10424279536

Committed 16 Aug 2024 06:08PM UTC coverage: 84.718% (-0.2%) from 84.9%

Build # 10424279536

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Pull #3112

github

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web-flow

Commit Message

Merge 6ef06d3b8 into 4ef1faf76

Pull Request Pull Request #3112: Revamp CI with dependency and Python caching for efficient installs

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87.12

/src/cross_sections.cpp

#include "openmc/cross_sections.h"

#include "openmc/capi.h"
#include "openmc/constants.h"
#include "openmc/container_util.h"
#include "openmc/error.h"
#include "openmc/file_utils.h"
#include "openmc/geometry_aux.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/photon.h"
#include "openmc/settings.h"
#include "openmc/simulation.h"
#include "openmc/string_utils.h"
#include "openmc/thermal.h"
#include "openmc/timer.h"
#include "openmc/wmp.h"
#include "openmc/xml_interface.h"

#include "pugixml.hpp"

#include <cstdlib> // for getenv
#include <unordered_set>

namespace openmc {

//==============================================================================
// Global variable declarations
//==============================================================================

namespace data {

std::map<LibraryKey, std::size_t> library_map;
vector<Library> libraries;
} // namespace data

//==============================================================================
// Library methods
//==============================================================================

Library::Library(pugi::xml_node node, const std::string& directory)
{
  // Get type of library
  if (check_for_node(node, "type")) {
    auto type = get_node_value(node, "type");
    if (type == "neutron") {
      type_ = Type::neutron;
    } else if (type == "thermal") {
      type_ = Type::thermal;
    } else if (type == "photon") {
      type_ = Type::photon;
    } else if (type == "wmp") {
      type_ = Type::wmp;
    } else {
      fatal_error("Unrecognized library type: " + type);
    }
  } else {
    fatal_error("Missing library type");
  }

  // Get list of materials
  if (check_for_node(node, "materials")) {
    materials_ = get_node_array<std::string>(node, "materials");
  }

  // determine path of cross section table
  if (!check_for_node(node, "path")) {
    fatal_error("Missing library path");
  }
  std::string path = get_node_value(node, "path");

  if (starts_with(path, "/")) {
    path_ = path;
  } else if (ends_with(directory, "/")) {
    path_ = directory + path;
  } else if (!directory.empty()) {
    path_ = directory + "/" + path;
  } else {
    path_ = path;
  }

  if (!file_exists(path_)) {
    warning("Cross section library " + path_ + " does not exist.");
  }
}

//==============================================================================
// Non-member functions
//==============================================================================

void read_cross_sections_xml()
{
  pugi::xml_document doc;
  std::string filename = settings::path_input + "materials.xml";
  // Check if materials.xml exists
  if (!file_exists(filename)) {
    fatal_error("Material XML file '" + filename + "' does not exist.");
  }
  // Parse materials.xml file
  doc.load_file(filename.c_str());

  auto root = doc.document_element();

  read_cross_sections_xml(root);
}

void read_cross_sections_xml(pugi::xml_node root)
{
  // Find cross_sections.xml file -- the first place to look is the
  // materials.xml file. If no file is found there, then we check the
  // OPENMC_CROSS_SECTIONS environment variable
  if (!check_for_node(root, "cross_sections")) {
    // No cross_sections.xml file specified in settings.xml, check
    // environment variable
    if (settings::run_CE) {
      char* envvar = std::getenv("OPENMC_CROSS_SECTIONS");
      if (!envvar) {
        fatal_error(
          "No cross_sections.xml file was specified in "
          "materials.xml or in the OPENMC_CROSS_SECTIONS"
          " environment variable. OpenMC needs such a file to identify "
          "where to find data libraries. Please consult the"
          " user's guide at https://docs.openmc.org/ for "
          "information on how to set up data libraries.");
      }
      settings::path_cross_sections = envvar;
    } else {
      char* envvar = std::getenv("OPENMC_MG_CROSS_SECTIONS");
      if (!envvar) {
        fatal_error(
          "No mgxs.h5 file was specified in "
          "materials.xml or in the OPENMC_MG_CROSS_SECTIONS environment "
          "variable. OpenMC needs such a file to identify where to "
          "find MG cross section libraries. Please consult the user's "
          "guide at https://docs.openmc.org for information on "
          "how to set up MG cross section libraries.");
      }
      settings::path_cross_sections = envvar;
    }
  } else {
    settings::path_cross_sections = get_node_value(root, "cross_sections");

    // If no '/' found, the file is probably in the input directory
    auto pos = settings::path_cross_sections.rfind("/");
    if (pos == std::string::npos && !settings::path_input.empty()) {
      settings::path_cross_sections =
        settings::path_input + "/" + settings::path_cross_sections;
    }
  }

  // Now that the cross_sections.xml or mgxs.h5 has been located, read it in
  if (settings::run_CE) {
    read_ce_cross_sections_xml();
  } else {
    data::mg.read_header(settings::path_cross_sections);
    put_mgxs_header_data_to_globals();
  }

  // Establish mapping between (type, material) and index in libraries
  int i = 0;
  for (const auto& lib : data::libraries) {
    for (const auto& name : lib.materials_) {
      LibraryKey key {lib.type_, name};
      data::library_map.insert({key, i});
    }
    ++i;
  }

  // Check that 0K nuclides are listed in the cross_sections.xml file
  for (const auto& name : settings::res_scat_nuclides) {
    LibraryKey key {Library::Type::neutron, name};
    if (data::library_map.find(key) == data::library_map.end()) {
      fatal_error("Could not find resonant scatterer " + name +
                  " in cross_sections.xml file!");
    }
  }
}

void read_ce_cross_sections(const vector<vector<double>>& nuc_temps,
  const vector<vector<double>>& thermal_temps)
{
  std::unordered_set<std::string> already_read;

  // Construct a vector of nuclide names because we haven't loaded nuclide data
  // yet, but we need to know the name of the i-th nuclide
  vector<std::string> nuclide_names(data::nuclide_map.size());
  vector<std::string> thermal_names(data::thermal_scatt_map.size());
  for (const auto& kv : data::nuclide_map) {
    nuclide_names[kv.second] = kv.first;
  }
  for (const auto& kv : data::thermal_scatt_map) {
    thermal_names[kv.second] = kv.first;
  }

  // Read cross sections
  for (const auto& mat : model::materials) {
    for (int i_nuc : mat->nuclide_) {
      // Find name of corresponding nuclide. Because we haven't actually loaded
      // data, we don't have the name available, so instead we search through
      // all key/value pairs in nuclide_map
      std::string& name = nuclide_names[i_nuc];

      // If we've already read this nuclide, skip it
      if (already_read.find(name) != already_read.end())
        continue;

      const auto& temps = nuc_temps[i_nuc];
      int err = openmc_load_nuclide(name.c_str(), temps.data(), temps.size());
      if (err < 0)
        throw std::runtime_error {openmc_err_msg};

      already_read.insert(name);
    }
  }

  // Perform final tasks -- reading S(a,b) tables, normalizing densities
  for (auto& mat : model::materials) {
    for (const auto& table : mat->thermal_tables_) {
      // Get name of S(a,b) table
      int i_table = table.index_table;
      std::string& name = thermal_names[i_table];

      if (already_read.find(name) == already_read.end()) {
        LibraryKey key {Library::Type::thermal, name};
        int idx = data::library_map[key];
        std::string& filename = data::libraries[idx].path_;

        write_message(6, "Reading {} from {}", name, filename);

        // Open file and make sure version matches
        hid_t file_id = file_open(filename, 'r');
        check_data_version(file_id);

        // Read thermal scattering data from HDF5
        hid_t group = open_group(file_id, name.c_str());
        data::thermal_scatt.push_back(
          make_unique<ThermalScattering>(group, thermal_temps[i_table]));
        close_group(group);
        file_close(file_id);

        // Add name to dictionary
        already_read.insert(name);
      }
    } // thermal_tables_

    // Finish setting up materials (normalizing densities, etc.)
    mat->finalize();
  } // materials

  if (settings::photon_transport &&
      settings::electron_treatment == ElectronTreatment::TTB) {
    // Take logarithm of energies since they are log-log interpolated
    data::ttb_e_grid = xt::log(data::ttb_e_grid);
  }

  // Show minimum/maximum temperature
  write_message(
    4, "Minimum neutron data temperature: {} K", data::temperature_min);
  write_message(
    4, "Maximum neutron data temperature: {} K", data::temperature_max);

  // If the user wants multipole, make sure we found a multipole library.
  if (settings::temperature_multipole) {
    bool mp_found = false;
    for (const auto& nuc : data::nuclides) {
      if (nuc->multipole_) {
        mp_found = true;
        break;
      }
    }
    if (mpi::master && !mp_found) {
      warning("Windowed multipole functionality is turned on, but no multipole "
              "libraries were found. Make sure that windowed multipole data is "
              "present in your cross_sections.xml file.");
    }
  }
}

void read_ce_cross_sections_xml()
{
  // Check if cross_sections.xml exists
  const auto& filename = settings::path_cross_sections;
  if (dir_exists(filename)) {
    fatal_error("OPENMC_CROSS_SECTIONS is set to a directory. "
                "It should be set to an XML file.");
  }
  if (!file_exists(filename)) {
    // Could not find cross_sections.xml file
    fatal_error("Cross sections XML file '" + filename + "' does not exist.");
  }

  write_message("Reading cross sections XML file...", 5);

  // Parse cross_sections.xml file
  pugi::xml_document doc;
  auto result = doc.load_file(filename.c_str());
  if (!result) {
    fatal_error("Error processing cross_sections.xml file.");
  }
  auto root = doc.document_element();

  std::string directory;
  if (check_for_node(root, "directory")) {
    // Copy directory information if present
    directory = get_node_value(root, "directory");
  } else {
    // If no directory is listed in cross_sections.xml, by default select the
    // directory in which the cross_sections.xml file resides

    // TODO: Use std::filesystem functionality when C++17 is adopted
    auto pos = filename.rfind("/");
    if (pos == std::string::npos) {
      // No '\\' found, so the file must be in the same directory as
      // materials.xml
      directory = settings::path_input;
    } else {
      directory = filename.substr(0, pos);
    }
  }

  for (const auto& node_library : root.children("library")) {
    data::libraries.emplace_back(node_library, directory);
  }

  // Make sure file was not empty
  if (data::libraries.empty()) {
    fatal_error(
      "No cross section libraries present in cross_sections.xml file.");
  }
}

void finalize_cross_sections()
{
  if (settings::run_mode != RunMode::PLOTTING) {
    simulation::time_read_xs.start();
    if (settings::run_CE) {
      // Determine desired temperatures for each nuclide and S(a,b) table
      double_2dvec nuc_temps(data::nuclide_map.size());
      double_2dvec thermal_temps(data::thermal_scatt_map.size());
      get_temperatures(nuc_temps, thermal_temps);

      // Read continuous-energy cross sections from HDF5
      read_ce_cross_sections(nuc_temps, thermal_temps);
    } else {
      // Create material macroscopic data for MGXS
      set_mg_interface_nuclides_and_temps();
      data::mg.init();
      mark_fissionable_mgxs_materials();
    }
    simulation::time_read_xs.stop();
  }
}

void library_clear()
{
  data::libraries.clear();
  data::library_map.clear();
}

} // namespace openmc

1	#include "openmc/cross_sections.h"
2
3	#include "openmc/capi.h"
4	#include "openmc/constants.h"
5	#include "openmc/container_util.h"
6	#include "openmc/error.h"
7	#include "openmc/file_utils.h"
8	#include "openmc/geometry_aux.h"
9	#include "openmc/hdf5_interface.h"
10	#include "openmc/material.h"
11	#include "openmc/message_passing.h"
12	#include "openmc/mgxs_interface.h"
13	#include "openmc/nuclide.h"
14	#include "openmc/photon.h"
15	#include "openmc/settings.h"
16	#include "openmc/simulation.h"
17	#include "openmc/string_utils.h"
18	#include "openmc/thermal.h"
19	#include "openmc/timer.h"
20	#include "openmc/wmp.h"
21	#include "openmc/xml_interface.h"
22
23	#include "pugixml.hpp"
24
25	#include <cstdlib> // for getenv
26	#include <unordered_set>
27
28	namespace openmc {
29
30	//==============================================================================
31	// Global variable declarations
32	//==============================================================================
33
34	namespace data {
35
36	std::map<LibraryKey, std::size_t> library_map;
37	vector<Library> libraries;
38	} // namespace data
39
40	//==============================================================================
41	// Library methods
42	//==============================================================================
43
44	Library::Library(pugi::xml_node node, const std::string& directory)	10,007,538✔
45	{
46	// Get type of library
47	if (check_for_node(node, "type")) {	10,007,538✔
48	auto type = get_node_value(node, "type");	10,007,538✔
49	if (type == "neutron") {	10,007,538✔
50	type_ = Type::neutron;	4,382,217✔
51	} else if (type == "thermal") {	5,625,321✔
52	type_ = Type::thermal;	207,564✔
53	} else if (type == "photon") {	5,417,757✔
54	type_ = Type::photon;	1,035,900✔
55	} else if (type == "wmp") {	4,381,857✔
56	type_ = Type::wmp;	4,381,857✔
57	} else {
58	fatal_error("Unrecognized library type: " + type);	×
59	}
60	} else {	10,007,538✔
61	fatal_error("Missing library type");	×
62	}
63
64	// Get list of materials
65	if (check_for_node(node, "materials")) {	10,007,538✔
66	materials_ = get_node_array<std::string>(node, "materials");	10,007,538✔
67	}
68
69	// determine path of cross section table
70	if (!check_for_node(node, "path")) {	10,007,538✔
71	fatal_error("Missing library path");	×
72	}
73	std::string path = get_node_value(node, "path");	10,007,538✔
74
75	if (starts_with(path, "/")) {	10,007,538✔
76	path_ = path;	×
77	} else if (ends_with(directory, "/")) {	10,007,538✔
78	path_ = directory + path;	×
79	} else if (!directory.empty()) {	10,007,538✔
80	path_ = directory + "/" + path;	9,984,330✔
81	} else {
82	path_ = path;	23,208✔
83	}
84
85	if (!file_exists(path_)) {	10,007,538✔
86	warning("Cross section library " + path_ + " does not exist.");	×
87	}
88	}	10,007,538✔
89
90	//==============================================================================
91	// Non-member functions
92	//==============================================================================
93
94	void read_cross_sections_xml()	3,081✔
95	{
96	pugi::xml_document doc;	3,081✔
97	std::string filename = settings::path_input + "materials.xml";	3,081✔
98	// Check if materials.xml exists
99	if (!file_exists(filename)) {	3,081✔
100	fatal_error("Material XML file '" + filename + "' does not exist.");	×
101	}
102	// Parse materials.xml file
103	doc.load_file(filename.c_str());	3,081✔
104
105	auto root = doc.document_element();	3,081✔
106
107	read_cross_sections_xml(root);	3,081✔
108	}	3,081✔
109
110	void read_cross_sections_xml(pugi::xml_node root)	12,249✔
111	{
112	// Find cross_sections.xml file -- the first place to look is the
113	// materials.xml file. If no file is found there, then we check the
114	// OPENMC_CROSS_SECTIONS environment variable
115	if (!check_for_node(root, "cross_sections")) {	12,249✔
116	// No cross_sections.xml file specified in settings.xml, check
117	// environment variable
118	if (settings::run_CE) {	10,335✔
119	char* envvar = std::getenv("OPENMC_CROSS_SECTIONS");	10,335✔
120	if (!envvar) {	10,335✔
121	fatal_error(	×
122	"No cross_sections.xml file was specified in "
123	"materials.xml or in the OPENMC_CROSS_SECTIONS"
124	" environment variable. OpenMC needs such a file to identify "
125	"where to find data libraries. Please consult the"
126	" user's guide at https://docs.openmc.org/ for "
127	"information on how to set up data libraries.");
128	}
129	settings::path_cross_sections = envvar;	10,335✔
130	} else {
131	char* envvar = std::getenv("OPENMC_MG_CROSS_SECTIONS");	×
132	if (!envvar) {	×
133	fatal_error(	×
134	"No mgxs.h5 file was specified in "
135	"materials.xml or in the OPENMC_MG_CROSS_SECTIONS environment "
136	"variable. OpenMC needs such a file to identify where to "
137	"find MG cross section libraries. Please consult the user's "
138	"guide at https://docs.openmc.org for information on "
139	"how to set up MG cross section libraries.");
140	}
141	settings::path_cross_sections = envvar;	×
142	}
143	} else {
144	settings::path_cross_sections = get_node_value(root, "cross_sections");	1,914✔
145
146	// If no '/' found, the file is probably in the input directory
147	auto pos = settings::path_cross_sections.rfind("/");	1,914✔
148	if (pos == std::string::npos && !settings::path_input.empty()) {	1,914✔
149	settings::path_cross_sections =
150	settings::path_input + "/" + settings::path_cross_sections;	×
151	}
152	}
153
154	// Now that the cross_sections.xml or mgxs.h5 has been located, read it in
155	if (settings::run_CE) {	12,249✔
156	read_ce_cross_sections_xml();	10,719✔
157	} else {
158	data::mg.read_header(settings::path_cross_sections);	1,530✔
159	put_mgxs_header_data_to_globals();	1,530✔
160	}
161
162	// Establish mapping between (type, material) and index in libraries
163	int i = 0;	12,249✔
164	for (const auto& lib : data::libraries) {	10,023,629✔
165	for (const auto& name : lib.materials_) {	20,022,760✔
166	LibraryKey key {lib.type_, name};	10,011,380✔
167	data::library_map.insert({key, i});	10,011,380✔
168	}	10,011,380✔
169	++i;	10,011,380✔
170	}
171
172	// Check that 0K nuclides are listed in the cross_sections.xml file
173	for (const auto& name : settings::res_scat_nuclides) {	12,351✔
174	LibraryKey key {Library::Type::neutron, name};	102✔
175	if (data::library_map.find(key) == data::library_map.end()) {	102✔
176	fatal_error("Could not find resonant scatterer " + name +	×
177	" in cross_sections.xml file!");
178	}
179	}	102✔
180	}	12,249✔
181
182	void read_ce_cross_sections(const vector<vector<double>>& nuc_temps,	10,719✔
183	const vector<vector<double>>& thermal_temps)
184	{
185	std::unordered_set<std::string> already_read;	10,719✔
186
187	// Construct a vector of nuclide names because we haven't loaded nuclide data
188	// yet, but we need to know the name of the i-th nuclide
189	vector<std::string> nuclide_names(data::nuclide_map.size());	10,719✔
190	vector<std::string> thermal_names(data::thermal_scatt_map.size());	10,719✔
191	for (const auto& kv : data::nuclide_map) {	64,371✔
192	nuclide_names[kv.second] = kv.first;	53,652✔
193	}
194	for (const auto& kv : data::thermal_scatt_map) {	12,932✔
195	thermal_names[kv.second] = kv.first;	2,213✔
196	}
197
198	// Read cross sections
199	for (const auto& mat : model::materials) {	35,103✔
200	for (int i_nuc : mat->nuclide_) {	140,068✔
201	// Find name of corresponding nuclide. Because we haven't actually loaded
202	// data, we don't have the name available, so instead we search through
203	// all key/value pairs in nuclide_map
204	std::string& name = nuclide_names[i_nuc];	115,684✔
205
206	// If we've already read this nuclide, skip it
207	if (already_read.find(name) != already_read.end())	115,684✔
208	continue;	62,032✔
209
210	const auto& temps = nuc_temps[i_nuc];	53,652✔
211	int err = openmc_load_nuclide(name.c_str(), temps.data(), temps.size());	53,652✔
212	if (err < 0)	53,652✔
213	throw std::runtime_error {openmc_err_msg};	×
214
215	already_read.insert(name);	53,652✔
216	}
217	}
218
219	// Perform final tasks -- reading S(a,b) tables, normalizing densities
220	for (auto& mat : model::materials) {	35,103✔
221	for (const auto& table : mat->thermal_tables_) {	28,128✔
222	// Get name of S(a,b) table
223	int i_table = table.index_table;	3,744✔
224	std::string& name = thermal_names[i_table];	3,744✔
225
226	if (already_read.find(name) == already_read.end()) {	3,744✔
227	LibraryKey key {Library::Type::thermal, name};	2,213✔
228	int idx = data::library_map[key];	2,213✔
229	std::string& filename = data::libraries[idx].path_;	2,213✔
230
231	write_message(6, "Reading {} from {}", name, filename);	2,213✔
232
233	// Open file and make sure version matches
234	hid_t file_id = file_open(filename, 'r');	2,213✔
235	check_data_version(file_id);	2,213✔
236
237	// Read thermal scattering data from HDF5
238	hid_t group = open_group(file_id, name.c_str());	2,213✔
239	data::thermal_scatt.push_back(	2,213✔
240	make_unique<ThermalScattering>(group, thermal_temps[i_table]));	4,426✔
241	close_group(group);	2,213✔
242	file_close(file_id);	2,213✔
243
244	// Add name to dictionary
245	already_read.insert(name);	2,213✔
246	}	2,213✔
247	} // thermal_tables_
248
249	// Finish setting up materials (normalizing densities, etc.)
250	mat->finalize();	24,384✔
251	} // materials
252
253	if (settings::photon_transport &&	10,719✔
254	settings::electron_treatment == ElectronTreatment::TTB) {	508✔
255	// Take logarithm of energies since they are log-log interpolated
256	data::ttb_e_grid = xt::log(data::ttb_e_grid);	484✔
257	}
258
259	// Show minimum/maximum temperature
260	write_message(	10,719✔
261	4, "Minimum neutron data temperature: {} K", data::temperature_min);
262	write_message(	10,719✔
263	4, "Maximum neutron data temperature: {} K", data::temperature_max);
264
265	// If the user wants multipole, make sure we found a multipole library.
266	if (settings::temperature_multipole) {	10,719✔
267	bool mp_found = false;	68✔
268	for (const auto& nuc : data::nuclides) {	68✔
269	if (nuc->multipole_) {	68✔
270	mp_found = true;	68✔
271	break;	68✔
272	}
273	}
274	if (mpi::master && !mp_found) {	68✔
275	warning("Windowed multipole functionality is turned on, but no multipole "	×
276	"libraries were found. Make sure that windowed multipole data is "
277	"present in your cross_sections.xml file.");
278	}
279	}
280	}	10,719✔
281
282	void read_ce_cross_sections_xml()	10,719✔
283	{
284	// Check if cross_sections.xml exists
285	const auto& filename = settings::path_cross_sections;	10,719✔
286	if (dir_exists(filename)) {	10,719✔
287	fatal_error("OPENMC_CROSS_SECTIONS is set to a directory. "	×
288	"It should be set to an XML file.");
289	}
290	if (!file_exists(filename)) {	10,719✔
291	// Could not find cross_sections.xml file
292	fatal_error("Cross sections XML file '" + filename + "' does not exist.");	×
293	}
294
295	write_message("Reading cross sections XML file...", 5);	10,719✔
296
297	// Parse cross_sections.xml file
298	pugi::xml_document doc;	10,719✔
299	auto result = doc.load_file(filename.c_str());	10,719✔
300	if (!result) {	10,719✔
301	fatal_error("Error processing cross_sections.xml file.");	×
302	}
303	auto root = doc.document_element();	10,719✔
304
305	std::string directory;	10,719✔
306	if (check_for_node(root, "directory")) {	10,719✔
307	// Copy directory information if present
308	directory = get_node_value(root, "directory");	×
309	} else {
310	// If no directory is listed in cross_sections.xml, by default select the
311	// directory in which the cross_sections.xml file resides
312
313	// TODO: Use std::filesystem functionality when C++17 is adopted
314	auto pos = filename.rfind("/");	10,719✔
315	if (pos == std::string::npos) {	10,719✔
316	// No '\\' found, so the file must be in the same directory as
317	// materials.xml
318	directory = settings::path_input;	24✔
319	} else {
320	directory = filename.substr(0, pos);	10,695✔
321	}
322	}
323
324	for (const auto& node_library : root.children("library")) {	10,018,257✔
325	data::libraries.emplace_back(node_library, directory);	10,007,538✔
326	}
327
328	// Make sure file was not empty
329	if (data::libraries.empty()) {	10,719✔
330	fatal_error(	×
331	"No cross section libraries present in cross_sections.xml file.");
332	}
333	}	10,719✔
334
335	void finalize_cross_sections()	12,725✔
336	{
337	if (settings::run_mode != RunMode::PLOTTING) {	12,725✔
338	simulation::time_read_xs.start();	12,249✔
339	if (settings::run_CE) {	12,249✔
340	// Determine desired temperatures for each nuclide and S(a,b) table
341	double_2dvec nuc_temps(data::nuclide_map.size());	10,719✔
342	double_2dvec thermal_temps(data::thermal_scatt_map.size());	10,719✔
343	get_temperatures(nuc_temps, thermal_temps);	10,719✔
344
345	// Read continuous-energy cross sections from HDF5
346	read_ce_cross_sections(nuc_temps, thermal_temps);	10,719✔
347	} else {	10,719✔
348	// Create material macroscopic data for MGXS
349	set_mg_interface_nuclides_and_temps();	1,530✔
350	data::mg.init();	1,530✔
351	mark_fissionable_mgxs_materials();	1,530✔
352	}
353	simulation::time_read_xs.stop();	12,249✔
354	}
355	}	12,725✔
356
357	void library_clear()	12,928✔
358	{
359	data::libraries.clear();	12,928✔
360	data::library_map.clear();	12,928✔
361	}	12,928✔
362
363	} // namespace openmc

openmc-dev / openmc / 10424279536

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