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Use helper function when scoring fission_q_*

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Add a brief helper function get_nuc_fission_q in
src/tallies/tally_scoring.cpp that is responsible for
returning the correct fission q value for a given
score. The two allowed scores are SCORE_FISS_Q_PROMPT and
SCORE_FISS_Q_RECOV. The helper function examines the correct
dataset on the nuclide object and evaluates the function given
the incident particle energy or returns zero.
The default value of zero is returned if the fission_q_prompt_ or
fission_q_recov_ datasets are empty, or the score is not
one of the expected types.
This commit is contained in:
Andrew Johnson 2019-08-30 14:22:59 -05:00
parent d4782d5719
commit 99bff4f231
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1 changed files with 26 additions and 42 deletions
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68
src/tallies/tally_scoring.cpp
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@ -171,6 +171,22 @@ score_fission_delayed_dg(int i_tally, int d_bin, double score, int score_index)
dg_match.bins_[i_bin] = original_bin;
}
//! Helper function to retrieve fission q value from a nuclide
double get_nuc_fission_q(const Nuclide& nuc, const Particle* p, int score_bin)
{
if (score_bin == SCORE_FISS_Q_PROMPT) {
if (nuc.fission_q_prompt_) {
return (*nuc.fission_q_prompt_)(p->E_last_);
}
} else if (score_bin == SCORE_FISS_Q_RECOV) {
if (nuc.fission_q_recov_) {
return (*nuc.fission_q_recov_)(p->E_last_);
}
}
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
@ -1040,17 +1056,9 @@ score_general_ce(Particle* p, int i_tally, int start_index,
// 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 auto& nuc {*data::nuclides[p->event_nuclide_]};
const Nuclide& nuc {*data::nuclides[p->event_nuclide_]};
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
double q_value = 0.;
if (score_bin == SCORE_FISS_Q_PROMPT) {
if (nuc.fission_q_prompt_)
q_value = (*nuc.fission_q_prompt_)(p->E_last_);
} else if (score_bin == SCORE_FISS_Q_RECOV) {
if (nuc.fission_q_recov_)
q_value = (*nuc.fission_q_recov_)(p->E_last_);
}
score = p->wgt_absorb_ * q_value
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;
}
@ -1060,51 +1068,27 @@ score_general_ce(Particle* p, int i_tally, int start_index,
// 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 auto& nuc {*data::nuclides[p->event_nuclide_]};
const Nuclide& nuc {*data::nuclides[p->event_nuclide_]};
if (p->neutron_xs_[p->event_nuclide_].absorption > 0) {
double q_value = 0.;
if (score_bin == SCORE_FISS_Q_PROMPT) {
if (nuc.fission_q_prompt_)
q_value = (*nuc.fission_q_prompt_)(p->E_last_);
} else if (score_bin == SCORE_FISS_Q_RECOV) {
if (nuc.fission_q_recov_)
q_value = (*nuc.fission_q_recov_)(p->E_last_);
}
score = p->wgt_last_ * q_value
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 auto& nuc {*data::nuclides[i_nuclide]};
double q_value = 0.;
if (score_bin == SCORE_FISS_Q_PROMPT) {
if (nuc.fission_q_prompt_)
q_value = (*nuc.fission_q_prompt_)(p->E_last_);
} else if (score_bin == SCORE_FISS_Q_RECOV) {
if (nuc.fission_q_recov_)
q_value = (*nuc.fission_q_recov_)(p->E_last_);
}
score = q_value * p->neutron_xs_[i_nuclide].fission
* atom_density * flux;
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 auto& nuc {*data::nuclides[j_nuclide]};
double q_value = 0.;
if (score_bin == SCORE_FISS_Q_PROMPT) {
if (nuc.fission_q_prompt_)
q_value = (*nuc.fission_q_prompt_)(p->E_last_);
} else if (score_bin == SCORE_FISS_Q_RECOV) {
if (nuc.fission_q_recov_)
q_value = (*nuc.fission_q_recov_)(p->E_last_);
}
score += q_value * p->neutron_xs_[j_nuclide].fission
* atom_density * flux;
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;
}
}
}