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Merge remote-tracking branch 'upstream/develop' into cpp_geometry
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Sterling Harper
commit
452de390ba
37 changed files with 792 additions and 1252 deletions
378
src/source.cpp
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378
src/source.cpp
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#include "openmc/source.h"
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#include <algorithm> // for move
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#include <sstream> // for stringstream
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#include "xtensor/xadapt.hpp"
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#include "openmc/cell.h"
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#include "openmc/error.h"
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#include "openmc/file_utils.h"
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#include "openmc/hdf5_interface.h"
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#include "openmc/material.h"
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#include "openmc/message_passing.h"
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#include "openmc/mgxs_interface.h"
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#include "openmc/nuclide.h"
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#include "openmc/capi.h"
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#include "openmc/random_lcg.h"
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#include "openmc/search.h"
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#include "openmc/settings.h"
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#include "openmc/simulation.h"
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#include "openmc/state_point.h"
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#include "openmc/xml_interface.h"
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namespace openmc {
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//==============================================================================
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// Global variables
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//==============================================================================
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std::vector<SourceDistribution> external_sources;
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//==============================================================================
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// SourceDistribution implementation
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//==============================================================================
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SourceDistribution::SourceDistribution(UPtrSpace space, UPtrAngle angle, UPtrDist energy)
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: space_{std::move(space)}, angle_{std::move(angle)}, energy_{std::move(energy)} { }
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SourceDistribution::SourceDistribution(pugi::xml_node node)
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{
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// Check for particle type
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if (check_for_node(node, "particle")) {
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auto temp_str = get_node_value(node, "particle", true, true);
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if (temp_str == "neutron") {
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particle_ = ParticleType::neutron;
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} else if (temp_str == "photon") {
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particle_ = ParticleType::photon;
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openmc_photon_transport = true;
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} else {
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fatal_error(std::string("Unknown source particle type: ") + temp_str);
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}
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}
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// Check for source strength
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if (check_for_node(node, "strength")) {
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strength_ = std::stod(get_node_value(node, "strength"));
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}
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// Check for external source file
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if (check_for_node(node, "file")) {
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// Copy path of source file
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path_source = get_node_value(node, "file", false, true);
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// Check if source file exists
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if (!file_exists(path_source)) {
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std::stringstream msg;
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msg << "Source file '" << path_source << "' does not exist.";
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fatal_error(msg);
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}
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} else {
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// Spatial distribution for external source
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if (check_for_node(node, "space")) {
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// Get pointer to spatial distribution
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pugi::xml_node node_space = node.child("space");
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// Check for type of spatial distribution and read
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std::string type;
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if (check_for_node(node_space, "type"))
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type = get_node_value(node_space, "type", true, true);
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if (type == "cartesian") {
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space_ = UPtrSpace{new CartesianIndependent(node_space)};
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} else if (type == "box") {
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space_ = UPtrSpace{new SpatialBox(node_space)};
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} else if (type == "fission") {
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space_ = UPtrSpace{new SpatialBox(node_space, true)};
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} else if (type == "point") {
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space_ = UPtrSpace{new SpatialPoint(node_space)};
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} else {
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std::stringstream msg;
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msg << "Invalid spatial distribution for external source: " << type;
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fatal_error(msg);
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}
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} else {
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// If no spatial distribution specified, make it a point source
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space_ = UPtrSpace{new SpatialPoint()};
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}
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// Determine external source angular distribution
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if (check_for_node(node, "angle")) {
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// Get pointer to angular distribution
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pugi::xml_node node_angle = node.child("angle");
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// Check for type of angular distribution
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std::string type;
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if (check_for_node(node_angle, "type"))
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type = get_node_value(node_angle, "type", true, true);
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if (type == "isotropic") {
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angle_ = UPtrAngle{new Isotropic()};
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} else if (type == "monodirectional") {
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angle_ = UPtrAngle{new Monodirectional(node_angle)};
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} else if (type == "mu-phi") {
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angle_ = UPtrAngle{new PolarAzimuthal(node_angle)};
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} else {
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std::stringstream msg;
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msg << "Invalid angular distribution for external source: " << type;
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fatal_error(msg);
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}
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} else {
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angle_ = UPtrAngle{new Isotropic()};
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}
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// Determine external source energy distribution
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if (check_for_node(node, "energy")) {
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pugi::xml_node node_dist = node.child("energy");
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energy_ = distribution_from_xml(node_dist);
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} else {
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// Default to a Watt spectrum with parameters 0.988 MeV and 2.249 MeV^-1
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energy_ = UPtrDist{new Watt(0.988e6, 2.249e-6)};
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}
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}
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}
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Bank SourceDistribution::sample() const
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{
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Bank site;
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// Set weight to one by default
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site.wgt = 1.0;
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// Repeat sampling source location until a good site has been found
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bool found = false;
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int n_reject = 0;
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static int n_accept = 0;
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while (!found) {
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// Set particle type
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site.particle = static_cast<int>(particle_);
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// Sample spatial distribution
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Position r = space_->sample();
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site.xyz[0] = r.x;
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site.xyz[1] = r.y;
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site.xyz[2] = 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.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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if (found) {
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auto space_box = dynamic_cast<SpatialBox*>(space_.get());
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if (space_box) {
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if (space_box->only_fissionable()) {
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// Determine material
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auto c = cells[cell_index - 1];
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int32_t mat_index = c->material_[instance];
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auto m = materials[mat_index];
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if (mat_index == MATERIAL_VOID) {
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found = false;
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} else {
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bool fissionable;
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openmc_material_get_fissionable(mat_index + 1, &fissionable);
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if (!fissionable) found = false;
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}
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}
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}
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}
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// Check for rejection
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if (!found) {
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++n_reject;
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if (n_reject >= EXTSRC_REJECT_THRESHOLD &&
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static_cast<double>(n_accept)/n_reject <= EXTSRC_REJECT_FRACTION) {
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fatal_error("More than 95% of external source sites sampled were "
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"rejected. Please check your external source definition.");
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}
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}
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}
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// Increment number of accepted samples
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++n_accept;
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// Sample angle
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Direction u = angle_->sample();
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site.uvw[0] = u.x;
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site.uvw[1] = u.y;
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site.uvw[2] = u.z;
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// Check for monoenergetic source above maximum particle energy
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auto p = static_cast<int>(particle_);
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auto energy_ptr = dynamic_cast<Discrete*>(energy_.get());
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if (energy_ptr) {
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auto energies = xt::adapt(energy_ptr->x());
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if (xt::any(energies > energy_max[p-1])) {
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fatal_error("Source energy above range of energies of at least "
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"one cross section table");
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} else if (xt::any(energies < energy_min[p-1])) {
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fatal_error("Source energy below range of energies of at least "
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"one cross section table");
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}
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}
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while (true) {
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// Sample energy spectrum
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site.E = energy_->sample();
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// Resample if energy falls outside minimum or maximum particle energy
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if (site.E < energy_max[p-1] && site.E > energy_min[p-1]) break;
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}
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// Set delayed group
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site.delayed_group = 0;
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return site;
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}
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//==============================================================================
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// Non-member functions
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//==============================================================================
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void initialize_source()
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{
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write_message("Initializing source particles...", 5);
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// Get pointer to source bank
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Bank* source_bank;
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int64_t n;
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openmc_source_bank(&source_bank, &n);
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if (path_source != "") {
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// Read the source from a binary file instead of sampling from some
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// assumed source distribution
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std::stringstream msg;
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msg << "Reading source file from " << path_source << "...";
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write_message(msg, 6);
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// Open the binary file
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hid_t file_id = file_open(path_source, 'r', true);
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// Read the file type
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std::string filetype;
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read_attribute(file_id, "filetype", filetype);
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// Check to make sure this is a source file
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if (filetype != "source" && filetype != "statepoint") {
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fatal_error("Specified starting source file not a source file type.");
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}
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// Read in the source bank
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read_source_bank(file_id, work_index.data(), source_bank);
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// Close file
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file_close(file_id);
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} else {
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// Generation source sites from specified distribution in user input
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for (int64_t i = 0; i < openmc_work; ++i) {
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// initialize random number seed
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int64_t id = openmc_total_gen*n_particles + work_index[openmc::mpi::rank] + i + 1;
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set_particle_seed(id);
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// sample external source distribution
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source_bank[i] = sample_external_source();
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}
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}
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// Write out initial source
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if (openmc_write_initial_source) {
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write_message("Writing out initial source...", 5);
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std::string filename = path_output + "initial_source.h5";
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hid_t file_id = file_open(filename, 'w', true);
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write_source_bank(file_id, work_index.data(), source_bank);
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file_close(file_id);
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}
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}
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extern "C" double* rev_energy_bins_ptr();
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Bank sample_external_source()
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{
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// Set the random number generator to the source stream.
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prn_set_stream(STREAM_SOURCE);
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// Determine total source strength
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double total_strength = 0.0;
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for (auto& s : external_sources)
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total_strength += s.strength();
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// Sample from among multiple source distributions
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int i = 0;
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if (external_sources.size() > 1) {
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double xi = prn()*total_strength;
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double c = 0.0;
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for (; i < external_sources.size(); ++i) {
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c += external_sources[i].strength();
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if (xi < c) break;
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}
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}
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// Sample source site from i-th source distribution
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Bank site {external_sources[i].sample()};
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// If running in MG, convert site % E to group
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if (!openmc_run_CE) {
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// Get pointer to rev_energy_bins array on Fortran side
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double* rev_energy_bins = rev_energy_bins_ptr();
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int n = num_energy_groups + 1;
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site.E = lower_bound_index(rev_energy_bins, rev_energy_bins + n, site.E);
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site.E = num_energy_groups - site.E;
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}
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// Set the random number generator back to the tracking stream.
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prn_set_stream(STREAM_TRACKING);
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return site;
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}
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//==============================================================================
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// Fortran compatibility functions
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//==============================================================================
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extern "C" void free_memory_source()
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{
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external_sources.clear();
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}
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extern "C" double total_source_strength()
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{
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double strength = 0.0;
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for (const auto& s : external_sources) {
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strength += s.strength();
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}
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return strength;
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}
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// Needed in fill_source_bank_fixedsource
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extern "C" int overall_generation();
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//! Fill source bank at end of generation for fixed source simulations
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extern "C" void fill_source_bank_fixedsource()
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{
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if (path_source.empty()) {
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// Get pointer to source bank
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Bank* source_bank;
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int64_t n;
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openmc_source_bank(&source_bank, &n);
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for (int64_t i = 0; i < openmc_work; ++i) {
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// initialize random number seed
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int64_t id = (openmc_total_gen + overall_generation())*n_particles +
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work_index[openmc::mpi::rank] + i + 1;
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set_particle_seed(id);
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// sample external source distribution
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source_bank[i] = sample_external_source();
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}
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}
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}
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} // namespace openmc
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