openmc.Settings

class openmc.Settings

Settings used for an OpenMC simulation.

Variables:

• batches (int) – Number of batches to simulate
• confidence_intervals (bool) – If True, uncertainties on tally results will be reported as the half-width of the 95% two-sided confidence interval. If False, uncertainties on tally results will be reported as the sample standard deviation.
• create_fission_neutrons (bool) – Indicate whether fission neutrons should be created or not.
• cutoff (dict) – Dictionary defining weight cutoff and energy cutoff. The dictionary may have six keys, ‘weight’, ‘weight_avg’, ‘energy_neutron’, ‘energy_photon’, ‘energy_electron’, and ‘energy_positron’. Value for ‘weight’ should be a float indicating weight cutoff below which particle undergo Russian roulette. Value for ‘weight_avg’ should be a float indicating weight assigned to particles that are not killed after Russian roulette. Value of energy should be a float indicating energy in eV below which particle type will be killed.
• dagmc (bool) – Indicate that a CAD-based DAGMC geometry will be used.
• delayed_photon_scaling (bool) –

  Indicate whether to scale the fission photon yield by (EGP + EGD)/EGP where EGP is the energy release of prompt photons and EGD is the energy release of delayed photons.

  New in version 0.12.

• electron_treatment ({'led', 'ttb'}) – Whether to deposit all energy from electrons locally (‘led’) or create secondary bremsstrahlung photons (‘ttb’).
• energy_mode ({'continuous-energy', 'multi-group'}) – Set whether the calculation should be continuous-energy or multi-group.
• entropy_mesh (openmc.RegularMesh) – Mesh to be used to calculate Shannon entropy. If the mesh dimensions are not specified, OpenMC assigns a mesh such that 20 source sites per mesh cell are to be expected on average.
• event_based (bool) –

  Indicate whether to use event-based parallelism instead of the default history-based parallelism.

  New in version 0.12.

• generations_per_batch (int) – Number of generations per batch
• max_lost_particles (int) –

  Maximum number of lost particles

  New in version 0.12.

• rel_max_lost_particles (int) –

  Maximum number of lost particles, relative to the total number of particles

  New in version 0.12.

• inactive (int) – Number of inactive batches
• keff_trigger (dict) – Dictionary defining a trigger on eigenvalue. The dictionary must have two keys, ‘type’ and ‘threshold’. Acceptable values corresponding to type are ‘variance’, ‘std_dev’, and ‘rel_err’. The threshold value should be a float indicating the variance, standard deviation, or relative error used.
• log_grid_bins (int) – Number of bins for logarithmic energy grid search
• material_cell_offsets (bool) –

  Generate an “offset table” for material cells by default. These tables are necessary when a particular instance of a cell needs to be tallied.

  New in version 0.12.

• max_particles_in_flight (int) –

  Number of neutrons to run concurrently when using event-based parallelism.

  New in version 0.12.

• max_order (None or int) – Maximum scattering order to apply globally when in multi-group mode.
• no_reduce (bool) – Indicate that all user-defined and global tallies should not be reduced across processes in a parallel calculation.
• output (dict) –

  Dictionary indicating what files to output. Acceptable keys are:

  path:String indicating a directory where output files should be written summary:Whether the ‘summary.h5’ file should be written (bool) tallies:Whether the ‘tallies.out’ file should be written (bool)
• particles (int) – Number of particles per generation
• photon_transport (bool) – Whether to use photon transport.
• ptables (bool) – Determine whether probability tables are used.
• resonance_scattering (dict) – Settings for resonance elastic scattering. Accepted keys are ‘enable’ (bool), ‘method’ (str), ‘energy_min’ (float), ‘energy_max’ (float), and ‘nuclides’ (list). The ‘method’ can be set to ‘dbrc’ (Doppler broadening rejection correction) or ‘rvs’ (relative velocity sampling). If not specified, ‘rvs’ is the default method. The ‘energy_min’ and ‘energy_max’ values indicate the minimum and maximum energies above and below which the resonance elastic scattering method is to be applied. The ‘nuclides’ list indicates what nuclides the method should be applied to. In its absence, the method will be applied to all nuclides with 0 K elastic scattering data present.
• run_mode ({'eigenvalue', 'fixed source', 'plot', 'volume', 'particle restart'}) – The type of calculation to perform (default is ‘eigenvalue’)
• seed (int) – Seed for the linear congruential pseudorandom number generator
• source (Iterable of openmc.Source) – Distribution of source sites in space, angle, and energy
• sourcepoint (dict) –

  Options for writing source points. Acceptable keys are:

  batches:list of batches at which to write source overwrite:bool indicating whether to overwrite separate:bool indicating whether the source should be written as a separate file write:bool indicating whether or not to write the source
• statepoint (dict) –

  Options for writing state points. Acceptable keys are:

  batches:list of batches at which to write source
• surf_source_read (dict) –

  Options for reading surface source points. Acceptable keys are:

  path:Path to surface source file (str).
• surf_source_write (dict) –

  Options for writing surface source points. Acceptable keys are:

  surface_ids:List of surface ids at which crossing particles are to be banked (int) max_particles:Maximum number of particles to be banked on surfaces per process (int)
• survival_biasing (bool) – Indicate whether survival biasing is to be used
• tabular_legendre (dict) – Determines if a multi-group scattering moment kernel expanded via Legendre polynomials is to be converted to a tabular distribution or not. Accepted keys are ‘enable’ and ‘num_points’. The value for ‘enable’ is a bool stating whether the conversion to tabular is performed; the value for ‘num_points’ sets the number of points to use in the tabular distribution, should ‘enable’ be True.
• temperature (dict) – Defines a default temperature and method for treating intermediate temperatures at which nuclear data doesn’t exist. Accepted keys are ‘default’, ‘method’, ‘range’, ‘tolerance’, and ‘multipole’. The value for ‘default’ should be a float representing the default temperature in Kelvin. The value for ‘method’ should be ‘nearest’ or ‘interpolation’. If the method is ‘nearest’, ‘tolerance’ indicates a range of temperature within which cross sections may be used. The value for ‘range’ should be a pair a minimum and maximum temperatures which are used to indicate that cross sections be loaded at all temperatures within the range. ‘multipole’ is a boolean indicating whether or not the windowed multipole method should be used to evaluate resolved resonance cross sections.
• trace (tuple or list) – Show detailed information about a single particle, indicated by three integers: the batch number, generation number, and particle number
• track (tuple or list) – Specify particles for which track files should be written. Each particle is identified by a triplet with the batch number, generation number, and particle number.
• trigger_active (bool) – Indicate whether tally triggers are used
• trigger_batch_interval (int) – Number of batches in between convergence checks
• trigger_max_batches (int) – Maximum number of batches simulated. If this is set, the number of batches specified via batches is interpreted as the minimum number of batches
• ufs_mesh (openmc.RegularMesh) – Mesh to be used for redistributing source sites via the uniform fision site (UFS) method.
• verbosity (int) – Verbosity during simulation between 1 and 10. Verbosity levels are described in <verbosity> Element.
• volume_calculations (VolumeCalculation or iterable of VolumeCalculation) – Stochastic volume calculation specifications

export_to_xml(path='settings.xml')

Export simulation settings to an XML file.

Parameters:path (str) – Path to file to write. Defaults to ‘settings.xml’.

classmethod from_xml(path='settings.xml')

Generate settings from XML file

Parameters:path (str, optional) – Path to settings XML file Returns:Settings object Return type:openmc.Settings