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Move cross section caches to C++

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This commit is contained in:
Paul Romano 2019-02-19 22:43:28 -06:00
parent 34be2851b4
commit 16b2a657d6
11 changed files with 39 additions and 281 deletions
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18
src/simulation.cpp
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@ -10,6 +10,7 @@
#include "openmc/nuclide.h"
#include "openmc/output.h"
#include "openmc/particle.h"
#include "openmc/photon.h"
#include "openmc/random_lcg.h"
#include "openmc/settings.h"
#include "openmc/source.h"
@ -84,9 +85,12 @@ int openmc_simulation_init()
mat->init_nuclide_index();
}
// Call Fortran initialization
simulation_init_f();
set_micro_xs();
// Create cross section caches
#pragma omp parallel
{
simulation::micro_xs = new NuclideMicroXS[data::nuclides.size()];
simulation::micro_photon_xs = new ElementMicroXS[data::elements.size()];
}
// Reset global variables -- this is done before loading state point (as that
// will potentially populate k_generation and entropy)
@ -135,7 +139,13 @@ int openmc_simulation_finalize()
for (auto& mat : model::materials) {
mat->mat_nuclide_index_.clear();
}
simulation_finalize_f();
// Clear cross section caches
#pragma omp parallel
{
delete[] simulation::micro_xs;
delete[] simulation::micro_photon_xs;
}
// Increment total number of generations
simulation::total_gen += simulation::current_batch*settings::gen_per_batch;