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https://github.com/openmc-dev/openmc.git
synced 2026-07-28 06:05:58 -04:00
Merge branch 'mcpl_output_dev' into mcpl_input
This commit is contained in:
commit
cb82616ebf
9 changed files with 210 additions and 19 deletions
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@ -159,6 +159,13 @@ if(${HDF5_VERSION} VERSION_GREATER_EQUAL 1.12.0)
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list(APPEND cxxflags -DH5Oget_info_by_idx_vers=1 -DH5O_info_t_vers=1)
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endif()
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#===============================================================================
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# MCPL
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#===============================================================================
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if (OPENMC_USE_MCPL)
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find_package(MCPL REQUIRED)
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endif()
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#===============================================================================
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# Set compile/link flags based on which compiler is being used
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#===============================================================================
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@ -186,10 +193,6 @@ if(OPENMC_ENABLE_COVERAGE)
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list(APPEND ldflags --coverage)
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endif()
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if(OPENMC_USE_MCPL)
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list(APPEND ldflags -lmcpl)
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endif()
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# Show flags being used
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message(STATUS "OpenMC C++ flags: ${cxxflags}")
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message(STATUS "OpenMC Linker flags: ${ldflags}")
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@ -444,10 +447,6 @@ endif()
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if (OPENMC_USE_MPI)
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target_compile_definitions(libopenmc PUBLIC -DOPENMC_MPI)
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endif()
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if(OPENMC_USE_MCPL)
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target_compile_definitions(libopenmc PUBLIC -DOPENMC_MCPL)
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endif()
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# Set git SHA1 hash as a compile definition
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if(GIT_FOUND)
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@ -491,6 +490,11 @@ if (OPENMC_USE_MPI)
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target_link_libraries(libopenmc MPI::MPI_CXX)
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endif()
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if (OPENMC_USE_MCPL)
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target_compile_definitions(libopenmc PUBLIC OPENMC_MCPL)
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target_link_libraries(libopenmc MCPL::mcpl)
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endif()
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#===============================================================================
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# openmc executable
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#===============================================================================
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@ -48,6 +48,7 @@ extern bool source_latest; //!< write latest source at each batch?
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extern bool source_separate; //!< write source to separate file?
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extern bool source_write; //!< write source in HDF5 files?
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extern bool surf_source_write; //!< write surface source file?
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extern bool surf_mcpl_write; //!< write surface mcpl file?
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extern bool surf_source_read; //!< read surface source file?
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extern bool survival_biasing; //!< use survival biasing?
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extern bool temperature_multipole; //!< use multipole data?
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@ -9,6 +9,10 @@
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#include "openmc/particle.h"
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#include "openmc/vector.h"
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#ifdef OPENMC_MCPL
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#include <mcpl.h>
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#endif
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namespace openmc {
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void load_state_point();
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@ -21,5 +25,10 @@ void write_tally_results_nr(hid_t file_id);
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void restart_set_keff();
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void write_unstructured_mesh_results();
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#ifdef OPENMC_MCPL
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void write_mcpl_source_point(const char *filename_, bool surf_source_bank = false);
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void write_mcpl_source_bank(mcpl_outfile_t file_id, bool surf_source_bank);
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#endif
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} // namespace openmc
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#endif // OPENMC_STATE_POINT_H
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@ -171,6 +171,7 @@ class Settings:
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banked (int)
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:max_particles: Maximum number of particles to be banked on
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surfaces per process (int)
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:mcpl: Output in the form of an MCPL-file (bool)
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survival_biasing : bool
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Indicate whether survival biasing is to be used
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tabular_legendre : dict
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@ -652,7 +653,7 @@ class Settings:
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cv.check_type('surface source writing options', surf_source_write, Mapping)
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for key, value in surf_source_write.items():
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cv.check_value('surface source writing key', key,
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('surface_ids', 'max_particles'))
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('surface_ids', 'max_particles', 'mcpl'))
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if key == 'surface_ids':
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cv.check_type('surface ids for source banking', value,
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Iterable, Integral)
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@ -664,6 +665,9 @@ class Settings:
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value, Integral)
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cv.check_greater_than('maximum particle banks on surfaces per process',
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value, 0)
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elif key == 'mcpl':
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cv.check_type('write to an MCPL-format file', value, bool)
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self._surf_source_write = surf_source_write
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@confidence_intervals.setter
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@ -1032,6 +1036,9 @@ class Settings:
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if 'max_particles' in self._surf_source_write:
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subelement = ET.SubElement(element, "max_particles")
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subelement.text = str(self._surf_source_write['max_particles'])
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if 'mcpl' in self._surf_source_write:
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subelement = ET.SubElement(element, "mcpl")
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subelement.text = str(self._surf_source_write['mcpl']).lower()
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def _create_confidence_intervals(self, root):
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if self._confidence_intervals is not None:
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@ -223,7 +223,10 @@ class Source:
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if self.particle != 'neutron':
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element.set("particle", self.particle)
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if self.file is not None:
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element.set("file", self.file)
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if (self.file.endswith('.mcpl')):
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element.set("mcpl", self.file)
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else:
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element.set("file", self.file)
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if self.library is not None:
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element.set("library", self.library)
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if self.parameters is not None:
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@ -61,6 +61,7 @@ bool source_latest {false};
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bool source_separate {false};
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bool source_write {true};
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bool surf_source_write {false};
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bool surf_mcpl_write {false};
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bool surf_source_read {false};
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bool survival_biasing {false};
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bool temperature_multipole {false};
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@ -682,9 +683,14 @@ void read_settings_xml()
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max_surface_particles =
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std::stoll(get_node_value(node_ssw, "max_particles"));
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}
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#ifdef OPENMC_MCPL
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if(check_for_node(node_ssw, "mcpl")){
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surf_mcpl_write=true;
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}
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#endif
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}
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// If source is not seperate and is to be written out in the statepoint file,
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// If source is not separate and is to be written out in the statepoint file,
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// make sure that the sourcepoint batch numbers are contained in the
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// statepoint list
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if (!source_separate) {
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@ -407,6 +407,13 @@ void finalize_batch()
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auto filename = settings::path_output + "surface_source.h5";
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write_source_point(filename.c_str(), true);
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}
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#ifdef OPENMC_MCPL
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if(settings::surf_mcpl_write && simulation::current_batch == settings::n_batches){
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auto filename = settings::path_output + "surface_source.mcpl";
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write_mcpl_source_point(filename.c_str(), true);
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}
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#endif
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}
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void initialize_generation()
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@ -343,17 +343,28 @@ FileSource::FileSource(mcpl_file_t mcpl_file)
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const mcpl_particle_t *mcpl_particle;
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//extract particle from mcpl-file
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mcpl_particle=mcpl_read(mcpl_file);
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// check if it is a neutron or a photon. otherwise skip
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while ( mcpl_particle->pdgcode!=2112 && mcpl_particle->pdgcode!=22 ) {
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// check if it is a neutron, photon, electron, or positron. Otherwise skip.
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int pdg=mcpl_particle->pdgcode;
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while ( pdg!=2112 && pdg!=22 && pdg!=11 && pdg!=-11) {
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mcpl_particle=mcpl_read(mcpl_file);
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//should check for file exhaustion This could happen if particles are other than
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//neutrons or photons
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pdg=mcpl_particle->pdgcode;
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//should check for file exhaustion. This could happen if particles are other than
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//neutrons, photons, electrons, or positrons.
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}
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if(mcpl_particle->pdgcode==2112) {
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site_.particle=ParticleType::neutron;
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} else if (mcpl_particle->pdgcode==22) {
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site_.particle=ParticleType::photon;
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switch(pdg){
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case 2112:
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site_.particle=ParticleType::neutron;
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break;
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case 22:
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site_.particle=ParticleType::photon;
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break;
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case 11:
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site_.particle=ParticleType::electron;
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break;
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case -11:
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site_.particle=ParticleType::positron;
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break;
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}
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//particle is good, convert to openmc-formalism
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@ -28,6 +28,10 @@
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#include "openmc/timer.h"
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#include "openmc/vector.h"
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#ifdef OPENMC_MCPL
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#include <mcpl.h>
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#endif
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namespace openmc {
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extern "C" int openmc_statepoint_write(const char* filename, bool* write_source)
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@ -599,6 +603,46 @@ void write_source_point(const char* filename, bool surf_source_bank)
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file_close(file_id);
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}
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#ifdef OPENMC_MCPL
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void write_mcpl_source_point(const char *filename, bool surf_source_bank)
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{
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std::string filename_;
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if (filename) {
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filename_ = filename;
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} else {
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// Determine width for zero padding
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int w = std::to_string(settings::n_max_batches).size();
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filename_ = fmt::format("{0}source.{1:0{2}}.mcpl", settings::path_output,
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simulation::current_batch, w);
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}
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mcpl_outfile_t file_id;
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std::string line;
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if (mpi::master) {
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// this must be rewritten: file_open is h5-specific
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file_id = mcpl_create_outfile(filename_.c_str());
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//write_attribute(file_id, "filetype", "source");
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//write header stuff (oopy in xml-files as binary blobs for instance))
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if (VERSION_DEV){
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line=fmt::format("OpenMC {0}.{1}.{2}-development",VERSION_MAJOR,VERSION_MINOR,VERSION_RELEASE);
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} else {
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line=fmt::format("OpenMC {0}.{1}.{2}",VERSION_MAJOR,VERSION_MINOR,VERSION_RELEASE);
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}
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mcpl_hdr_set_srcname(file_id,line.c_str());
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}
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write_mcpl_source_bank(file_id, surf_source_bank);
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if (mpi::master) {
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//change this - this is h5 specific
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mcpl_closeandgzip_outfile(file_id);
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}
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}
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#endif
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void write_source_bank(hid_t group_id, bool surf_source_bank)
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{
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hid_t banktype = h5banktype();
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@ -715,6 +759,105 @@ void write_source_bank(hid_t group_id, bool surf_source_bank)
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H5Tclose(banktype);
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}
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#ifdef OPENMC_MCPL
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void write_mcpl_source_bank(mcpl_outfile_t file_id, bool surf_source_bank)
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{
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int64_t dims_size = settings::n_particles;
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int64_t count_size = simulation::work_per_rank;
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// Set vectors for source bank and starting bank index of each process
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vector<int64_t>* bank_index = &simulation::work_index;
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vector<SourceSite>* source_bank = &simulation::source_bank;
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vector<int64_t> surf_source_index_vector;
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vector<SourceSite> surf_source_bank_vector;
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if(surf_source_bank) {
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surf_source_index_vector = calculate_surf_source_size();
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dims_size = surf_source_index_vector[mpi::n_procs];
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count_size = simulation::surf_source_bank.size();
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bank_index = &surf_source_index_vector;
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// Copy data in a SharedArray into a vector.
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surf_source_bank_vector.resize(count_size);
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surf_source_bank_vector.assign(simulation::surf_source_bank.data(),
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simulation::surf_source_bank.data() + count_size);
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source_bank = &surf_source_bank_vector;
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}
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if (mpi::master) {
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// Particles are writeen to disk from the master node only
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// Save source bank sites since the array is overwritten below
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#ifdef OPENMC_MPI
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vector<SourceSite> temp_source {source_bank->begin(), source_bank->end()};
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#endif
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//loop over the other nodes and receive data - then write those.
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for (int i = 0; i < mpi::n_procs; ++i) {
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// number of particles for node node i
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size_t count[] {
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static_cast<size_t>((*bank_index)[i + 1] - (*bank_index)[i])};
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#ifdef OPENMC_MPI
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if (i>0)
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MPI_Recv(source_bank->data(), count[0], mpi::source_site, i, i,
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mpi::intracomm, MPI_STATUS_IGNORE);
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#endif
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// now write the source_bank data again.
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for (vector<SourceSite>::iterator _site=source_bank->begin(); _site!=source_bank->end();_site++){
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// particle is now at the iterator
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// write it to the mcpl-file
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mcpl_particle_t p;
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p.position[0]=_site->r.x;
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p.position[1]=_site->r.y;
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p.position[2]=_site->r.z;
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// mcpl requires that the direction vector is unit length
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// which is also the case in openmc
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p.direction[0]=_site->u.x;
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p.direction[1]=_site->u.y;
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p.direction[2]=_site->u.z;
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// mcpl stores kinetic energy in MeV
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p.ekin=_site->E*1e-6;
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p.time=_site->time*1e3;
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p.weight=_site->wgt;
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switch(_site->particle){
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case ParticleType::neutron:
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p.pdgcode=2112;
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break;
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case ParticleType::photon:
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p.pdgcode=22;
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break;
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case ParticleType::electron:
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p.pdgcode=11;
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break;
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case ParticleType::positron:
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p.pdgcode=-11;
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break;
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}
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mcpl_add_particle(file_id,&p);
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}
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}
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#ifdef OPENMC_MPI
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// Restore state of source bank
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std::copy(temp_source.begin(), temp_source.end(), source_bank->begin());
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#endif
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} else {
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#ifdef OPENMC_MPI
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MPI_Send(source_bank->data(), count_size, mpi::source_site, 0, mpi::rank,
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mpi::intracomm);
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#endif
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}
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}
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#endif
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// Determine member names of a compound HDF5 datatype
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std::string dtype_member_names(hid_t dtype_id)
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{
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||||
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