Respond to @smharper comments on #1183

This commit is contained in:
Paul Romano 2019-03-05 07:05:33 -06:00
parent 3ad2caa0ac
commit 7382d35679
4 changed files with 5 additions and 4 deletions

View file

@ -312,7 +312,7 @@ read_ce_cross_sections(const std::vector<std::vector<double>>& nuc_temps,
}
} // thermal_tables_
// Finish setting up.material_s (normalizing densities, etc.)
// Finish setting up materials (normalizing densities, etc.)
mat->finalize();
} // materials

View file

@ -221,7 +221,7 @@ void load_dagmc_geometry()
c->material_.push_back(MATERIAL_VOID);
} else {
if (using_uwuw) {
// lookup.material_ in uwuw if the were present
// lookup material in uwuw if the were present
std::string uwuw_mat = DMD.volume_material_property_data_eh[vol_handle];
if (uwuw.material_library.count(uwuw_mat) != 0) {
// Note: material numbers are set by UWUW

View file

@ -73,7 +73,7 @@ int openmc_simulation_init()
t->init_results();
}
// Set up.material_ nuclide index mapping
// Set up material nuclide index mapping
for (auto& mat : model::materials) {
mat->init_nuclide_index();
}

View file

@ -157,10 +157,11 @@ Particle::Bank SourceDistribution::sample() const
// Sample spatial distribution
site.r = space_->sample();
double xyz[] {site.r.x, site.r.y, site.r.z};
// Now search to see if location exists in geometry
int32_t cell_index, instance;
int err = openmc_find_cell(&site.r.x, &cell_index, &instance);
int err = openmc_find_cell(xyz, &cell_index, &instance);
found = (err != OPENMC_E_GEOMETRY);
// Check if spatial site is in fissionable material