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Support cell densities in the random ray solver (#3720)
This commit is contained in:
Kevin Sawatzky
GitHub
parent
7106958e00
commit
5bce5adabc
12 changed files with 648 additions and 30 deletions
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@ -14,6 +14,7 @@
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#include "openmc/memory.h" // for unique_ptr
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#include "openmc/ncrystal_interface.h"
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#include "openmc/particle.h"
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#include "openmc/settings.h"
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#include "openmc/vector.h"
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namespace openmc {
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@ -110,9 +111,12 @@ public:
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//! \return Density in [atom/b-cm]
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double density() const { return density_; }
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//! Get density in [g/cm^3]
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//! Get density in [g/cm^3].
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//! \return Density in [g/cm^3]
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double density_gpcc() const { return density_gpcc_; }
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double density_gpcc() const
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{
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return settings::run_CE ? density_gpcc_ : density();
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}
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//! Get charge density in [e/b-cm]
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//! \return Charge density in [e/b-cm]
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@ -146,6 +146,7 @@ public:
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// Scalar fields
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int* material_;
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double* density_mult_;
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int* is_small_;
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int* n_hits_;
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int* birthday_;
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@ -195,6 +196,9 @@ public:
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int& material() { return *material_; }
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const int material() const { return *material_; }
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double& density_mult() { return *density_mult_; }
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const double density_mult() const { return *density_mult_; }
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int& is_small() { return *is_small_; }
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const int is_small() const { return *is_small_; }
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@ -316,7 +320,9 @@ public:
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//---------------------------------------
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// Scalar fields
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int material_ {0}; //!< Index in openmc::model::materials array
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int material_ {0}; //!< Index in openmc::model::materials array
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double density_mult_ {1.0}; //!< A density multiplier queried from the cell
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//!< corresponding to the source region.
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OpenMPMutex lock_;
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double volume_ {
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0.0}; //!< Volume (computed from the sum of ray crossing lengths)
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@ -394,6 +400,9 @@ public:
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int& material(int64_t sr) { return material_[sr]; }
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const int material(int64_t sr) const { return material_[sr]; }
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double& density_mult(int64_t sr) { return density_mult_[sr]; }
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const double density_mult(int64_t sr) const { return density_mult_[sr]; }
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int& is_small(int64_t sr) { return is_small_[sr]; }
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const int is_small(int64_t sr) const { return is_small_[sr]; }
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@ -625,6 +634,7 @@ private:
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// SoA storage for scalar fields (one item per source region)
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vector<int> material_;
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vector<double> density_mult_;
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vector<int> is_small_;
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vector<int> n_hits_;
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vector<int> mesh_;
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@ -109,18 +109,21 @@ void FlatSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)
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// Add scattering + fission source
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int material = srh.material();
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double density_mult = srh.density_mult();
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if (material != MATERIAL_VOID) {
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double inverse_k_eff = 1.0 / k_eff_;
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for (int g_out = 0; g_out < negroups_; g_out++) {
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double sigma_t = sigma_t_[material * negroups_ + g_out];
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double sigma_t = sigma_t_[material * negroups_ + g_out] * density_mult;
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double scatter_source = 0.0;
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double fission_source = 0.0;
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for (int g_in = 0; g_in < negroups_; g_in++) {
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double scalar_flux = srh.scalar_flux_old(g_in);
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double sigma_s =
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sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];
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double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];
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double sigma_s = sigma_s_[material * negroups_ * negroups_ +
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g_out * negroups_ + g_in] *
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density_mult;
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double nu_sigma_f =
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nu_sigma_f_[material * negroups_ + g_in] * density_mult;
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double chi = chi_[material * negroups_ + g_out];
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scatter_source += sigma_s * scalar_flux;
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@ -198,7 +201,8 @@ void FlatSourceDomain::set_flux_to_flux_plus_source(
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source_regions_.volume_sq(sr);
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}
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} else {
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double sigma_t = sigma_t_[source_regions_.material(sr) * negroups_ + g];
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double sigma_t = sigma_t_[source_regions_.material(sr) * negroups_ + g] *
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source_regions_.density_mult(sr);
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source_regions_.scalar_flux_new(sr, g) /= (sigma_t * volume);
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source_regions_.scalar_flux_new(sr, g) += source_regions_.source(sr, g);
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}
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@ -332,7 +336,8 @@ void FlatSourceDomain::compute_k_eff()
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double sr_fission_source_new = 0;
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for (int g = 0; g < negroups_; g++) {
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double nu_sigma_f = nu_sigma_f_[material * negroups_ + g];
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double nu_sigma_f = nu_sigma_f_[material * negroups_ + g] *
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source_regions_.density_mult(sr);
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sr_fission_source_old +=
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nu_sigma_f * source_regions_.scalar_flux_old(sr, g);
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sr_fission_source_new +=
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@ -562,7 +567,8 @@ double FlatSourceDomain::compute_fixed_source_normalization_factor() const
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// to get the total source strength in the expected units.
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double sigma_t = 1.0;
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if (material != MATERIAL_VOID) {
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sigma_t = sigma_t_[material * negroups_ + g];
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sigma_t =
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sigma_t_[material * negroups_ + g] * source_regions_.density_mult(sr);
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}
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simulation_external_source_strength +=
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source_regions_.external_source(sr, g) * sigma_t * volume;
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@ -618,7 +624,9 @@ void FlatSourceDomain::random_ray_tally()
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// source strength.
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double volume = source_regions_.volume(sr) * simulation_volume_;
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double material = source_regions_.material(sr);
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int material = source_regions_.material(sr);
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double density_mult = source_regions_.density_mult(sr);
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for (int g = 0; g < negroups_; g++) {
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double flux =
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source_regions_.scalar_flux_new(sr, g) * source_normalization_factor;
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@ -634,19 +642,22 @@ void FlatSourceDomain::random_ray_tally()
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case SCORE_TOTAL:
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if (material != MATERIAL_VOID) {
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score = flux * volume * sigma_t_[material * negroups_ + g];
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score =
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flux * volume * sigma_t_[material * negroups_ + g] * density_mult;
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}
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break;
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case SCORE_FISSION:
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if (material != MATERIAL_VOID) {
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score = flux * volume * sigma_f_[material * negroups_ + g];
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score =
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flux * volume * sigma_f_[material * negroups_ + g] * density_mult;
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}
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break;
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case SCORE_NU_FISSION:
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if (material != MATERIAL_VOID) {
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score = flux * volume * nu_sigma_f_[material * negroups_ + g];
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score = flux * volume * nu_sigma_f_[material * negroups_ + g] *
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density_mult;
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}
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break;
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@ -913,7 +924,8 @@ void FlatSourceDomain::output_to_vtk() const
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for (int g = 0; g < negroups_; g++) {
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int64_t source_element = fsr * negroups_ + g;
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float flux = evaluate_flux_at_point(voxel_positions[i], fsr, g);
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double sigma_f = sigma_f_[mat * negroups_ + g];
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double sigma_f = sigma_f_[mat * negroups_ + g] *
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source_regions_.density_mult(fsr);
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total_fission += sigma_f * flux;
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}
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}
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@ -934,7 +946,8 @@ void FlatSourceDomain::output_to_vtk() const
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// multiply it back to get the true external source.
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double sigma_t = 1.0;
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if (mat != MATERIAL_VOID) {
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sigma_t = sigma_t_[mat * negroups_ + g];
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sigma_t = sigma_t_[mat * negroups_ + g] *
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source_regions_.density_mult(fsr);
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}
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total_external += source_regions_.external_source(fsr, g) * sigma_t;
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}
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@ -1244,7 +1257,8 @@ void FlatSourceDomain::set_adjoint_sources()
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continue;
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}
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for (int g = 0; g < negroups_; g++) {
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double sigma_t = sigma_t_[material * negroups_ + g];
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double sigma_t =
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sigma_t_[material * negroups_ + g] * source_regions_.density_mult(sr);
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source_regions_.external_source(sr, g) /= sigma_t;
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}
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}
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@ -1495,6 +1509,8 @@ SourceRegionHandle FlatSourceDomain::get_subdivided_source_region_handle(
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handle.material() = material;
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handle.density_mult() = cell.density_mult(gs.cell_instance());
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// Store the mesh index (if any) assigned to this source region
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handle.mesh() = mesh_idx;
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@ -1523,7 +1539,8 @@ SourceRegionHandle FlatSourceDomain::get_subdivided_source_region_handle(
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// Divide external source term by sigma_t
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if (material != C_NONE) {
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for (int g = 0; g < negroups_; g++) {
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double sigma_t = sigma_t_[material * negroups_ + g];
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double sigma_t =
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sigma_t_[material * negroups_ + g] * handle.density_mult();
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handle.external_source(g) /= sigma_t;
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}
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}
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@ -1598,6 +1615,7 @@ void FlatSourceDomain::apply_transport_stabilization()
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#pragma omp parallel for
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for (int64_t sr = 0; sr < n_source_regions(); sr++) {
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int material = source_regions_.material(sr);
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double density_mult = source_regions_.density_mult(sr);
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if (material == MATERIAL_VOID) {
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continue;
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}
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@ -1605,9 +1623,10 @@ void FlatSourceDomain::apply_transport_stabilization()
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// Only apply stabilization if the diagonal (in-group) scattering XS is
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// negative
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double sigma_s =
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sigma_s_[material * negroups_ * negroups_ + g * negroups_ + g];
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sigma_s_[material * negroups_ * negroups_ + g * negroups_ + g] *
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density_mult;
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if (sigma_s < 0.0) {
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double sigma_t = sigma_t_[material * negroups_ + g];
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double sigma_t = sigma_t_[material * negroups_ + g] * density_mult;
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double phi_new = source_regions_.scalar_flux_new(sr, g);
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double phi_old = source_regions_.scalar_flux_old(sr, g);
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@ -43,12 +43,13 @@ void LinearSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)
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// Add scattering + fission source
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int material = srh.material();
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double density_mult = srh.density_mult();
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if (material != MATERIAL_VOID) {
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double inverse_k_eff = 1.0 / k_eff_;
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MomentMatrix invM = srh.mom_matrix().inverse();
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for (int g_out = 0; g_out < negroups_; g_out++) {
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double sigma_t = sigma_t_[material * negroups_ + g_out];
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double sigma_t = sigma_t_[material * negroups_ + g_out] * density_mult;
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double scatter_flat = 0.0f;
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double fission_flat = 0.0f;
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@ -61,9 +62,11 @@ void LinearSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)
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MomentArray flux_linear = srh.flux_moments_old(g_in);
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// Handles for cross sections
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double sigma_s =
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sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];
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double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];
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double sigma_s = sigma_s_[material * negroups_ * negroups_ +
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g_out * negroups_ + g_in] *
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density_mult;
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double nu_sigma_f =
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nu_sigma_f_[material * negroups_ + g_in] * density_mult;
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double chi = chi_[material * negroups_ + g_out];
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// Compute source terms for flat and linear components of the flux
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@ -435,7 +435,8 @@ void RandomRay::attenuate_flux_flat_source(
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// MOC incoming flux attenuation + source contribution/attenuation equation
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for (int g = 0; g < negroups_; g++) {
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float sigma_t = domain_->sigma_t_[material * negroups_ + g];
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float sigma_t =
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domain_->sigma_t_[material * negroups_ + g] * srh.density_mult();
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float tau = sigma_t * distance;
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float exponential = cjosey_exponential(tau); // exponential = 1 - exp(-tau)
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float new_delta_psi = (angular_flux_[g] - srh.source(g)) * exponential;
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@ -558,7 +559,8 @@ void RandomRay::attenuate_flux_linear_source(
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for (int g = 0; g < negroups_; g++) {
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// Compute tau, the optical thickness of the ray segment
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float sigma_t = domain_->sigma_t_[material * negroups_ + g];
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float sigma_t =
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domain_->sigma_t_[material * negroups_ + g] * srh.density_mult();
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float tau = sigma_t * distance;
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// If tau is very small, set it to zero to avoid numerical issues.
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@ -11,10 +11,11 @@ namespace openmc {
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//==============================================================================
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SourceRegionHandle::SourceRegionHandle(SourceRegion& sr)
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: negroups_(sr.scalar_flux_old_.size()), material_(&sr.material_),
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is_small_(&sr.is_small_), n_hits_(&sr.n_hits_),
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is_linear_(sr.source_gradients_.size() > 0), lock_(&sr.lock_),
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volume_(&sr.volume_), volume_t_(&sr.volume_t_), volume_sq_(&sr.volume_sq_),
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volume_sq_t_(&sr.volume_sq_t_), volume_naive_(&sr.volume_naive_),
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density_mult_(&sr.density_mult_), is_small_(&sr.is_small_),
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n_hits_(&sr.n_hits_), is_linear_(sr.source_gradients_.size() > 0),
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lock_(&sr.lock_), volume_(&sr.volume_), volume_t_(&sr.volume_t_),
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volume_sq_(&sr.volume_sq_), volume_sq_t_(&sr.volume_sq_t_),
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volume_naive_(&sr.volume_naive_),
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position_recorded_(&sr.position_recorded_),
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external_source_present_(&sr.external_source_present_),
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position_(&sr.position_), centroid_(&sr.centroid_),
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@ -70,6 +71,7 @@ void SourceRegionContainer::push_back(const SourceRegion& sr)
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// Scalar fields
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material_.push_back(sr.material_);
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density_mult_.push_back(sr.density_mult_);
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is_small_.push_back(sr.is_small_);
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n_hits_.push_back(sr.n_hits_);
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lock_.push_back(sr.lock_);
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@ -123,6 +125,7 @@ void SourceRegionContainer::assign(
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// Clear existing data
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n_source_regions_ = 0;
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material_.clear();
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density_mult_.clear();
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is_small_.clear();
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n_hits_.clear();
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lock_.clear();
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@ -180,6 +183,7 @@ SourceRegionHandle SourceRegionContainer::get_source_region_handle(int64_t sr)
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SourceRegionHandle handle;
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handle.negroups_ = negroups();
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handle.material_ = &material(sr);
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handle.density_mult_ = &density_mult(sr);
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handle.is_small_ = &is_small(sr);
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handle.n_hits_ = &n_hits(sr);
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handle.is_linear_ = is_linear();
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@ -0,0 +1,109 @@
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<?xml version='1.0' encoding='utf-8'?>
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<model>
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<materials>
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<cross_sections>mgxs.h5</cross_sections>
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<material id="1" name="UO2 fuel">
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<density value="1.0" units="macro"/>
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<macroscopic name="UO2"/>
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</material>
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<material id="2" name="Water">
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<density value="1.0" units="macro"/>
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<macroscopic name="LWTR"/>
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</material>
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</materials>
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<geometry>
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<cell id="1" name="fuel inner a" material="1" region="-2" density="2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0" universe="1"/>
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<cell id="2" name="fuel inner b" material="1" region="2 -3" density="2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0" universe="1"/>
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<cell id="3" name="fuel inner c" material="1" region="3 -1" density="2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0" universe="1"/>
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<cell id="4" name="moderator inner a" material="2" region="1 -4" universe="1"/>
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<cell id="5" name="moderator outer b" material="2" region="4 -5" universe="1"/>
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<cell id="6" name="moderator outer c" material="2" region="5" universe="1"/>
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<cell id="7" name="azimuthal_cell_0" fill="1" region="6 -7" universe="2"/>
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<cell id="8" name="azimuthal_cell_1" fill="1" region="7 -8" universe="2"/>
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<cell id="9" name="azimuthal_cell_2" fill="1" region="8 -9" universe="2"/>
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<cell id="10" name="azimuthal_cell_3" fill="1" region="9 -10" universe="2"/>
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<cell id="11" name="azimuthal_cell_4" fill="1" region="10 -11" universe="2"/>
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<cell id="12" name="azimuthal_cell_5" fill="1" region="11 -12" universe="2"/>
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<cell id="13" name="azimuthal_cell_6" fill="1" region="12 -13" universe="2"/>
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<cell id="14" name="azimuthal_cell_7" fill="1" region="13 -6" universe="2"/>
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<cell id="15" name="moderator infinite" material="2" universe="3"/>
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<cell id="16" fill="4" universe="5"/>
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<cell id="17" name="assembly" fill="6" region="14 -15 16 -17" universe="7"/>
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<lattice id="4">
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<pitch>0.126 0.126</pitch>
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<dimension>10 10</dimension>
|
||||
<lower_left>-0.63 -0.63</lower_left>
|
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<universes>
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
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3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 </universes>
|
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<lower_left>-1.26 -1.26</lower_left>
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<universes>
|
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2 2
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2 5 </universes>
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<surface id="3" name="inner ring b" type="z-cylinder" coeffs="0.0 0.0 0.45"/>
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<surface id="4" name="outer ring a" type="z-cylinder" coeffs="0.0 0.0 0.6"/>
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<surface id="5" name="outer ring b" type="z-cylinder" coeffs="0.0 0.0 0.69"/>
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<surface id="13" type="plane" coeffs="0.7071067811865477 0.7071067811865474 0 0"/>
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<surface id="14" name="minimum x" type="x-plane" boundary="reflective" coeffs="-1.26"/>
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<surface id="15" name="maximum x" type="x-plane" boundary="reflective" coeffs="1.26"/>
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<surface id="16" name="minimum y" type="y-plane" boundary="reflective" coeffs="-1.26"/>
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<surface id="17" name="maximum y" type="y-plane" boundary="reflective" coeffs="1.26"/>
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</geometry>
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<settings>
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<run_mode>eigenvalue</run_mode>
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<particles>100</particles>
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<batches>10</batches>
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<inactive>5</inactive>
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<energy_mode>multi-group</energy_mode>
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<random_ray>
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<distance_active>100.0</distance_active>
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<distance_inactive>20.0</distance_inactive>
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<source type="independent" strength="1.0" particle="neutron">
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<space type="box">
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<parameters>-1.26 -1.26 -1 1.26 1.26 1</parameters>
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</space>
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</source>
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<volume_normalized_flux_tallies>true</volume_normalized_flux_tallies>
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</random_ray>
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<tallies>
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<upper_right>1.26 1.26</upper_right>
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</mesh>
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<filter id="1" type="mesh">
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<bins>1</bins>
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<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
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</filter>
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<tally id="1" name="Mesh tally">
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<filters>1 2</filters>
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<scores>flux fission nu-fission</scores>
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<estimator>analog</estimator>
|
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</tally>
|
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</tallies>
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</model>
|
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|
|
@ -0,0 +1,171 @@
|
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k-combined:
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7.606488E-01 9.025978E-03
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tally 1:
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6.209503E-01
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|
|
@ -0,0 +1,244 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
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<model>
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<materials>
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<cross_sections>mgxs.h5</cross_sections>
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<material id="1" name="source">
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<density value="1.0" units="macro"/>
|
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<macroscopic name="source"/>
|
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</material>
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<material id="2" name="void">
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<density value="1.0" units="macro"/>
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<macroscopic name="void"/>
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</material>
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<material id="3" name="absorber">
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<density value="1.0" units="macro"/>
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<macroscopic name="absorber"/>
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</material>
|
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</materials>
|
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<geometry>
|
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<cell id="1" name="infinite source region" material="1" density="1000.0" universe="1"/>
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<cell id="2" name="infinite void region" material="2" universe="2"/>
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<cell id="3" name="infinite absorber region" material="3" universe="3"/>
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<cell id="4" fill="4" universe="5"/>
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<dimension>12 12 12</dimension>
|
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|
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<universes>
|
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3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
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1 1 2 2 2 2 2 2 2 2 3 3
|
||||
|
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3 3 3 3 3 3 3 3 3 3 3 3
|
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3 3 3 3 3 3 3 3 3 3 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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|
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3 3 3 3 3 3 3 3 3 3 3 3
|
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3 3 3 3 3 3 3 3 3 3 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
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2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3 </universes>
|
||||
</lattice>
|
||||
<surface id="1" type="x-plane" boundary="reflective" coeffs="0.0"/>
|
||||
<surface id="2" type="x-plane" boundary="vacuum" coeffs="30.0"/>
|
||||
<surface id="3" type="y-plane" boundary="reflective" coeffs="0.0"/>
|
||||
<surface id="4" type="y-plane" boundary="vacuum" coeffs="30.0"/>
|
||||
<surface id="5" type="z-plane" boundary="reflective" coeffs="0.0"/>
|
||||
<surface id="6" type="z-plane" boundary="vacuum" coeffs="30.0"/>
|
||||
</geometry>
|
||||
<settings>
|
||||
<run_mode>fixed source</run_mode>
|
||||
<particles>90</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
<source type="independent" strength="3.14" particle="neutron">
|
||||
<energy type="discrete">
|
||||
<parameters>100.0 1.0</parameters>
|
||||
</energy>
|
||||
<constraints>
|
||||
<domain_type>universe</domain_type>
|
||||
<domain_ids>1</domain_ids>
|
||||
</constraints>
|
||||
</source>
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
<random_ray>
|
||||
<distance_active>500.0</distance_active>
|
||||
<distance_inactive>100.0</distance_inactive>
|
||||
<source type="independent" strength="1.0" particle="neutron">
|
||||
<space type="box">
|
||||
<parameters>0.0 0.0 0.0 30.0 30.0 30.0</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<volume_normalized_flux_tallies>true</volume_normalized_flux_tallies>
|
||||
</random_ray>
|
||||
</settings>
|
||||
<tallies>
|
||||
<filter id="3" type="material">
|
||||
<bins>1</bins>
|
||||
</filter>
|
||||
<filter id="2" type="material">
|
||||
<bins>2</bins>
|
||||
</filter>
|
||||
<filter id="1" type="material">
|
||||
<bins>3</bins>
|
||||
</filter>
|
||||
<tally id="3" name="Source Tally">
|
||||
<filters>3</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="2" name="Void Tally">
|
||||
<filters>2</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="1" name="Absorber Tally">
|
||||
<filters>1</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
</tallies>
|
||||
</model>
|
||||
|
|
@ -0,0 +1,9 @@
|
|||
tally 1:
|
||||
6.203077E-01
|
||||
7.706659E-02
|
||||
tally 2:
|
||||
3.203448E-02
|
||||
2.058679E-04
|
||||
tally 3:
|
||||
2.091970E-03
|
||||
8.765168E-07
|
||||
43
tests/regression_tests/random_ray_cell_density/test.py
Normal file
43
tests/regression_tests/random_ray_cell_density/test.py
Normal file
|
|
@ -0,0 +1,43 @@
|
|||
import os
|
||||
|
||||
import openmc
|
||||
from openmc.examples import random_ray_lattice, random_ray_three_region_cube
|
||||
from openmc.utility_funcs import change_directory
|
||||
import pytest
|
||||
|
||||
from tests.testing_harness import TolerantPyAPITestHarness
|
||||
|
||||
|
||||
class MGXSTestHarness(TolerantPyAPITestHarness):
|
||||
def _cleanup(self):
|
||||
super()._cleanup()
|
||||
f = 'mgxs.h5'
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
|
||||
|
||||
@pytest.mark.parametrize("run_mode", ["eigen", "fs"])
|
||||
def test_random_ray_basic(run_mode):
|
||||
with change_directory(run_mode):
|
||||
if run_mode == "eigen":
|
||||
openmc.reset_auto_ids()
|
||||
model = random_ray_lattice()
|
||||
# Double the densities of the lower-left fuel pin -> cell instances [0, 9).
|
||||
for id, cell in model.geometry.get_all_cells().items():
|
||||
if cell.fill.name == "UO2 fuel":
|
||||
cell.density = [((i < 8) + 1.0) for i in range(24)]
|
||||
|
||||
# Gold file was generated with manually scaled fuel cross sections.
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
else:
|
||||
openmc.reset_auto_ids()
|
||||
model = random_ray_three_region_cube()
|
||||
# Increase the density in the source region.
|
||||
for id, cell in model.geometry.get_all_cells().items():
|
||||
if cell.fill.name == "source":
|
||||
cell.density = 1e3
|
||||
|
||||
# Gold file was generated with manually scaled source cross sections.
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
Loading…
Add table
Add a link
Reference in a new issue