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source.cpp
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#include "openmc/source.h"
#include <algorithm> // for move
#include <sstream> // for stringstream
#include "xtensor/xadapt.hpp"
#include "openmc/bank.h"
#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
//==============================================================================
namespace model {
std::vector<SourceDistribution> 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_ = Particle::Type::neutron;
} else if (temp_str == "photon") {
particle_ = Particle::Type::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)};
}
}
}
Particle::Bank SourceDistribution::sample() const
{
Particle::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 = particle_;
// 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(xyz, &cell_index, &instance);
found = (err != OPENMC_E_GEOMETRY);
// Check if spatial site is in fissionable material
if (found) {
auto space_box = dynamic_cast<SpatialBox*>(space_.get());
if (space_box) {
if (space_box->only_fissionable()) {
// Determine material
const auto& c = model::cells[cell_index];
auto mat_index = c->material_.size() == 1
? c->material_[0] : c->material_[instance];
if (mat_index == MATERIAL_VOID) {
found = false;
} else {
if (!model::materials[mat_index]->fissionable_) found = false;
}
}
}
}
// Check for rejection
if (!found) {
++n_reject;
if (n_reject >= EXTSRC_REJECT_THRESHOLD &&
static_cast<double>(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
site.u = angle_->sample();
// Check for monoenergetic source above maximum particle energy
auto p = static_cast<int>(particle_);
auto energy_ptr = dynamic_cast<Discrete*>(energy_.get());
if (energy_ptr) {
auto energies = xt::adapt(energy_ptr->x());
if (xt::any(energies > data::energy_max[p])) {
fatal_error("Source energy above range of energies of at least "
"one cross section table");
} else if (xt::any(energies < data::energy_min[p])) {
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 < data::energy_max[p] && site.E > data::energy_min[p]) break;
}
// Set delayed group
site.delayed_group = 0;
return site;
}
//==============================================================================
// Non-member functions
//==============================================================================
void initialize_source()
{
write_message("Initializing source particles...", 5);
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);
// Close file
file_close(file_id);
} else {
// Generation source sites from specified distribution in user input
for (int64_t i = 0; i < simulation::work_per_rank; ++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
simulation::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);
file_close(file_id);
}
}
Particle::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 : model::external_sources)
total_strength += s.strength();
// Sample from among multiple source distributions
int i = 0;
if (model::external_sources.size() > 1) {
double xi = prn()*total_strength;
double c = 0.0;
for (; i < model::external_sources.size(); ++i) {
c += model::external_sources[i].strength();
if (xi < c) break;
}
}
// Sample source site from i-th source distribution
Particle::Bank site {model::external_sources[i].sample()};
// If running in MG, convert site % E to group
if (!settings::run_CE) {
site.E = lower_bound_index(data::rev_energy_bins.begin(),
data::rev_energy_bins.end(), site.E);
site.E = data::num_energy_groups - site.E;
}
// Set the random number generator back to the tracking stream.
prn_set_stream(STREAM_TRACKING);
return site;
}
void free_memory_source()
{
model::external_sources.clear();
}
void fill_source_bank_fixedsource()
{
if (settings::path_source.empty()) {
for (int64_t i = 0; i < simulation::work_per_rank; ++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
simulation::source_bank[i] = sample_external_source();
}
}
}
} // namespace openmc