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https://github.com/openmc-dev/openmc.git
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0169fd9226
Co-authored-by: John Tramm <jtramm@gmail.com> Co-authored-by: Claude Opus 4.6 <noreply@anthropic.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com> Co-authored-by: Copilot <copilot@github.com>
130 lines
4.5 KiB
C++
130 lines
4.5 KiB
C++
//! \file simulation.h
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//! \brief Variables/functions related to a running simulation
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#ifndef OPENMC_SIMULATION_H
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#define OPENMC_SIMULATION_H
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#include "openmc/mesh.h"
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#include "openmc/particle.h"
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#include "openmc/vector.h"
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#include <cstdint>
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namespace openmc {
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constexpr int STATUS_EXIT_NORMAL {0};
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constexpr int STATUS_EXIT_MAX_BATCH {1};
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constexpr int STATUS_EXIT_ON_TRIGGER {2};
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//==============================================================================
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// Global variable declarations
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//==============================================================================
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namespace simulation {
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extern int ct_current_file; //!< current collision track file index
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extern "C" int current_batch; //!< current batch
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extern "C" int current_gen; //!< current fission generation
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extern "C" bool initialized; //!< has simulation been initialized?
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extern "C" double keff; //!< average k over batches
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extern "C" double keff_std; //!< standard deviation of average k
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extern "C" double k_col_abs; //!< sum over batches of k_collision * k_absorption
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extern "C" double
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k_col_tra; //!< sum over batches of k_collision * k_tracklength
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extern "C" double
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k_abs_tra; //!< sum over batches of k_absorption * k_tracklength
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extern double log_spacing; //!< lethargy spacing for energy grid searches
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extern "C" int n_lost_particles; //!< cumulative number of lost particles
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extern "C" bool need_depletion_rx; //!< need to calculate depletion rx?
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extern "C" int restart_batch; //!< batch at which a restart job resumed
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extern "C" bool satisfy_triggers; //!< have tally triggers been satisfied?
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extern int ssw_current_file; //!< current surface source file
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extern "C" int total_gen; //!< total number of generations simulated
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extern double total_weight; //!< Total source weight in a batch
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extern int64_t work_per_rank; //!< number of particles per MPI rank
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extern const RegularMesh* entropy_mesh;
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extern const RegularMesh* ufs_mesh;
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extern vector<double> k_generation;
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extern vector<int64_t> work_index;
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extern int64_t
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simulation_tracks_completed; //!< Number of tracks completed on this rank
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} // namespace simulation
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//==============================================================================
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// Functions
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//==============================================================================
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//! Allocate space for source and fission banks
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void allocate_banks();
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//! Determine number of particles to transport per process
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void calculate_work(int64_t n_particles);
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//! Initialize nuclear data before a simulation
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void initialize_data();
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//! Initialize a batch
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void initialize_batch();
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//! Initialize a fission generation
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void initialize_generation();
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//! Full initialization of a particle track
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void initialize_particle_track(
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Particle& p, int64_t index_source, bool is_secondary);
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//! Finalize a batch
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//!
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//! Handles synchronization and accumulation of tallies, calculation of Shannon
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//! entropy, getting single-batch estimate of keff, and turning on tallies when
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//! appropriate
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void finalize_batch();
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//! Finalize a fission generation
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void finalize_generation();
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//! Determine overall generation number
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extern "C" int overall_generation();
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#ifdef OPENMC_MPI
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void broadcast_results();
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#endif
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void free_memory_simulation();
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//! Compute unique particle ID from a 1-based source index
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//! \param index_source 1-based source index within this rank's work
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//! \return globally unique particle ID
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int64_t compute_particle_id(int64_t index_source);
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//! Compute the transport RNG seed from a particle ID
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//! \param particle_id the particle's globally unique ID
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//! \return seed value passed to init_particle_seeds()
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int64_t compute_transport_seed(int64_t particle_id);
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//! Simulate a single particle history from birth to death, inclusive of any
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//! secondary particles. In shared secondary mode, only a single track is
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//! transported and secondaries are deposited into a shared bank instead.
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void transport_history_based_single_particle(Particle& p);
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//! Simulate all particle histories using history-based parallelism
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void transport_history_based();
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//! Simulate all particles using history-based parallelism, with a shared
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//! secondary bank
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void transport_history_based_shared_secondary();
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//! Simulate all particle histories using event-based parallelism
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void transport_event_based();
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//! Simulate all particles using event-based parallelism, with a shared
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//! secondary bank
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void transport_event_based_shared_secondary();
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} // namespace openmc
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#endif // OPENMC_SIMULATION_H
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