14515233533

Committed 17 Apr 2025 12:06PM UTC coverage: 83.16% (-2.3%) from 85.414%

Build # 14515233533

Build Type

Pull #3087

github

Committed by

web-flow

Commit Message

Merge 6ed397e9d into 47ca2916a

Pull Request Pull Request #3087: wheel building with scikit build core

Run Details

140769 of 169274 relevant lines covered (83.16%)

11830168.1 hits per line

Source File
Press 'n' to go to next uncovered line, 'b' for previous

62.61

/src/material.cpp

#include "openmc/material.h"

#include <algorithm> // for min, max, sort, fill
#include <cassert>
#include <cmath>
#include <iterator>
#include <sstream>
#include <string>
#include <unordered_set>

#include "xtensor/xbuilder.hpp"
#include "xtensor/xoperation.hpp"
#include "xtensor/xview.hpp"

#include "openmc/capi.h"
#include "openmc/container_util.h"
#include "openmc/cross_sections.h"
#include "openmc/error.h"
#include "openmc/file_utils.h"
#include "openmc/hdf5_interface.h"
#include "openmc/math_functions.h"
#include "openmc/message_passing.h"
#include "openmc/mgxs_interface.h"
#include "openmc/nuclide.h"
#include "openmc/photon.h"
#include "openmc/search.h"
#include "openmc/settings.h"
#include "openmc/simulation.h"
#include "openmc/string_utils.h"
#include "openmc/thermal.h"
#include "openmc/xml_interface.h"

namespace openmc {

//==============================================================================
// Global variables
//==============================================================================

namespace model {

std::unordered_map<int32_t, int32_t> material_map;
vector<unique_ptr<Material>> materials;

} // namespace model

//==============================================================================
// Material implementation
//==============================================================================

Material::Material(pugi::xml_node node)
{
  index_ = model::materials.size(); // Avoids warning about narrowing

  if (check_for_node(node, "id")) {
    this->set_id(std::stoi(get_node_value(node, "id")));
  } else {
    fatal_error("Must specify id of material in materials XML file.");
  }

  if (check_for_node(node, "name")) {
    name_ = get_node_value(node, "name");
  }

  if (check_for_node(node, "cfg")) {
    auto cfg = get_node_value(node, "cfg");
    write_message(
      5, "NCrystal config string for material #{}: '{}'", this->id(), cfg);
    ncrystal_mat_ = NCrystalMat(cfg);
  }

  if (check_for_node(node, "depletable")) {
    depletable_ = get_node_value_bool(node, "depletable");
  }

  bool sum_density {false};
  pugi::xml_node density_node = node.child("density");
  std::string units;
  if (density_node) {
    units = get_node_value(density_node, "units");
    if (units == "sum") {
      sum_density = true;
    } else if (units == "macro") {
      if (check_for_node(density_node, "value")) {
        density_ = std::stod(get_node_value(density_node, "value"));
      } else {
        density_ = 1.0;
      }
    } else {
      double val = std::stod(get_node_value(density_node, "value"));
      if (val <= 0.0) {
        fatal_error("Need to specify a positive density on material " +
                    std::to_string(id_) + ".");
      }

      if (units == "g/cc" || units == "g/cm3") {
        density_ = -val;
      } else if (units == "kg/m3") {
        density_ = -1.0e-3 * val;
      } else if (units == "atom/b-cm") {
        density_ = val;
      } else if (units == "atom/cc" || units == "atom/cm3") {
        density_ = 1.0e-24 * val;
      } else {
        fatal_error("Unknown units '" + units + "' specified on material " +
                    std::to_string(id_) + ".");
      }
    }
  } else {
    fatal_error("Must specify <density> element in material " +
                std::to_string(id_) + ".");
  }

  if (node.child("element")) {
    fatal_error(
      "Unable to add an element to material " + std::to_string(id_) +
      " since the element option has been removed from the xml input. "
      "Elements can only be added via the Python API, which will expand "
      "elements into their natural nuclides.");
  }

  // =======================================================================
  // READ AND PARSE <nuclide> TAGS

  // Check to ensure material has at least one nuclide
  if (!check_for_node(node, "nuclide") &&
      !check_for_node(node, "macroscopic")) {
    fatal_error("No macroscopic data or nuclides specified on material " +
                std::to_string(id_));
  }

  // Create list of macroscopic x/s based on those specified, just treat
  // them as nuclides. This is all really a facade so the user thinks they
  // are entering in macroscopic data but the code treats them the same
  // as nuclides internally.
  // Get pointer list of XML <macroscopic>
  auto node_macros = node.children("macroscopic");
  int num_macros = std::distance(node_macros.begin(), node_macros.end());

  vector<std::string> names;
  vector<double> densities;
  if (settings::run_CE && num_macros > 0) {
    fatal_error("Macroscopic can not be used in continuous-energy mode.");
  } else if (num_macros > 1) {
    fatal_error("Only one macroscopic object permitted per material, " +
                std::to_string(id_));
  } else if (num_macros == 1) {
    pugi::xml_node node_nuc = *node_macros.begin();

    // Check for empty name on nuclide
    if (!check_for_node(node_nuc, "name")) {
      fatal_error("No name specified on macroscopic data in material " +
                  std::to_string(id_));
    }

    // store nuclide name
    std::string name = get_node_value(node_nuc, "name", false, true);
    names.push_back(name);

    // Set density for macroscopic data
    if (units == "macro") {
      densities.push_back(density_);
    } else {
      fatal_error("Units can only be macro for macroscopic data " + name);
    }
  } else {
    // Create list of nuclides based on those specified
    for (auto node_nuc : node.children("nuclide")) {
      // Check for empty name on nuclide
      if (!check_for_node(node_nuc, "name")) {
        fatal_error(
          "No name specified on nuclide in material " + std::to_string(id_));
      }

      // store nuclide name
      std::string name = get_node_value(node_nuc, "name", false, true);
      names.push_back(name);

      // Check if no atom/weight percents were specified or if both atom and
      // weight percents were specified
      if (units == "macro") {
        densities.push_back(density_);
      } else {
        bool has_ao = check_for_node(node_nuc, "ao");
        bool has_wo = check_for_node(node_nuc, "wo");

        if (!has_ao && !has_wo) {
          fatal_error(
            "No atom or weight percent specified for nuclide: " + name);
        } else if (has_ao && has_wo) {
          fatal_error("Cannot specify both atom and weight percents for a "
                      "nuclide: " +
                      name);
        }

        // Copy atom/weight percents
        if (has_ao) {
          densities.push_back(std::stod(get_node_value(node_nuc, "ao")));
        } else {
          densities.push_back(-std::stod(get_node_value(node_nuc, "wo")));
        }
      }
    }
  }

  // =======================================================================
  // READ AND PARSE <isotropic> element

  vector<std::string> iso_lab;
  if (check_for_node(node, "isotropic")) {
    iso_lab = get_node_array<std::string>(node, "isotropic");
  }

  // ========================================================================
  // COPY NUCLIDES TO ARRAYS IN MATERIAL

  // allocate arrays in Material object
  auto n = names.size();
  nuclide_.reserve(n);
  atom_density_ = xt::empty<double>({n});
  if (settings::photon_transport)
    element_.reserve(n);

  for (int i = 0; i < n; ++i) {
    const auto& name {names[i]};

    // Check that this nuclide is listed in the nuclear data library
    // (cross_sections.xml for CE and the MGXS HDF5 for MG)
    if (settings::run_mode != RunMode::PLOTTING) {
      LibraryKey key {Library::Type::neutron, name};
      if (data::library_map.find(key) == data::library_map.end()) {
        fatal_error("Could not find nuclide " + name +
                    " in the "
                    "nuclear data library.");
      }
    }

    // If this nuclide hasn't been encountered yet, we need to add its name
    // and alias to the nuclide_dict
    if (data::nuclide_map.find(name) == data::nuclide_map.end()) {
      int index = data::nuclide_map.size();
      data::nuclide_map[name] = index;
      nuclide_.push_back(index);
    } else {
      nuclide_.push_back(data::nuclide_map[name]);
    }

    // If the corresponding element hasn't been encountered yet and photon
    // transport will be used, we need to add its symbol to the element_dict
    if (settings::photon_transport) {
      std::string element = to_element(name);

      // Make sure photon cross section data is available
      if (settings::run_mode != RunMode::PLOTTING) {
        LibraryKey key {Library::Type::photon, element};
        if (data::library_map.find(key) == data::library_map.end()) {
          fatal_error(
            "Could not find element " + element + " in cross_sections.xml.");
        }
      }

      if (data::element_map.find(element) == data::element_map.end()) {
        int index = data::element_map.size();
        data::element_map[element] = index;
        element_.push_back(index);
      } else {
        element_.push_back(data::element_map[element]);
      }
    }

    // Copy atom/weight percent
    atom_density_(i) = densities[i];
  }

  if (settings::run_CE) {
    // By default, isotropic-in-lab is not used
    if (iso_lab.size() > 0) {
      p0_.resize(n);

      // Apply isotropic-in-lab treatment to specified nuclides
      for (int j = 0; j < n; ++j) {
        for (const auto& nuc : iso_lab) {
          if (names[j] == nuc) {
            p0_[j] = true;
            break;
          }
        }
      }
    }
  }

  // Check to make sure either all atom percents or all weight percents are
  // given
  if (!(xt::all(atom_density_ >= 0.0) || xt::all(atom_density_ <= 0.0))) {
    fatal_error(
      "Cannot mix atom and weight percents in material " + std::to_string(id_));
  }

  // Determine density if it is a sum value
  if (sum_density)
    density_ = xt::sum(atom_density_)();

  if (check_for_node(node, "temperature")) {
    temperature_ = std::stod(get_node_value(node, "temperature"));
  }

  if (check_for_node(node, "volume")) {
    volume_ = std::stod(get_node_value(node, "volume"));
  }

  // =======================================================================
  // READ AND PARSE <sab> TAG FOR THERMAL SCATTERING DATA
  if (settings::run_CE) {
    // Loop over <sab> elements

    vector<std::string> sab_names;
    for (auto node_sab : node.children("sab")) {
      // Determine name of thermal scattering table
      if (!check_for_node(node_sab, "name")) {
        fatal_error("Need to specify <name> for thermal scattering table.");
      }
      std::string name = get_node_value(node_sab, "name");
      sab_names.push_back(name);

      // Read the fraction of nuclei affected by this thermal scattering table
      double fraction = 1.0;
      if (check_for_node(node_sab, "fraction")) {
        fraction = std::stod(get_node_value(node_sab, "fraction"));
      }

      // Check that the thermal scattering table is listed in the
      // cross_sections.xml file
      if (settings::run_mode != RunMode::PLOTTING) {
        LibraryKey key {Library::Type::thermal, name};
        if (data::library_map.find(key) == data::library_map.end()) {
          fatal_error("Could not find thermal scattering data " + name +
                      " in cross_sections.xml file.");
        }
      }

      // Determine index of thermal scattering data in global
      // data::thermal_scatt array
      int index_table;
      if (data::thermal_scatt_map.find(name) == data::thermal_scatt_map.end()) {
        index_table = data::thermal_scatt_map.size();
        data::thermal_scatt_map[name] = index_table;
      } else {
        index_table = data::thermal_scatt_map[name];
      }

      // Add entry to thermal tables vector. For now, we put the nuclide index
      // as zero since we don't know which nuclides the table is being applied
      // to yet (this is assigned in init_thermal)
      thermal_tables_.push_back({index_table, 0, fraction});
    }
  }
}

Material::~Material()
{
  model::material_map.erase(id_);
}

Material& Material::clone()
{
  std::unique_ptr<Material> mat = std::make_unique<Material>();

  // set all other parameters to whatever the calling Material has
  mat->name_ = name_;
  mat->nuclide_ = nuclide_;
  mat->element_ = element_;
  mat->ncrystal_mat_ = ncrystal_mat_.clone();
  mat->atom_density_ = atom_density_;
  mat->density_ = density_;
  mat->density_gpcc_ = density_gpcc_;
  mat->volume_ = volume_;
  mat->fissionable() = fissionable_;
  mat->depletable() = depletable_;
  mat->p0_ = p0_;
  mat->mat_nuclide_index_ = mat_nuclide_index_;
  mat->thermal_tables_ = thermal_tables_;
  mat->temperature_ = temperature_;

  if (ttb_)
    mat->ttb_ = std::make_unique<Bremsstrahlung>(*ttb_);

  mat->index_ = model::materials.size();
  mat->set_id(C_NONE);
  model::materials.push_back(std::move(mat));
  return *model::materials.back();
}

void Material::finalize()
{
  // Set fissionable if any nuclide is fissionable
  if (settings::run_CE) {
    for (const auto& i_nuc : nuclide_) {
      if (data::nuclides[i_nuc]->fissionable_) {
        fissionable_ = true;
        break;
      }
    }

    // Generate material bremsstrahlung data for electrons and positrons
    if (settings::photon_transport &&
        settings::electron_treatment == ElectronTreatment::TTB) {
      this->init_bremsstrahlung();
    }

    // Assign thermal scattering tables
    this->init_thermal();
  }

  // Normalize density
  this->normalize_density();
}

void Material::normalize_density()
{
  bool percent_in_atom = (atom_density_(0) >= 0.0);
  bool density_in_atom = (density_ >= 0.0);

  for (int i = 0; i < nuclide_.size(); ++i) {
    // determine atomic weight ratio
    int i_nuc = nuclide_[i];
    double awr = settings::run_CE ? data::nuclides[i_nuc]->awr_
                                  : data::mg.nuclides_[i_nuc].awr;

    // if given weight percent, convert all values so that they are divided
    // by awr. thus, when a sum is done over the values, it's actually
    // sum(w/awr)
    if (!percent_in_atom)
      atom_density_(i) = -atom_density_(i) / awr;
  }

  // determine normalized atom percents. if given atom percents, this is
  // straightforward. if given weight percents, the value is w/awr and is
  // divided by sum(w/awr)
  atom_density_ /= xt::sum(atom_density_)();

  // Change density in g/cm^3 to atom/b-cm. Since all values are now in
  // atom percent, the sum needs to be re-evaluated as 1/sum(x*awr)
  if (!density_in_atom) {
    double sum_percent = 0.0;
    for (int i = 0; i < nuclide_.size(); ++i) {
      int i_nuc = nuclide_[i];
      double awr = settings::run_CE ? data::nuclides[i_nuc]->awr_
                                    : data::mg.nuclides_[i_nuc].awr;
      sum_percent += atom_density_(i) * awr;
    }
    sum_percent = 1.0 / sum_percent;
    density_ = -density_ * N_AVOGADRO / MASS_NEUTRON * sum_percent;
  }

  // Calculate nuclide atom densities
  atom_density_ *= density_;

  // Calculate density in g/cm^3.
  density_gpcc_ = 0.0;
  for (int i = 0; i < nuclide_.size(); ++i) {
    int i_nuc = nuclide_[i];
    double awr = settings::run_CE ? data::nuclides[i_nuc]->awr_ : 1.0;
    density_gpcc_ += atom_density_(i) * awr * MASS_NEUTRON / N_AVOGADRO;
  }
}

void Material::init_thermal()
{
  vector<ThermalTable> tables;

  std::unordered_set<int> already_checked;
  for (const auto& table : thermal_tables_) {
    // Make sure each S(a,b) table only gets checked once
    if (already_checked.find(table.index_table) != already_checked.end()) {
      continue;
    }
    already_checked.insert(table.index_table);

    // In order to know which nuclide the S(a,b) table applies to, we need
    // to search through the list of nuclides for one which has a matching
    // name
    bool found = false;
    for (int j = 0; j < nuclide_.size(); ++j) {
      const auto& name {data::nuclides[nuclide_[j]]->name_};
      if (contains(data::thermal_scatt[table.index_table]->nuclides_, name)) {
        tables.push_back({table.index_table, j, table.fraction});
        found = true;
      }
    }

    // Check to make sure thermal scattering table matched a nuclide
    if (!found) {
      fatal_error("Thermal scattering table " +
                  data::thermal_scatt[table.index_table]->name_ +
                  " did not match any nuclide on material " +
                  std::to_string(id_));
    }
  }

  // Make sure each nuclide only appears in one table.
  for (int j = 0; j < tables.size(); ++j) {
    for (int k = j + 1; k < tables.size(); ++k) {
      if (tables[j].index_nuclide == tables[k].index_nuclide) {
        int index = nuclide_[tables[j].index_nuclide];
        auto name = data::nuclides[index]->name_;
        fatal_error(
          name + " in material " + std::to_string(id_) +
          " was found "
          "in multiple thermal scattering tables. Each nuclide can appear in "
          "only one table per material.");
      }
    }
  }

  // If there are multiple S(a,b) tables, we need to make sure that the
  // entries in i_sab_nuclides are sorted or else they won't be applied
  // correctly in the cross_section module.
  std::sort(tables.begin(), tables.end(), [](ThermalTable a, ThermalTable b) {
    return a.index_nuclide < b.index_nuclide;
  });

  // Update the list of thermal tables
  thermal_tables_ = tables;
}

void Material::collision_stopping_power(double* s_col, bool positron)
{
  // Average electron number and average atomic weight
  double electron_density = 0.0;
  double mass_density = 0.0;

  // Log of the mean excitation energy of the material
  double log_I = 0.0;

  // Effective number of conduction electrons in the material
  double n_conduction = 0.0;

  // Oscillator strength and square of the binding energy for each oscillator
  // in material
  vector<double> f;
  vector<double> e_b_sq;

  for (int i = 0; i < element_.size(); ++i) {
    const auto& elm = *data::elements[element_[i]];
    double awr = data::nuclides[nuclide_[i]]->awr_;

    // Get atomic density of nuclide given atom/weight percent
    double atom_density =
      (atom_density_[0] > 0.0) ? atom_density_[i] : -atom_density_[i] / awr;

    electron_density += atom_density * elm.Z_;
    mass_density += atom_density * awr * MASS_NEUTRON;
    log_I += atom_density * elm.Z_ * std::log(elm.I_);

    for (int j = 0; j < elm.n_electrons_.size(); ++j) {
      if (elm.n_electrons_[j] < 0) {
        n_conduction -= elm.n_electrons_[j] * atom_density;
        continue;
      }
      e_b_sq.push_back(elm.ionization_energy_[j] * elm.ionization_energy_[j]);
      f.push_back(elm.n_electrons_[j] * atom_density);
    }
  }
  log_I /= electron_density;
  n_conduction /= electron_density;
  for (auto& f_i : f)
    f_i /= electron_density;

  // Get density in g/cm^3 if it is given in atom/b-cm
  double density = (density_ < 0.0) ? -density_ : mass_density / N_AVOGADRO;

  // Calculate the square of the plasma energy
  double e_p_sq =
    PLANCK_C * PLANCK_C * PLANCK_C * N_AVOGADRO * electron_density * density /
    (2.0 * PI * PI * FINE_STRUCTURE * MASS_ELECTRON_EV * mass_density);

  // Get the Sternheimer adjustment factor
  double rho =
    sternheimer_adjustment(f, e_b_sq, e_p_sq, n_conduction, log_I, 1.0e-6, 100);

  // Classical electron radius in cm
  constexpr double CM_PER_ANGSTROM {1.0e-8};
  constexpr double r_e =
    CM_PER_ANGSTROM * PLANCK_C / (2.0 * PI * FINE_STRUCTURE * MASS_ELECTRON_EV);

  // Constant in expression for collision stopping power
  constexpr double BARN_PER_CM_SQ {1.0e24};
  double c =
    BARN_PER_CM_SQ * 2.0 * PI * r_e * r_e * MASS_ELECTRON_EV * electron_density;

  // Loop over incident charged particle energies
  for (int i = 0; i < data::ttb_e_grid.size(); ++i) {
    double E = data::ttb_e_grid(i);

    // Get the density effect correction
    double delta =
      density_effect(f, e_b_sq, e_p_sq, n_conduction, rho, E, 1.0e-6, 100);

    // Square of the ratio of the speed of light to the velocity of the charged
    // particle
    double beta_sq = E * (E + 2.0 * MASS_ELECTRON_EV) /
                     ((E + MASS_ELECTRON_EV) * (E + MASS_ELECTRON_EV));

    double tau = E / MASS_ELECTRON_EV;

    double F;
    if (positron) {
      double t = tau + 2.0;
      F = std::log(4.0) - (beta_sq / 12.0) * (23.0 + 14.0 / t + 10.0 / (t * t) +
                                               4.0 / (t * t * t));
    } else {
      F = (1.0 - beta_sq) *
          (1.0 + tau * tau / 8.0 - (2.0 * tau + 1.0) * std::log(2.0));
    }

    // Calculate the collision stopping power for this energy
    s_col[i] =
      c / beta_sq *
      (2.0 * (std::log(E) - log_I) + std::log(1.0 + tau / 2.0) + F - delta);
  }
}

void Material::init_bremsstrahlung()
{
  // Create new object
  ttb_ = make_unique<Bremsstrahlung>();

  // Get the size of the energy grids
  auto n_k = data::ttb_k_grid.size();
  auto n_e = data::ttb_e_grid.size();

  // Determine number of elements
  int n = element_.size();

  for (int particle = 0; particle < 2; ++particle) {
    // Loop over logic twice, once for electron, once for positron
    BremsstrahlungData* ttb =
      (particle == 0) ? &ttb_->electron : &ttb_->positron;
    bool positron = (particle == 1);

    // Allocate arrays for TTB data
    ttb->pdf = xt::zeros<double>({n_e, n_e});
    ttb->cdf = xt::zeros<double>({n_e, n_e});
    ttb->yield = xt::empty<double>({n_e});

    // Allocate temporary arrays
    xt::xtensor<double, 1> stopping_power_collision({n_e}, 0.0);
    xt::xtensor<double, 1> stopping_power_radiative({n_e}, 0.0);
    xt::xtensor<double, 2> dcs({n_e, n_k}, 0.0);

    double Z_eq_sq = 0.0;
    double sum_density = 0.0;

    // Get the collision stopping power of the material
    this->collision_stopping_power(stopping_power_collision.data(), positron);

    // Calculate the molecular DCS and the molecular radiative stopping power
    // using Bragg's additivity rule.
    for (int i = 0; i < n; ++i) {
      // Get pointer to current element
      const auto& elm = *data::elements[element_[i]];
      double awr = data::nuclides[nuclide_[i]]->awr_;

      // Get atomic density and mass density of nuclide given atom/weight
      // percent
      double atom_density =
        (atom_density_[0] > 0.0) ? atom_density_[i] : -atom_density_[i] / awr;

      // Calculate the "equivalent" atomic number Zeq of the material
      Z_eq_sq += atom_density * elm.Z_ * elm.Z_;
      sum_density += atom_density;

      // Accumulate material DCS
      dcs += (atom_density * elm.Z_ * elm.Z_) * elm.dcs_;

      // Accumulate material radiative stopping power
      stopping_power_radiative += atom_density * elm.stopping_power_radiative_;
    }
    Z_eq_sq /= sum_density;

    // Calculate the positron DCS and radiative stopping power. These are
    // obtained by multiplying the electron DCS and radiative stopping powers by
    // a factor r, which is a numerical approximation of the ratio of the
    // radiative stopping powers for positrons and electrons. Source: F. Salvat,
    // J. M. Fernández-Varea, and J. Sempau, "PENELOPE-2011: A Code System for
    // Monte Carlo Simulation of Electron and Photon Transport," OECD-NEA,
    // Issy-les-Moulineaux, France (2011).
    if (positron) {
      for (int i = 0; i < n_e; ++i) {
        double t = std::log(
          1.0 + 1.0e6 * data::ttb_e_grid(i) / (Z_eq_sq * MASS_ELECTRON_EV));
        double r =
          1.0 -
          std::exp(-1.2359e-1 * t + 6.1274e-2 * std::pow(t, 2) -
                   3.1516e-2 * std::pow(t, 3) + 7.7446e-3 * std::pow(t, 4) -
                   1.0595e-3 * std::pow(t, 5) + 7.0568e-5 * std::pow(t, 6) -
                   1.808e-6 * std::pow(t, 7));
        stopping_power_radiative(i) *= r;
        auto dcs_i = xt::view(dcs, i, xt::all());
        dcs_i *= r;
      }
    }

    // Total material stopping power
    xt::xtensor<double, 1> stopping_power =
      stopping_power_collision + stopping_power_radiative;

    // Loop over photon energies
    xt::xtensor<double, 1> f({n_e}, 0.0);
    xt::xtensor<double, 1> z({n_e}, 0.0);
    for (int i = 0; i < n_e - 1; ++i) {
      double w = data::ttb_e_grid(i);

      // Loop over incident particle energies
      for (int j = i; j < n_e; ++j) {
        double e = data::ttb_e_grid(j);

        // Reduced photon energy
        double k = w / e;

        // Find the lower bounding index of the reduced photon energy
        int i_k = lower_bound_index(
          data::ttb_k_grid.cbegin(), data::ttb_k_grid.cend(), k);

        // Get the interpolation bounds
        double k_l = data::ttb_k_grid(i_k);
        double k_r = data::ttb_k_grid(i_k + 1);
        double x_l = dcs(j, i_k);
        double x_r = dcs(j, i_k + 1);

        // Find the value of the DCS using linear interpolation in reduced
        // photon energy k
        double x = x_l + (k - k_l) * (x_r - x_l) / (k_r - k_l);

        // Square of the ratio of the speed of light to the velocity of the
        // charged particle
        double beta_sq = e * (e + 2.0 * MASS_ELECTRON_EV) /
                         ((e + MASS_ELECTRON_EV) * (e + MASS_ELECTRON_EV));

        // Compute the integrand of the PDF
        f(j) = x / (beta_sq * stopping_power(j) * w);
      }

      // Number of points to integrate
      int n = n_e - i;

      // Integrate the PDF using cubic spline integration over the incident
      // particle energy
      if (n > 2) {
        spline(n, &data::ttb_e_grid(i), &f(i), &z(i));

        double c = 0.0;
        for (int j = i; j < n_e - 1; ++j) {
          c += spline_integrate(n, &data::ttb_e_grid(i), &f(i), &z(i),
            data::ttb_e_grid(j), data::ttb_e_grid(j + 1));

          ttb->pdf(j + 1, i) = c;
        }

        // Integrate the last two points using trapezoidal rule in log-log space
      } else {
        double e_l = std::log(data::ttb_e_grid(i));
        double e_r = std::log(data::ttb_e_grid(i + 1));
        double x_l = std::log(f(i));
        double x_r = std::log(f(i + 1));

        ttb->pdf(i + 1, i) =
          0.5 * (e_r - e_l) * (std::exp(e_l + x_l) + std::exp(e_r + x_r));
      }
    }

    // Loop over incident particle energies
    for (int j = 1; j < n_e; ++j) {
      // Set last element of PDF to small non-zero value to enable log-log
      // interpolation
      ttb->pdf(j, j) = std::exp(-500.0);

      // Loop over photon energies
      double c = 0.0;
      for (int i = 0; i < j; ++i) {
        // Integrate the CDF from the PDF using the trapezoidal rule in log-log
        // space
        double w_l = std::log(data::ttb_e_grid(i));
        double w_r = std::log(data::ttb_e_grid(i + 1));
        double x_l = std::log(ttb->pdf(j, i));
        double x_r = std::log(ttb->pdf(j, i + 1));

        c += 0.5 * (w_r - w_l) * (std::exp(w_l + x_l) + std::exp(w_r + x_r));
        ttb->cdf(j, i + 1) = c;
      }

      // Set photon number yield
      ttb->yield(j) = c;
    }

    // Use logarithm of number yield since it is log-log interpolated
    ttb->yield = xt::where(ttb->yield > 0.0, xt::log(ttb->yield), -500.0);
  }
}

void Material::init_nuclide_index()
{
  int n = settings::run_CE ? data::nuclides.size() : data::mg.nuclides_.size();
  mat_nuclide_index_.resize(n);
  std::fill(mat_nuclide_index_.begin(), mat_nuclide_index_.end(), C_NONE);
  for (int i = 0; i < nuclide_.size(); ++i) {
    mat_nuclide_index_[nuclide_[i]] = i;
  }
}

void Material::calculate_xs(Particle& p) const
{
  // Set all material macroscopic cross sections to zero
  p.macro_xs().total = 0.0;
  p.macro_xs().absorption = 0.0;
  p.macro_xs().fission = 0.0;
  p.macro_xs().nu_fission = 0.0;

  if (p.type() == ParticleType::neutron) {
    this->calculate_neutron_xs(p);
  } else if (p.type() == ParticleType::photon) {
    this->calculate_photon_xs(p);
  }
}

void Material::calculate_neutron_xs(Particle& p) const
{
  // Find energy index on energy grid
  int neutron = static_cast<int>(ParticleType::neutron);
  int i_grid =
    std::log(p.E() / data::energy_min[neutron]) / simulation::log_spacing;

  // Determine if this material has S(a,b) tables
  bool check_sab = (thermal_tables_.size() > 0);

  // Initialize position in i_sab_nuclides
  int j = 0;

  // Calculate NCrystal cross section
  double ncrystal_xs = -1.0;
  if (ncrystal_mat_ && p.E() < NCRYSTAL_MAX_ENERGY) {
    ncrystal_xs = ncrystal_mat_.xs(p);
  }

  // Add contribution from each nuclide in material
  for (int i = 0; i < nuclide_.size(); ++i) {
    // ======================================================================
    // CHECK FOR S(A,B) TABLE

    int i_sab = C_NONE;
    double sab_frac = 0.0;

    // Check if this nuclide matches one of the S(a,b) tables specified.
    // This relies on thermal_tables_ being sorted by .index_nuclide
    if (check_sab) {
      const auto& sab {thermal_tables_[j]};
      if (i == sab.index_nuclide) {
        // Get index in sab_tables
        i_sab = sab.index_table;
        sab_frac = sab.fraction;

        // If particle energy is greater than the highest energy for the
        // S(a,b) table, then don't use the S(a,b) table
        if (p.E() > data::thermal_scatt[i_sab]->energy_max_)
          i_sab = C_NONE;

        // Increment position in thermal_tables_
        ++j;

        // Don't check for S(a,b) tables if there are no more left
        if (j == thermal_tables_.size())
          check_sab = false;
      }
    }

    // ======================================================================
    // CALCULATE MICROSCOPIC CROSS SECTION

    // Get nuclide index
    int i_nuclide = nuclide_[i];

    // Update microscopic cross section for this nuclide
    p.update_neutron_xs(i_nuclide, i_grid, i_sab, sab_frac, ncrystal_xs);
    auto& micro = p.neutron_xs(i_nuclide);

    // ======================================================================
    // ADD TO MACROSCOPIC CROSS SECTION

    // Copy atom density of nuclide in material
    double atom_density = atom_density_(i);

    // Add contributions to cross sections
    p.macro_xs().total += atom_density * micro.total;
    p.macro_xs().absorption += atom_density * micro.absorption;
    p.macro_xs().fission += atom_density * micro.fission;
    p.macro_xs().nu_fission += atom_density * micro.nu_fission;
  }
}

void Material::calculate_photon_xs(Particle& p) const
{
  p.macro_xs().coherent = 0.0;
  p.macro_xs().incoherent = 0.0;
  p.macro_xs().photoelectric = 0.0;
  p.macro_xs().pair_production = 0.0;

  // Add contribution from each nuclide in material
  for (int i = 0; i < nuclide_.size(); ++i) {
    // ========================================================================
    // CALCULATE MICROSCOPIC CROSS SECTION

    // Determine microscopic cross sections for this nuclide
    int i_element = element_[i];

    // Calculate microscopic cross section for this nuclide
    const auto& micro {p.photon_xs(i_element)};
    if (p.E() != micro.last_E) {
      data::elements[i_element]->calculate_xs(p);
    }

    // ========================================================================
    // ADD TO MACROSCOPIC CROSS SECTION

    // Copy atom density of nuclide in material
    double atom_density = atom_density_(i);

    // Add contributions to material macroscopic cross sections
    p.macro_xs().total += atom_density * micro.total;
    p.macro_xs().coherent += atom_density * micro.coherent;
    p.macro_xs().incoherent += atom_density * micro.incoherent;
    p.macro_xs().photoelectric += atom_density * micro.photoelectric;
    p.macro_xs().pair_production += atom_density * micro.pair_production;
  }
}

void Material::set_id(int32_t id)
{
  assert(id >= 0 || id == C_NONE);

  // Clear entry in material map if an ID was already assigned before
  if (id_ != C_NONE) {
    model::material_map.erase(id_);
    id_ = C_NONE;
  }

  // Make sure no other material has same ID
  if (model::material_map.find(id) != model::material_map.end()) {
    throw std::runtime_error {
      "Two materials have the same ID: " + std::to_string(id)};
  }

  // If no ID specified, auto-assign next ID in sequence
  if (id == C_NONE) {
    id = 0;
    for (const auto& m : model::materials) {
      id = std::max(id, m->id_);
    }
    ++id;
  }

  // Update ID and entry in material map
  id_ = id;
  model::material_map[id] = index_;
}

void Material::set_density(double density, const std::string& units)
{
  assert(density >= 0.0);

  if (nuclide_.empty()) {
    throw std::runtime_error {"No nuclides exist in material yet."};
  }

  if (units == "atom/b-cm") {
    // Set total density based on value provided
    density_ = density;

    // Determine normalized atom percents
    double sum_percent = xt::sum(atom_density_)();
    atom_density_ /= sum_percent;

    // Recalculate nuclide atom densities based on given density
    atom_density_ *= density;

    // Calculate density in g/cm^3.
    density_gpcc_ = 0.0;
    for (int i = 0; i < nuclide_.size(); ++i) {
      int i_nuc = nuclide_[i];
      double awr = data::nuclides[i_nuc]->awr_;
      density_gpcc_ += atom_density_(i) * awr * MASS_NEUTRON / N_AVOGADRO;
    }
  } else if (units == "g/cm3" || units == "g/cc") {
    // Determine factor by which to change densities
    double previous_density_gpcc = density_gpcc_;
    double f = density / previous_density_gpcc;

    // Update densities
    density_gpcc_ = density;
    density_ *= f;
    atom_density_ *= f;
  } else {
    throw std::invalid_argument {
      "Invalid units '" + std::string(units.data()) + "' specified."};
  }
}

void Material::set_densities(
  const vector<std::string>& name, const vector<double>& density)
{
  auto n = name.size();
  assert(n > 0);
  assert(n == density.size());

  if (n != nuclide_.size()) {
    nuclide_.resize(n);
    atom_density_ = xt::zeros<double>({n});
    if (settings::photon_transport)
      element_.resize(n);
  }

  double sum_density = 0.0;
  for (int64_t i = 0; i < n; ++i) {
    const auto& nuc {name[i]};
    if (data::nuclide_map.find(nuc) == data::nuclide_map.end()) {
      int err = openmc_load_nuclide(nuc.c_str(), nullptr, 0);
      if (err < 0)
        throw std::runtime_error {openmc_err_msg};
    }

    nuclide_[i] = data::nuclide_map.at(nuc);
    assert(density[i] > 0.0);
    atom_density_(i) = density[i];
    sum_density += density[i];

    if (settings::photon_transport) {
      auto element_name = to_element(nuc);
      element_[i] = data::element_map.at(element_name);
    }
  }

  // Set total density to the sum of the vector
  this->set_density(sum_density, "atom/b-cm");

  // Generate material bremsstrahlung data for electrons and positrons
  if (settings::photon_transport &&
      settings::electron_treatment == ElectronTreatment::TTB) {
    this->init_bremsstrahlung();
  }

  // Assign S(a,b) tables
  this->init_thermal();
}

double Material::volume() const
{
  if (volume_ < 0.0) {
    throw std::runtime_error {
      "Volume for material with ID=" + std::to_string(id_) + " not set."};
  }
  return volume_;
}

double Material::temperature() const
{
  // If material doesn't have an assigned temperature, use global default
  return temperature_ >= 0 ? temperature_ : settings::temperature_default;
}

void Material::to_hdf5(hid_t group) const
{
  hid_t material_group = create_group(group, "material " + std::to_string(id_));

  write_attribute(material_group, "depletable", static_cast<int>(depletable()));
  if (volume_ > 0.0) {
    write_attribute(material_group, "volume", volume_);
  }
  if (temperature_ > 0.0) {
    write_attribute(material_group, "temperature", temperature_);
  }
  write_dataset(material_group, "name", name_);
  write_dataset(material_group, "atom_density", density_);

  // Copy nuclide/macro name for each nuclide to vector
  vector<std::string> nuc_names;
  vector<std::string> macro_names;
  vector<double> nuc_densities;
  if (settings::run_CE) {
    for (int i = 0; i < nuclide_.size(); ++i) {
      int i_nuc = nuclide_[i];
      nuc_names.push_back(data::nuclides[i_nuc]->name_);
      nuc_densities.push_back(atom_density_(i));
    }
  } else {
    for (int i = 0; i < nuclide_.size(); ++i) {
      int i_nuc = nuclide_[i];
      if (data::mg.nuclides_[i_nuc].awr != MACROSCOPIC_AWR) {
        nuc_names.push_back(data::mg.nuclides_[i_nuc].name);
        nuc_densities.push_back(atom_density_(i));
      } else {
        macro_names.push_back(data::mg.nuclides_[i_nuc].name);
      }
    }
  }

  // Write vector to 'nuclides'
  if (!nuc_names.empty()) {
    write_dataset(material_group, "nuclides", nuc_names);
    write_dataset(material_group, "nuclide_densities", nuc_densities);
  }

  // Write vector to 'macroscopics'
  if (!macro_names.empty()) {
    write_dataset(material_group, "macroscopics", macro_names);
  }

  if (!thermal_tables_.empty()) {
    vector<std::string> sab_names;
    for (const auto& table : thermal_tables_) {
      sab_names.push_back(data::thermal_scatt[table.index_table]->name_);
    }
    write_dataset(material_group, "sab_names", sab_names);
  }

  close_group(material_group);
}

void Material::export_properties_hdf5(hid_t group) const
{
  hid_t material_group = create_group(group, "material " + std::to_string(id_));
  write_attribute(material_group, "atom_density", density_);
  write_attribute(material_group, "mass_density", density_gpcc_);
  close_group(material_group);
}

void Material::import_properties_hdf5(hid_t group)
{
  hid_t material_group = open_group(group, "material " + std::to_string(id_));
  double density;
  read_attribute(material_group, "atom_density", density);
  this->set_density(density, "atom/b-cm");
  close_group(material_group);
}

void Material::add_nuclide(const std::string& name, double density)
{
  // Check if nuclide is already in material
  for (int i = 0; i < nuclide_.size(); ++i) {
    int i_nuc = nuclide_[i];
    if (data::nuclides[i_nuc]->name_ == name) {
      double awr = data::nuclides[i_nuc]->awr_;
      density_ += density - atom_density_(i);
      density_gpcc_ +=
        (density - atom_density_(i)) * awr * MASS_NEUTRON / N_AVOGADRO;
      atom_density_(i) = density;
      return;
    }
  }

  // If nuclide wasn't found, extend nuclide/density arrays
  int err = openmc_load_nuclide(name.c_str(), nullptr, 0);
  if (err < 0)
    throw std::runtime_error {openmc_err_msg};

  // Append new nuclide/density
  int i_nuc = data::nuclide_map[name];
  nuclide_.push_back(i_nuc);

  // Append new element if photon transport is on
  if (settings::photon_transport) {
    int i_elem = data::element_map[to_element(name)];
    element_.push_back(i_elem);
  }

  auto n = nuclide_.size();

  // Create copy of atom_density_ array with one extra entry
  xt::xtensor<double, 1> atom_density = xt::zeros<double>({n});
  xt::view(atom_density, xt::range(0, n - 1)) = atom_density_;
  atom_density(n - 1) = density;
  atom_density_ = atom_density;

  density_ += density;
  density_gpcc_ +=
    density * data::nuclides[i_nuc]->awr_ * MASS_NEUTRON / N_AVOGADRO;
}

//==============================================================================
// Non-method functions
//==============================================================================

double sternheimer_adjustment(const vector<double>& f,
  const vector<double>& e_b_sq, double e_p_sq, double n_conduction,
  double log_I, double tol, int max_iter)
{
  // Get the total number of oscillators
  int n = f.size();

  // Calculate the Sternheimer adjustment factor using Newton's method
  double rho = 2.0;
  int iter;
  for (iter = 0; iter < max_iter; ++iter) {
    double rho_0 = rho;

    // Function to find the root of and its derivative
    double g = 0.0;
    double gp = 0.0;

    for (int i = 0; i < n; ++i) {
      // Square of resonance energy of a bound-shell oscillator
      double e_r_sq = e_b_sq[i] * rho * rho + 2.0 / 3.0 * f[i] * e_p_sq;
      g += f[i] * std::log(e_r_sq);
      gp += e_b_sq[i] * f[i] * rho / e_r_sq;
    }
    // Include conduction electrons
    if (n_conduction > 0.0) {
      g += n_conduction * std::log(n_conduction * e_p_sq);
    }

    // Set the next guess: rho_n+1 = rho_n - g(rho_n)/g'(rho_n)
    rho -= (g - 2.0 * log_I) / (2.0 * gp);

    // If the initial guess is too large, rho can be negative
    if (rho < 0.0)
      rho = rho_0 / 2.0;

    // Check for convergence
    if (std::abs(rho - rho_0) / rho_0 < tol)
      break;
  }
  // Did not converge
  if (iter >= max_iter) {
    warning("Maximum Newton-Raphson iterations exceeded.");
    rho = 1.0e-6;
  }
  return rho;
}

double density_effect(const vector<double>& f, const vector<double>& e_b_sq,
  double e_p_sq, double n_conduction, double rho, double E, double tol,
  int max_iter)
{
  // Get the total number of oscillators
  int n = f.size();

  // Square of the ratio of the speed of light to the velocity of the charged
  // particle
  double beta_sq = E * (E + 2.0 * MASS_ELECTRON_EV) /
                   ((E + MASS_ELECTRON_EV) * (E + MASS_ELECTRON_EV));

  // For nonmetals, delta = 0 for beta < beta_0, where beta_0 is obtained by
  // setting the frequency w = 0.
  double beta_0_sq = 0.0;
  if (n_conduction == 0.0) {
    for (int i = 0; i < n; ++i) {
      beta_0_sq += f[i] * e_p_sq / (e_b_sq[i] * rho * rho);
    }
    beta_0_sq = 1.0 / (1.0 + beta_0_sq);
  }
  double delta = 0.0;
  if (beta_sq < beta_0_sq)
    return delta;

  // Compute the square of the frequency w^2 using Newton's method, with the
  // initial guess of w^2 equal to beta^2 * gamma^2
  double w_sq = E / MASS_ELECTRON_EV * (E / MASS_ELECTRON_EV + 2);
  int iter;
  for (iter = 0; iter < max_iter; ++iter) {
    double w_sq_0 = w_sq;

    // Function to find the root of and its derivative
    double g = 0.0;
    double gp = 0.0;

    for (int i = 0; i < n; ++i) {
      double c = e_b_sq[i] * rho * rho / e_p_sq + w_sq;
      g += f[i] / c;
      gp -= f[i] / (c * c);
    }
    // Include conduction electrons
    g += n_conduction / w_sq;
    gp -= n_conduction / (w_sq * w_sq);

    // Set the next guess: w_n+1 = w_n - g(w_n)/g'(w_n)
    w_sq -= (g + 1.0 - 1.0 / beta_sq) / gp;

    // If the initial guess is too large, w can be negative
    if (w_sq < 0.0)
      w_sq = w_sq_0 / 2.0;

    // Check for convergence
    if (std::abs(w_sq - w_sq_0) / w_sq_0 < tol)
      break;
  }
  // Did not converge
  if (iter >= max_iter) {
    warning("Maximum Newton-Raphson iterations exceeded: setting density "
            "effect correction to zero.");
    return delta;
  }

  // Solve for the density effect correction
  for (int i = 0; i < n; ++i) {
    double l_sq = e_b_sq[i] * rho * rho / e_p_sq + 2.0 / 3.0 * f[i];
    delta += f[i] * std::log((l_sq + w_sq) / l_sq);
  }
  // Include conduction electrons
  if (n_conduction > 0.0) {
    delta += n_conduction * std::log((n_conduction + w_sq) / n_conduction);
  }

  return delta - w_sq * (1.0 - beta_sq);
}

void read_materials_xml()
{
  write_message("Reading materials XML file...", 5);

  pugi::xml_document doc;

  // Check if materials.xml exists
  std::string filename = settings::path_input + "materials.xml";
  if (!file_exists(filename)) {
    fatal_error("Material XML file '" + filename + "' does not exist!");
  }

  // Parse materials.xml file and get root element
  doc.load_file(filename.c_str());

  // Loop over XML material elements and populate the array.
  pugi::xml_node root = doc.document_element();

  read_materials_xml(root);
}

void read_materials_xml(pugi::xml_node root)
{
  for (pugi::xml_node material_node : root.children("material")) {
    model::materials.push_back(make_unique<Material>(material_node));
  }
  model::materials.shrink_to_fit();
}

void free_memory_material()
{
  model::materials.clear();
  model::material_map.clear();
}

//==============================================================================
// C API
//==============================================================================

extern "C" int openmc_get_material_index(int32_t id, int32_t* index)
{
  auto it = model::material_map.find(id);
  if (it == model::material_map.end()) {
    set_errmsg("No material exists with ID=" + std::to_string(id) + ".");
    return OPENMC_E_INVALID_ID;
  } else {
    *index = it->second;
    return 0;
  }
}

extern "C" int openmc_material_add_nuclide(
  int32_t index, const char* name, double density)
{
  int err = 0;
  if (index >= 0 && index < model::materials.size()) {
    try {
      model::materials[index]->add_nuclide(name, density);
    } catch (const std::runtime_error& e) {
      return OPENMC_E_DATA;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
  return err;
}

extern "C" int openmc_material_get_densities(
  int32_t index, const int** nuclides, const double** densities, int* n)
{
  if (index >= 0 && index < model::materials.size()) {
    auto& mat = model::materials[index];
    if (!mat->nuclides().empty()) {
      *nuclides = mat->nuclides().data();
      *densities = mat->densities().data();
      *n = mat->nuclides().size();
      return 0;
    } else {
      set_errmsg("Material atom density array has not been allocated.");
      return OPENMC_E_ALLOCATE;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_get_density(int32_t index, double* density)
{
  if (index >= 0 && index < model::materials.size()) {
    auto& mat = model::materials[index];
    *density = mat->density_gpcc();
    return 0;
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_get_fissionable(int32_t index, bool* fissionable)
{
  if (index >= 0 && index < model::materials.size()) {
    *fissionable = model::materials[index]->fissionable();
    return 0;
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_get_id(int32_t index, int32_t* id)
{
  if (index >= 0 && index < model::materials.size()) {
    *id = model::materials[index]->id();
    return 0;
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_get_temperature(
  int32_t index, double* temperature)
{
  if (index < 0 || index >= model::materials.size()) {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
  *temperature = model::materials[index]->temperature();
  return 0;
}

extern "C" int openmc_material_get_volume(int32_t index, double* volume)
{
  if (index >= 0 && index < model::materials.size()) {
    try {
      *volume = model::materials[index]->volume();
    } catch (const std::exception& e) {
      set_errmsg(e.what());
      return OPENMC_E_UNASSIGNED;
    }
    return 0;
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_set_density(
  int32_t index, double density, const char* units)
{
  if (index >= 0 && index < model::materials.size()) {
    try {
      model::materials[index]->set_density(density, units);
    } catch (const std::exception& e) {
      set_errmsg(e.what());
      return OPENMC_E_UNASSIGNED;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
  return 0;
}

extern "C" int openmc_material_set_densities(
  int32_t index, int n, const char** name, const double* density)
{
  if (index >= 0 && index < model::materials.size()) {
    try {
      model::materials[index]->set_densities(
        {name, name + n}, {density, density + n});
    } catch (const std::exception& e) {
      set_errmsg(e.what());
      return OPENMC_E_UNASSIGNED;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
  return 0;
}

extern "C" int openmc_material_set_id(int32_t index, int32_t id)
{
  if (index >= 0 && index < model::materials.size()) {
    try {
      model::materials.at(index)->set_id(id);
    } catch (const std::exception& e) {
      set_errmsg(e.what());
      return OPENMC_E_UNASSIGNED;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
  return 0;
}

extern "C" int openmc_material_get_name(int32_t index, const char** name)
{
  if (index < 0 || index >= model::materials.size()) {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }

  *name = model::materials[index]->name().data();

  return 0;
}

extern "C" int openmc_material_set_name(int32_t index, const char* name)
{
  if (index < 0 || index >= model::materials.size()) {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }

  model::materials[index]->set_name(name);

  return 0;
}

extern "C" int openmc_material_set_volume(int32_t index, double volume)
{
  if (index >= 0 && index < model::materials.size()) {
    auto& m {model::materials[index]};
    if (volume >= 0.0) {
      m->volume_ = volume;
      return 0;
    } else {
      set_errmsg("Volume must be non-negative");
      return OPENMC_E_INVALID_ARGUMENT;
    }
  } else {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }
}

extern "C" int openmc_material_get_depletable(int32_t index, bool* depletable)
{
  if (index < 0 || index >= model::materials.size()) {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }

  *depletable = model::materials[index]->depletable();

  return 0;
}

extern "C" int openmc_material_set_depletable(int32_t index, bool depletable)
{
  if (index < 0 || index >= model::materials.size()) {
    set_errmsg("Index in materials array is out of bounds.");
    return OPENMC_E_OUT_OF_BOUNDS;
  }

  model::materials[index]->depletable() = depletable;

  return 0;
}

extern "C" int openmc_extend_materials(
  int32_t n, int32_t* index_start, int32_t* index_end)
{
  if (index_start)
    *index_start = model::materials.size();
  if (index_end)
    *index_end = model::materials.size() + n - 1;
  for (int32_t i = 0; i < n; i++) {
    model::materials.push_back(make_unique<Material>());
  }
  return 0;
}

extern "C" size_t n_materials()
{
  return model::materials.size();
}

} // namespace openmc

openmc-dev / openmc / 14515233533

Source File Press 'n' to go to next uncovered line, 'b' for previous

Source File
Press 'n' to go to next uncovered line, 'b' for previous