorptions that would have resulted in
// fission scaled by the Q-value
const Nuclide& nuc {*data::nuclides[p->event_nuclide_]};
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
score = p->wgt_absorb_ * get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[p->event_nuclide_].fission
/ p->neutron_xs_[p->event_nuclide_].absorption * flux;
}
} else {
// Skip any non-absorption events
if (p->event_ == EVENT_SCATTER) continue;
// All fission events will contribute, so again we can use particle's
// weight entering the collision as the estimate for the fission
// reaction rate
const Nuclide& nuc {*data::nuclides[p->event_nuclide_]};
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
score = p->wgt_last_ * get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[p->event_nuclide_].fission
/ p->neutron_xs_[p->event_nuclide_].absorption * flux;
}
}
} else {
if (i_nuclide >= 0) {
const Nuclide& nuc {*data::nuclides[i_nuclide]};
score = get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[i_nuclide].fission * 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 j_nuclide = material.nuclide_[i];
auto atom_density = material.atom_density_(i);
const Nuclide& nuc {*data::nuclides[j_nuclide]};
score += get_nuc_fission_q(nuc, p, score_bin)
* p->neutron_xs_[j_nuclide].fission * atom_density * flux;
}
}
}
}
score = score_fission_q(p, score_bin, tally, flux, i_nuclide, atom_density);
break;