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Respond to @smharper comments on #1183
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4 changed files with 5 additions and 4 deletions
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@ -312,7 +312,7 @@ read_ce_cross_sections(const std::vector<std::vector<double>>& nuc_temps,
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}
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} // thermal_tables_
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// Finish setting up.material_s (normalizing densities, etc.)
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// Finish setting up materials (normalizing densities, etc.)
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mat->finalize();
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} // materials
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@ -221,7 +221,7 @@ void load_dagmc_geometry()
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c->material_.push_back(MATERIAL_VOID);
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} else {
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if (using_uwuw) {
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// lookup.material_ in uwuw if the were present
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// lookup material in uwuw if the were present
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std::string uwuw_mat = DMD.volume_material_property_data_eh[vol_handle];
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if (uwuw.material_library.count(uwuw_mat) != 0) {
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// Note: material numbers are set by UWUW
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@ -73,7 +73,7 @@ int openmc_simulation_init()
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t->init_results();
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}
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// Set up.material_ nuclide index mapping
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// Set up material nuclide index mapping
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for (auto& mat : model::materials) {
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mat->init_nuclide_index();
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}
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@ -157,10 +157,11 @@ Particle::Bank SourceDistribution::sample() const
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// Sample spatial distribution
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site.r = space_->sample();
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double xyz[] {site.r.x, site.r.y, site.r.z};
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// Now search to see if location exists in geometry
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int32_t cell_index, instance;
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int err = openmc_find_cell(&site.r.x, &cell_index, &instance);
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int err = openmc_find_cell(xyz, &cell_index, &instance);
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found = (err != OPENMC_E_GEOMETRY);
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// Check if spatial site is in fissionable material
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