#include "openmc/source.h" #include // for move #include // for stringstream #include "xtensor/xadapt.hpp" #include "openmc/cell.h" #include "openmc/error.h" #include "openmc/file_utils.h" #include "openmc/hdf5_interface.h" #include "openmc/material.h" #include "openmc/message_passing.h" #include "openmc/mgxs_interface.h" #include "openmc/nuclide.h" #include "openmc/capi.h" #include "openmc/random_lcg.h" #include "openmc/search.h" #include "openmc/settings.h" #include "openmc/simulation.h" #include "openmc/state_point.h" #include "openmc/xml_interface.h" namespace openmc { //============================================================================== // Global variables //============================================================================== std::vector external_sources; //============================================================================== // SourceDistribution implementation //============================================================================== SourceDistribution::SourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy) : space_{std::move(space)}, angle_{std::move(angle)}, energy_{std::move(energy)} { } SourceDistribution::SourceDistribution(pugi::xml_node node) { // Check for particle type if (check_for_node(node, "particle")) { auto temp_str = get_node_value(node, "particle", true, true); if (temp_str == "neutron") { particle_ = ParticleType::neutron; } else if (temp_str == "photon") { particle_ = ParticleType::photon; settings::photon_transport = true; } else { fatal_error(std::string("Unknown source particle type: ") + temp_str); } } // Check for source strength if (check_for_node(node, "strength")) { strength_ = std::stod(get_node_value(node, "strength")); } // Check for external source file if (check_for_node(node, "file")) { // Copy path of source file settings::path_source = get_node_value(node, "file", false, true); // Check if source file exists if (!file_exists(settings::path_source)) { std::stringstream msg; msg << "Source file '" << settings::path_source << "' does not exist."; fatal_error(msg); } } else { // Spatial distribution for external source if (check_for_node(node, "space")) { // Get pointer to spatial distribution pugi::xml_node node_space = node.child("space"); // Check for type of spatial distribution and read std::string type; if (check_for_node(node_space, "type")) type = get_node_value(node_space, "type", true, true); if (type == "cartesian") { space_ = UPtrSpace{new CartesianIndependent(node_space)}; } else if (type == "box") { space_ = UPtrSpace{new SpatialBox(node_space)}; } else if (type == "fission") { space_ = UPtrSpace{new SpatialBox(node_space, true)}; } else if (type == "point") { space_ = UPtrSpace{new SpatialPoint(node_space)}; } else { std::stringstream msg; msg << "Invalid spatial distribution for external source: " << type; fatal_error(msg); } } else { // If no spatial distribution specified, make it a point source space_ = UPtrSpace{new SpatialPoint()}; } // Determine external source angular distribution if (check_for_node(node, "angle")) { // Get pointer to angular distribution pugi::xml_node node_angle = node.child("angle"); // Check for type of angular distribution std::string type; if (check_for_node(node_angle, "type")) type = get_node_value(node_angle, "type", true, true); if (type == "isotropic") { angle_ = UPtrAngle{new Isotropic()}; } else if (type == "monodirectional") { angle_ = UPtrAngle{new Monodirectional(node_angle)}; } else if (type == "mu-phi") { angle_ = UPtrAngle{new PolarAzimuthal(node_angle)}; } else { std::stringstream msg; msg << "Invalid angular distribution for external source: " << type; fatal_error(msg); } } else { angle_ = UPtrAngle{new Isotropic()}; } // Determine external source energy distribution if (check_for_node(node, "energy")) { pugi::xml_node node_dist = node.child("energy"); energy_ = distribution_from_xml(node_dist); } else { // Default to a Watt spectrum with parameters 0.988 MeV and 2.249 MeV^-1 energy_ = UPtrDist{new Watt(0.988e6, 2.249e-6)}; } } } Bank SourceDistribution::sample() const { Bank site; // Set weight to one by default site.wgt = 1.0; // Repeat sampling source location until a good site has been found bool found = false; int n_reject = 0; static int n_accept = 0; while (!found) { // Set particle type site.particle = static_cast(particle_); // Sample spatial distribution Position r = space_->sample(); site.xyz[0] = r.x; site.xyz[1] = r.y; site.xyz[2] = r.z; // Now search to see if location exists in geometry int32_t cell_index, instance; int err = openmc_find_cell(site.xyz, &cell_index, &instance); found = (err != OPENMC_E_GEOMETRY); // Check if spatial site is in fissionable material if (found) { auto space_box = dynamic_cast(space_.get()); if (space_box) { if (space_box->only_fissionable()) { // Determine material auto c = cells[cell_index - 1]; int32_t mat_index = c->material_[instance]; auto m = materials[mat_index]; if (mat_index == MATERIAL_VOID) { found = false; } else { bool fissionable; openmc_material_get_fissionable(mat_index + 1, &fissionable); if (!fissionable) found = false; } } } } // Check for rejection if (!found) { ++n_reject; if (n_reject >= EXTSRC_REJECT_THRESHOLD && static_cast(n_accept)/n_reject <= EXTSRC_REJECT_FRACTION) { fatal_error("More than 95% of external source sites sampled were " "rejected. Please check your external source definition."); } } } // Increment number of accepted samples ++n_accept; // Sample angle Direction u = angle_->sample(); site.uvw[0] = u.x; site.uvw[1] = u.y; site.uvw[2] = u.z; // Check for monoenergetic source above maximum particle energy auto p = static_cast(particle_); auto energy_ptr = dynamic_cast(energy_.get()); if (energy_ptr) { auto energies = xt::adapt(energy_ptr->x()); if (xt::any(energies > energy_max[p-1])) { fatal_error("Source energy above range of energies of at least " "one cross section table"); } else if (xt::any(energies < energy_min[p-1])) { fatal_error("Source energy below range of energies of at least " "one cross section table"); } } while (true) { // Sample energy spectrum site.E = energy_->sample(); // Resample if energy falls outside minimum or maximum particle energy if (site.E < energy_max[p-1] && site.E > energy_min[p-1]) break; } // Set delayed group site.delayed_group = 0; return site; } //============================================================================== // Non-member functions //============================================================================== void initialize_source() { write_message("Initializing source particles...", 5); // Get pointer to source bank Bank* source_bank; int64_t n; openmc_source_bank(&source_bank, &n); if (settings::path_source != "") { // Read the source from a binary file instead of sampling from some // assumed source distribution std::stringstream msg; msg << "Reading source file from " << settings::path_source << "..."; write_message(msg, 6); // Open the binary file hid_t file_id = file_open(settings::path_source, 'r', true); // Read the file type std::string filetype; read_attribute(file_id, "filetype", filetype); // Check to make sure this is a source file if (filetype != "source" && filetype != "statepoint") { fatal_error("Specified starting source file not a source file type."); } // Read in the source bank read_source_bank(file_id, source_bank); // Close file file_close(file_id); } else { // Generation source sites from specified distribution in user input for (int64_t i = 0; i < simulation::work; ++i) { // initialize random number seed int64_t id = simulation::total_gen*settings::n_particles + simulation::work_index[mpi::rank] + i + 1; set_particle_seed(id); // sample external source distribution source_bank[i] = sample_external_source(); } } // Write out initial source if (settings::write_initial_source) { write_message("Writing out initial source...", 5); std::string filename = settings::path_output + "initial_source.h5"; hid_t file_id = file_open(filename, 'w', true); write_source_bank(file_id, source_bank); file_close(file_id); } } extern "C" double* rev_energy_bins_ptr(); Bank sample_external_source() { // Set the random number generator to the source stream. prn_set_stream(STREAM_SOURCE); // Determine total source strength double total_strength = 0.0; for (auto& s : external_sources) total_strength += s.strength(); // Sample from among multiple source distributions int i = 0; if (external_sources.size() > 1) { double xi = prn()*total_strength; double c = 0.0; for (; i < external_sources.size(); ++i) { c += external_sources[i].strength(); if (xi < c) break; } } // Sample source site from i-th source distribution Bank site {external_sources[i].sample()}; // If running in MG, convert site % E to group if (!settings::run_CE) { // Get pointer to rev_energy_bins array on Fortran side double* rev_energy_bins = rev_energy_bins_ptr(); int n = num_energy_groups + 1; site.E = lower_bound_index(rev_energy_bins, rev_energy_bins + n, site.E); site.E = num_energy_groups - site.E; } // Set the random number generator back to the tracking stream. prn_set_stream(STREAM_TRACKING); return site; } //============================================================================== // Fortran compatibility functions //============================================================================== extern "C" void free_memory_source() { external_sources.clear(); } extern "C" double total_source_strength() { double strength = 0.0; for (const auto& s : external_sources) { strength += s.strength(); } return strength; } void fill_source_bank_fixedsource() { if (settings::path_source.empty()) { // Get pointer to source bank Bank* source_bank; int64_t n; openmc_source_bank(&source_bank, &n); for (int64_t i = 0; i < simulation::work; ++i) { // initialize random number seed int64_t id = (simulation::total_gen + overall_generation()) * settings::n_particles + simulation::work_index[mpi::rank] + i + 1; set_particle_seed(id); // sample external source distribution source_bank[i] = sample_external_source(); } } } } // namespace openmc