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fixed issue with fixed source problems, where fission neutrons were getting banked to fission bank instead of secondary bank.

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This commit is contained in:
John Tramm 2019-12-13 18:05:58 +00:00
parent f01db6d3d3
commit f5e2c12681
2 changed files with 21 additions and 9 deletions
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2
include/openmc/physics.h
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@ -49,7 +49,7 @@ int sample_nuclide(Particle* p);
//! Determine the average total, prompt, and delayed neutrons produced from
//! fission and creates appropriate bank sites.
void create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx,
std::vector<Particle::Bank>& bank);
std::vector<Particle::Bank>& bank, bool use_fission_bank);
int sample_element(Particle* p);

28
src/physics.cpp
View file

@ -95,11 +95,13 @@ void sample_neutron_reaction(Particle* p)
if (nuc->fissionable_) {
Reaction* rx = sample_fission(i_nuclide, p);
if (settings::run_mode == RUN_MODE_EIGENVALUE) {
create_fission_sites(p, i_nuclide, rx, simulation::fission_bank);
//create_fission_sites(p, i_nuclide, rx, simulation::fission_bank);
create_fission_sites(p, i_nuclide, rx, simulation::fission_bank, true);
} else if (settings::run_mode == RUN_MODE_FIXEDSOURCE &&
settings::create_fission_neutrons) {
//create_fission_sites(p, i_nuclide, rx, simulation::secondary_bank);
create_fission_sites(p, i_nuclide, rx, p->secondary_bank_);
//create_fission_sites(p, i_nuclide, rx, p->secondary_bank_);
create_fission_sites(p, i_nuclide, rx, p->secondary_bank_, false);
// Make sure particle population doesn't grow out of control for
// subcritical multiplication problems.
@ -149,7 +151,7 @@ void sample_neutron_reaction(Particle* p)
void
create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx,
std::vector<Particle::Bank>& bank)
std::vector<Particle::Bank>& bank, bool use_fission_bank)
{
// If uniform fission source weighting is turned on, we increase or decrease
// the expected number of fission sites produced
@ -173,11 +175,21 @@ create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx,
p->fission_ = true;
for (int i = 0; i < nu; ++i) {
// Create new bank site and get reference to last element
int idx;
#pragma omp atomic capture
idx = shared_fission_bank_length++;
Particle::Bank * site = shared_fission_bank + idx;
Particle::Bank * site;
if(use_fission_bank)
{
// Create new bank site and get reference to last element
int idx;
#pragma omp atomic capture
idx = shared_fission_bank_length++;
Particle::Bank * site = shared_fission_bank + idx;
}
else
{
// Create new bank site and get reference to last element
bank.emplace_back();
site = &bank.back();
}
site->r = p->r();
site->particle = Particle::Type::neutron;
site->wgt = 1. / weight;