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made similar line changes to MG physics as @paulromano made to regular physics file.

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This commit is contained in:
John Tramm 2020-01-15 23:03:20 +00:00
parent c60a7e569f
commit 48b8055ae8
3 changed files with 18 additions and 32 deletions
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4
examples/xml/pincell/settings.xml
View file

@ -3,9 +3,9 @@
<!-- Define how many particles to run and for how many batches -->
<run_mode>eigenvalue</run_mode>
<batches>100</batches>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<particles>100000</particles>
<!-- The starting source is a uniform distribution over the entire pin
cell. Note that since this is effectively a 2D model, the z coordinates

17
src/physics.cpp
View file

@ -176,9 +176,7 @@ create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx)
// Determine whether to place fission sites into the shared fission bank
// or the secondary particle bank.
bool use_fission_bank = false;
if (settings::run_mode == RUN_MODE_EIGENVALUE)
use_fission_bank = true;
bool use_fission_bank = (settings::run_mode == RUN_MODE_EIGENVALUE)
for (int i = 0; i < nu; ++i) {
Particle::Bank* site;
@ -197,9 +195,7 @@ create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx)
break;
}
site = simulation::fission_bank + idx;
}
else
{
} else {
// Create new bank site and get reference to last element
auto& bank = p->secondary_bank_;
bank.emplace_back();
@ -224,12 +220,11 @@ create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx)
// Write fission particles to nuBank
if(use_fission_bank)
{
Particle::NuBank* nu_bank_entry;
p->nu_bank_.emplace_back();
nu_bank_entry = &p->nu_bank_.back();
nu_bank_entry->wgt = site->wgt;
nu_bank_entry->E = site->E;
nu_bank_entry->delayed_group = site->delayed_group;
Particle::NuBank* nu_bank_entry = &p->nu_bank_.back();
nu_bank_entry->wgt = site->wgt;
nu_bank_entry->E = site->E;
nu_bank_entry->delayed_group = site->delayed_group;
}
}

29
src/physics_mg.cpp
View file

@ -122,19 +122,15 @@ create_fission_sites(Particle* p)
// Determine whether to place fission sites into the shared fission bank
// or the secondary particle bank.
bool use_fission_bank = false;
if (settings::run_mode == RUN_MODE_EIGENVALUE)
use_fission_bank = true;
bool use_fission_bank = (settings::run_mode == RUN_MODE_EIGENVALUE)
for (int i = 0; i < nu; ++i) {
Particle::Bank* site;
if(use_fission_bank)
{
if (use_fission_bank) {
int64_t idx;
#pragma omp atomic capture
idx = simulation::fission_bank_length++;
if( idx >= simulation::fission_bank_max )
{
if (idx >= simulation::fission_bank_max) {
warning("The shared fission bank is full. Additional fission sites created "
"in this generation will not be banked.");
#pragma omp atomic write
@ -143,9 +139,7 @@ create_fission_sites(Particle* p)
break;
}
site = simulation::fission_bank + idx;
}
else
{
} else {
// Create new bank site and get reference to last element
auto& bank = p->secondary_bank_;
bank.emplace_back();
@ -188,21 +182,18 @@ create_fission_sites(Particle* p)
}
// Write fission particles to nuBank
if(use_fission_bank)
{
Particle::NuBank* nu_bank_entry;
if (use_fission_bank) {
p->nu_bank_.emplace_back();
nu_bank_entry = &p->nu_bank_.back();
nu_bank_entry->wgt = site->wgt;
nu_bank_entry->E = site->E;
nu_bank_entry->delayed_group = site->delayed_group;
Particle::NuBank* nu_bank_entry = &p->nu_bank_.back();
nu_bank_entry->wgt = site->wgt;
nu_bank_entry->E = site->E;
nu_bank_entry->delayed_group = site->delayed_group;
}
}
// If shared fission bank was full, and no fissions could be added,
// set the particle fission flag to false.
if( nu == skipped )
{
if (nu == skipped) {
p->fission_ = false;
return;
}