Reorder attributes in Settings docstring

This commit is contained in:
Paul Romano 2016-12-13 06:37:26 -06:00
parent f866af1b16
commit 38362b6796

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@ -17,49 +17,15 @@ class Settings(object):
Attributes
----------
run_mode : {'eigenvalue' or 'fixed source'}
The type of calculation to perform (default is 'eigenvalue')
batches : int
Number of batches to simulate
generations_per_batch : int
Number of generations per batch
inactive : int
Number of inactive batches
particles : int
Number of particles per generation
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.
source : Iterable of openmc.Source
Distribution of source sites in space, angle, and energy
output : dict
Dictionary indicating what files to output. Valid keys are 'summary',
'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
each key should be given as a boolean value.
output_path : str
Path to write output to
verbosity : int
Verbosity during simulation between 1 and 10
statepoint : dict
Options for writing state points. Acceptable keys are:
:batches: list of batches at which to write source
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
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.
cross_sections : str
Indicates the path to an XML cross section listing file (usually named
cross_sections.xml). If it is not set, the
@ -67,23 +33,6 @@ class Settings(object):
continuous-energy calculations and
:envvar:`OPENMC_MG_CROSS_SECTIONS` will be used for multi-group
calculations to find the path to the XML cross section file.
multipole_library : str
Indicates the path to a directory containing a windowed multipole
cross section library. If it is not set, the
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
multipole library is optional.
energy_mode : {'continuous-energy', 'multi-group'}
Set whether the calculation should be continuous-energy or multi-group.
max_order : int
Maximum scattering order to apply globally when in multi-group mode.
ptables : bool
Determine whether probability tables are used.
run_cmfd : bool
Indicate if coarse mesh finite difference acceleration is to be used
seed : int
Seed for the linear congruential pseudorandom number generator
survival_biasing : bool
Indicate whether survival biasing is to be used
cutoff : dict
Dictionary defining weight cutoff and energy cutoff. The dictionary may
have three keys, 'weight', 'weight_avg' and 'energy'. Value for 'weight'
@ -92,6 +41,8 @@ class Settings(object):
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 will be killed.
energy_mode : {'continuous-energy', 'multi-group'}
Set whether the calculation should be continuous-energy or multi-group.
entropy_dimension : tuple or list
Number of Shannon entropy mesh cells in the x, y, and z directions,
respectively
@ -99,6 +50,60 @@ class Settings(object):
Coordinates of the lower-left point of the Shannon entropy mesh
entropy_upper_right : tuple or list
Coordinates of the upper-right point of the Shannon entropy mesh
generations_per_batch : int
Number of generations per batch
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.
max_order : int
Maximum scattering order to apply globally when in multi-group mode.
multipole_library : str
Indicates the path to a directory containing a windowed multipole
cross section library. If it is not set, the
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
multipole library is optional.
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. Valid keys are 'summary',
'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
each key should be given as a boolean value.
output_path : str
Path to write output to
particles : int
Number of particles per generation
ptables : bool
Determine whether probability tables are used.
resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
The elastic scattering model to use for resonant isotopes
run_cmfd : bool
Indicate if coarse mesh finite difference acceleration is to be used
run_mode : {'eigenvalue' or 'fixed source'}
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
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
@ -116,17 +121,6 @@ class Settings(object):
within which cross sections may be used. 'multipole' is a boolean
indicating whether or not the windowed multipole method should be used
to evaluate resolved resonance cross sections.
trigger_active : bool
Indicate whether tally triggers are used
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
trigger_batch_interval : int
Number of batches in between convergence checks
no_reduce : bool
Indicate that all user-defined and global tallies should not be reduced
across processes in a parallel calculation.
threads : int
Number of OpenMP threads
trace : tuple or list
@ -136,6 +130,14 @@ class Settings(object):
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_dimension : tuple or list
Number of uniform fission site (UFS) mesh cells in the x, y, and z
directions, respectively
@ -143,12 +145,10 @@ class Settings(object):
Coordinates of the lower-left point of the UFS mesh
ufs_upper_right : tuple or list
Coordinates of the upper-right point of the UFS mesh
resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
The elastic scattering model to use for resonant isotopes
verbosity : int
Verbosity during simulation between 1 and 10
volume_calculations : VolumeCalculation or iterable of VolumeCalculation
Stochastic volume calculation specifications
create_fission_neutrons : bool
Indicate whether fission neutrons should be created or not.
"""