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Reorder attributes in Settings docstring
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1 changed files with 68 additions and 68 deletions
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@ -17,49 +17,15 @@ class Settings(object):
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Attributes
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----------
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run_mode : {'eigenvalue' or 'fixed source'}
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The type of calculation to perform (default is 'eigenvalue')
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batches : int
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Number of batches to simulate
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generations_per_batch : int
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Number of generations per batch
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inactive : int
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Number of inactive batches
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particles : int
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Number of particles per generation
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keff_trigger : dict
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Dictionary defining a trigger on eigenvalue. The dictionary must have
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two keys, 'type' and 'threshold'. Acceptable values corresponding to
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type are 'variance', 'std_dev', and 'rel_err'. The threshold value
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should be a float indicating the variance, standard deviation, or
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relative error used.
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source : Iterable of openmc.Source
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Distribution of source sites in space, angle, and energy
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output : dict
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Dictionary indicating what files to output. Valid keys are 'summary',
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'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
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each key should be given as a boolean value.
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output_path : str
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Path to write output to
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verbosity : int
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Verbosity during simulation between 1 and 10
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statepoint : dict
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Options for writing state points. Acceptable keys are:
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:batches: list of batches at which to write source
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sourcepoint : dict
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Options for writing source points. Acceptable keys are:
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:batches: list of batches at which to write source
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:overwrite: bool indicating whether to overwrite
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:separate: bool indicating whether the source should be written as a
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separate file
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:write: bool indicating whether or not to write the source
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confidence_intervals : bool
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If True, uncertainties on tally results will be reported as the
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half-width of the 95% two-sided confidence interval. If False,
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uncertainties on tally results will be reported as the sample standard
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deviation.
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create_fission_neutrons : bool
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Indicate whether fission neutrons should be created or not.
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cross_sections : str
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Indicates the path to an XML cross section listing file (usually named
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cross_sections.xml). If it is not set, the
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@ -67,23 +33,6 @@ class Settings(object):
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continuous-energy calculations and
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:envvar:`OPENMC_MG_CROSS_SECTIONS` will be used for multi-group
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calculations to find the path to the XML cross section file.
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multipole_library : str
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Indicates the path to a directory containing a windowed multipole
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cross section library. If it is not set, the
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:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
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multipole library is optional.
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energy_mode : {'continuous-energy', 'multi-group'}
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Set whether the calculation should be continuous-energy or multi-group.
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max_order : int
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Maximum scattering order to apply globally when in multi-group mode.
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ptables : bool
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Determine whether probability tables are used.
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run_cmfd : bool
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Indicate if coarse mesh finite difference acceleration is to be used
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seed : int
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Seed for the linear congruential pseudorandom number generator
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survival_biasing : bool
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Indicate whether survival biasing is to be used
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cutoff : dict
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Dictionary defining weight cutoff and energy cutoff. The dictionary may
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have three keys, 'weight', 'weight_avg' and 'energy'. Value for 'weight'
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@ -92,6 +41,8 @@ class Settings(object):
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weight assigned to particles that are not killed after Russian
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roulette. Value of energy should be a float indicating energy in eV
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below which particle will be killed.
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energy_mode : {'continuous-energy', 'multi-group'}
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Set whether the calculation should be continuous-energy or multi-group.
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entropy_dimension : tuple or list
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Number of Shannon entropy mesh cells in the x, y, and z directions,
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respectively
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@ -99,6 +50,60 @@ class Settings(object):
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Coordinates of the lower-left point of the Shannon entropy mesh
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entropy_upper_right : tuple or list
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Coordinates of the upper-right point of the Shannon entropy mesh
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generations_per_batch : int
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Number of generations per batch
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inactive : int
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Number of inactive batches
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keff_trigger : dict
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Dictionary defining a trigger on eigenvalue. The dictionary must have
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two keys, 'type' and 'threshold'. Acceptable values corresponding to
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type are 'variance', 'std_dev', and 'rel_err'. The threshold value
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should be a float indicating the variance, standard deviation, or
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relative error used.
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max_order : int
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Maximum scattering order to apply globally when in multi-group mode.
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multipole_library : str
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Indicates the path to a directory containing a windowed multipole
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cross section library. If it is not set, the
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:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
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multipole library is optional.
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no_reduce : bool
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Indicate that all user-defined and global tallies should not be reduced
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across processes in a parallel calculation.
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output : dict
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Dictionary indicating what files to output. Valid keys are 'summary',
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'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
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each key should be given as a boolean value.
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output_path : str
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Path to write output to
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particles : int
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Number of particles per generation
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ptables : bool
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Determine whether probability tables are used.
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resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
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The elastic scattering model to use for resonant isotopes
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run_cmfd : bool
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Indicate if coarse mesh finite difference acceleration is to be used
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run_mode : {'eigenvalue' or 'fixed source'}
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The type of calculation to perform (default is 'eigenvalue')
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seed : int
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Seed for the linear congruential pseudorandom number generator
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source : Iterable of openmc.Source
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Distribution of source sites in space, angle, and energy
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sourcepoint : dict
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Options for writing source points. Acceptable keys are:
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:batches: list of batches at which to write source
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:overwrite: bool indicating whether to overwrite
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:separate: bool indicating whether the source should be written as a
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separate file
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:write: bool indicating whether or not to write the source
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statepoint : dict
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Options for writing state points. Acceptable keys are:
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:batches: list of batches at which to write source
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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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Determines if a multi-group scattering moment kernel expanded via
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Legendre polynomials is to be converted to a tabular distribution or
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@ -116,17 +121,6 @@ class Settings(object):
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within which cross sections may be used. 'multipole' is a boolean
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indicating whether or not the windowed multipole method should be used
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to evaluate resolved resonance cross sections.
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trigger_active : bool
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Indicate whether tally triggers are used
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trigger_max_batches : int
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Maximum number of batches simulated. If this is set, the number of
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batches specified via ``batches`` is interpreted as the minimum number
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of batches
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trigger_batch_interval : int
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Number of batches in between convergence checks
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no_reduce : bool
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Indicate that all user-defined and global tallies should not be reduced
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across processes in a parallel calculation.
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threads : int
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Number of OpenMP threads
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trace : tuple or list
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@ -136,6 +130,14 @@ class Settings(object):
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Specify particles for which track files should be written. Each particle
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is identified by a triplet with the batch number, generation number, and
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particle number.
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trigger_active : bool
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Indicate whether tally triggers are used
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trigger_batch_interval : int
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Number of batches in between convergence checks
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trigger_max_batches : int
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Maximum number of batches simulated. If this is set, the number of
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batches specified via ``batches`` is interpreted as the minimum number
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of batches
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ufs_dimension : tuple or list
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Number of uniform fission site (UFS) mesh cells in the x, y, and z
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directions, respectively
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@ -143,12 +145,10 @@ class Settings(object):
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Coordinates of the lower-left point of the UFS mesh
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ufs_upper_right : tuple or list
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Coordinates of the upper-right point of the UFS mesh
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resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
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The elastic scattering model to use for resonant isotopes
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verbosity : int
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Verbosity during simulation between 1 and 10
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volume_calculations : VolumeCalculation or iterable of VolumeCalculation
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Stochastic volume calculation specifications
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create_fission_neutrons : bool
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Indicate whether fission neutrons should be created or not.
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"""
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