deleting all files to prepare for review

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Paul Romano 2019-10-28 11:48:19 -05:00
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------------------------------------
:mod:`openmc` -- Basic Functionality
------------------------------------
Handling nuclear data
---------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.XSdata
openmc.MGXSLibrary
Simulation Settings
-------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Source
openmc.VolumeCalculation
openmc.Settings
Material Specification
----------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Nuclide
openmc.Element
openmc.Macroscopic
openmc.Material
openmc.Materials
Cross sections for nuclides, elements, and materials can be plotted using the
following function:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.plot_xs
Building geometry
-----------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Plane
openmc.XPlane
openmc.YPlane
openmc.ZPlane
openmc.XCylinder
openmc.YCylinder
openmc.ZCylinder
openmc.Sphere
openmc.Cone
openmc.XCone
openmc.YCone
openmc.ZCone
openmc.Quadric
openmc.Halfspace
openmc.Intersection
openmc.Union
openmc.Complement
openmc.Cell
openmc.Universe
openmc.RectLattice
openmc.HexLattice
openmc.Geometry
Many of the above classes are derived from several abstract classes:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Surface
openmc.Region
openmc.Lattice
.. _pythonapi_tallies:
Constructing Tallies
--------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Filter
openmc.UniverseFilter
openmc.MaterialFilter
openmc.CellFilter
openmc.CellFromFilter
openmc.CellbornFilter
openmc.SurfaceFilter
openmc.MeshFilter
openmc.MeshSurfaceFilter
openmc.EnergyFilter
openmc.EnergyoutFilter
openmc.MuFilter
openmc.PolarFilter
openmc.AzimuthalFilter
openmc.DistribcellFilter
openmc.DelayedGroupFilter
openmc.EnergyFunctionFilter
openmc.LegendreFilter
openmc.SpatialLegendreFilter
openmc.SphericalHarmonicsFilter
openmc.ZernikeFilter
openmc.ZernikeRadialFilter
openmc.ParticleFilter
openmc.RegularMesh
openmc.RectilinearMesh
openmc.Trigger
openmc.TallyDerivative
openmc.Tally
openmc.Tallies
Geometry Plotting
-----------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Plot
openmc.Plots
Running OpenMC
--------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.run
openmc.calculate_volumes
openmc.plot_geometry
openmc.plot_inline
openmc.search_for_keff
Post-processing
---------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.Particle
openmc.StatePoint
openmc.Summary
The following classes and functions are used for functional expansion reconstruction.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.ZernikeRadial
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.legendre_from_expcoef
Various classes may be created when performing tally slicing and/or arithmetic:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.arithmetic.CrossScore
openmc.arithmetic.CrossNuclide
openmc.arithmetic.CrossFilter
openmc.arithmetic.AggregateScore
openmc.arithmetic.AggregateNuclide
openmc.arithmetic.AggregateFilter
Coarse Mesh Finite Difference Acceleration
------------------------------------------
CMFD is implemented in OpenMC and allows users to accelerate fission source
convergence during inactive neutron batches. To use CMFD, the
:class:`openmc.cmfd.CMFDRun` class executes OpenMC through the C API, solving
the CMFD system between fission generations and modifying the source weights.
Note that the :mod:`openmc.cmfd` module is not imported by default with the
:mod:`openmc` namespace and needs to be imported explicitly.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.cmfd.CMFDMesh
openmc.cmfd.CMFDRun
At the minimum, a CMFD mesh needs to be specified in order to run CMFD. Once the
mesh and other optional properties are set, a simulation can be run with CMFD
turned on using :meth:`openmc.cmfd.CMFDRun.run`.

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------------------------------------------------------
:mod:`openmc.lib` -- Python bindings to the C/C++ API
------------------------------------------------------
.. automodule:: openmc.lib
Functions
---------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
calculate_volumes
finalize
find_cell
find_material
hard_reset
init
iter_batches
keff
load_nuclide
next_batch
num_realizations
plot_geometry
reset
run
run_in_memory
simulation_init
simulation_finalize
source_bank
statepoint_write
Classes
-------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Cell
EnergyFilter
MaterialFilter
Material
MeshFilter
MeshSurfaceFilter
Nuclide
RegularMesh
Tally

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--------------------------------------------
:mod:`openmc.data` -- Nuclear Data Interface
--------------------------------------------
.. module:: openmc.data
Core Classes
------------
The following classes are used for incident neutron data, decay data, fission
and product yields.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
IncidentNeutron
Reaction
Product
FissionEnergyRelease
DataLibrary
Decay
FissionProductYields
WindowedMultipole
ProbabilityTables
The following classes are used for storing atomic data (incident photon cross
sections, atomic relaxation):
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
IncidentPhoton
PhotonReaction
AtomicRelaxation
The following classes are used for storing thermal neutron scattering data:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
ThermalScattering
ThermalScatteringReaction
CoherentElastic
IncoherentElastic
Core Functions
--------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
atomic_mass
gnd_name
linearize
thin
water_density
zam
One-dimensional Functions
-------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Function1D
Tabulated1D
Polynomial
Combination
Sum
Regions1D
ResonancesWithBackground
Angle-Energy Distributions
--------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
AngleEnergy
KalbachMann
CorrelatedAngleEnergy
UncorrelatedAngleEnergy
NBodyPhaseSpace
LaboratoryAngleEnergy
AngleDistribution
EnergyDistribution
ArbitraryTabulated
GeneralEvaporation
MaxwellEnergy
Evaporation
WattEnergy
MadlandNix
DiscretePhoton
LevelInelastic
ContinuousTabular
CoherentElasticAE
IncoherentElasticAE
IncoherentElasticAEDiscrete
IncoherentInelasticAEDiscrete
Resonance Data
--------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Resonances
ResonanceRange
SingleLevelBreitWigner
MultiLevelBreitWigner
ReichMoore
RMatrixLimited
ResonanceCovariances
ResonanceCovarianceRange
SingleLevelBreitWignerCovariance
MultiLevelBreitWignerCovariance
ReichMooreCovariance
ParticlePair
SpinGroup
Unresolved
ACE Format
----------
Classes
+++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
ace.Library
ace.Table
Functions
+++++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
ace.ascii_to_binary
ENDF Format
-----------
Classes
+++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
endf.Evaluation
Functions
+++++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
endf.float_endf
endf.get_cont_record
endf.get_evaluations
endf.get_head_record
endf.get_tab1_record
endf.get_tab2_record
endf.get_text_record
NJOY Interface
--------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
njoy.run
njoy.make_pendf
njoy.make_ace
njoy.make_ace_thermal

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.. _pythonapi_deplete:
.. module:: openmc.deplete
----------------------------------
:mod:`openmc.deplete` -- Depletion
----------------------------------
Primary API
-----------
The two primary requirements to perform depletion with :mod:`openmc.deplete`
are:
1) A transport operator
2) A time-integration scheme
The former is responsible for executing a transport code, like OpenMC,
and retaining important information required for depletion. The most common examples
are reaction rates and power normalization data. The latter is responsible for
projecting reaction rates and compositions forward in calendar time across
some step size :math:`\Delta t`, and obtaining new compositions given a power
or power density. The :class:`Operator` is provided to handle communicating with
OpenMC. Several classes are provided that implement different time-integration
algorithms for depletion calculations, which are described in detail in Colin
Josey's thesis, `Development and analysis of high order neutron
transport-depletion coupling algorithms <http://hdl.handle.net/1721.1/113721>`_.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myintegrator.rst
PredictorIntegrator
CECMIntegrator
CELIIntegrator
CF4Integrator
EPCRK4Integrator
LEQIIntegrator
SICELIIntegrator
SILEQIIntegrator
Each of these classes expects a "transport operator" to be passed. An operator
specific to OpenMC is available using the following class:
.. autosummary::
:toctree: generated
:nosignatures:
:template: mycallable.rst
Operator
The :class:`Operator` must also have some knowledge of how nuclides transmute
and decay. This is handled by the :class:`Chain`.
Minimal Example
---------------
A minimal example for performing depletion would be:
.. code::
>>> import openmc
>>> import openmc.deplete
>>> geometry = openmc.Geometry.from_xml()
>>> settings = openmc.Settings.from_xml()
# Representation of a depletion chain
>>> chain_file = "chain_casl.xml"
>>> operator = openmc.deplete.Operator(
... geometry, settings, chain_file)
# Set up 5 time steps of one day each
>>> dt = [24 * 60 * 60] * 5
>>> power = 1e6 # constant power of 1 MW
# Deplete using mid-point predictor-corrector
>>> cecm = openmc.deplete.CECMIntegrator(
... operator, dt, power)
>>> cecm.integrate()
Internal Classes and Functions
------------------------------
When running in parallel using `mpi4py
<https://mpi4py.readthedocs.io/en/stable/>`_, the MPI intercommunicator used can
be changed by modifying the following module variable. If it is not explicitly
modified, it defaults to ``mpi4py.MPI.COMM_WORLD``.
.. data:: comm
MPI intercommunicator used to call OpenMC library
:type: mpi4py.MPI.Comm
During a depletion calculation, the depletion chain, reaction rates, and number
densities are managed through a series of internal classes that are not normally
visible to a user. However, should you find yourself wondering about these
classes (e.g., if you want to know what decay modes or reactions are present in
a depletion chain), they are documented here. The following classes store data
for a depletion chain:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Chain
DecayTuple
Nuclide
ReactionTuple
FissionYieldDistribution
FissionYield
The following classes are used during a depletion simulation and store auxiliary
data, such as number densities and reaction rates for each material.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
AtomNumber
OperatorResult
ReactionRates
Results
ResultsList
The following class and functions are used to solve the depletion equations,
with :func:`cram.CRAM48` being the default.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myintegrator.rst
cram.IPFCramSolver
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
cram.CRAM16
cram.CRAM48
cram.deplete
cram.timed_deplete
The following classes are used to help the :class:`openmc.deplete.Operator`
compute quantities like effective fission yields, reaction rates, and
total system energy.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
helpers.AveragedFissionYieldHelper
helpers.ChainFissionHelper
helpers.ConstantFissionYieldHelper
helpers.DirectReactionRateHelper
helpers.EnergyScoreHelper
helpers.FissionYieldCutoffHelper
Abstract Base Classes
---------------------
A good starting point for extending capabilities in :mod:`openmc.deplete` is
to examine the following abstract base classes. Custom classes can
inherit from :class:`abc.TransportOperator` to implement alternative
schemes for collecting reaction rates and other data from a transport code
prior to depleting materials
.. autosummary::
:toctree: generated
:nosignatures:
:template: mycallable.rst
abc.TransportOperator
The following classes are abstract classes used to pass information from
OpenMC simulations back on to the :class:`abc.TransportOperator`
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
abc.EnergyHelper
abc.FissionYieldHelper
abc.ReactionRateHelper
abc.TalliedFissionYieldHelper
Custom integrators or depletion solvers can be developed by subclassing from
the following abstract base classes:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myintegrator.rst
abc.Integrator
abc.SIIntegrator
abc.DepSystemSolver

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----------------------------------------
:mod:`openmc.examples` -- Example Models
----------------------------------------
Simple Models
-------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.examples.slab_mg
Reactor Models
--------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.examples.pwr_pin_cell
openmc.examples.pwr_assembly
openmc.examples.pwr_core

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.. _pythonapi:
==========
Python API
==========
OpenMC includes a rich Python API that enables programmatic pre- and
post-processing. The easiest way to begin using the API is to take a look at the
:ref:`examples`. This assumes that you are already familiar with Python and
common third-party packages such as `NumPy <http://www.numpy.org/>`_. If you
have never used Python before, the prospect of learning a new code *and* a
programming language might sound daunting. However, you should keep in mind that
there are many substantial benefits to using the Python API, including:
- The ability to define dimensions using variables.
- Availability of standard-library modules for working with files.
- An entire ecosystem of third-party packages for scientific computing.
- Automated multi-group cross section generation (:mod:`openmc.mgxs`)
- A fully-featured nuclear data interface (:mod:`openmc.data`)
- Depletion capability (:mod:`openmc.deplete`)
- Convenience functions (e.g., a function returning a hexagonal region)
- Ability to plot individual universes as geometry is being created
- A :math:`k_\text{eff}` search function (:func:`openmc.search_for_keff`)
- Random sphere packing for generating TRISO particle locations
(:func:`openmc.model.pack_spheres`)
- Ability to create materials based on natural elements or uranium enrichment
For those new to Python, there are many good tutorials available online. We
recommend going through the modules from `Codecademy
<https://www.codecademy.com/learn/learn-python-3>`_ and/or the `Scipy lectures
<https://scipy-lectures.github.io/>`_.
The full API documentation serves to provide more information on a given module
or class.
.. tip:: Users are strongly encouraged to use the Python API to generate input
files and analyze results.
.. rubric:: Modules
.. toctree::
:maxdepth: 1
base
model
examples
deplete
mgxs
stats
data
capi
openmoc

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----------------------------------------------------------
:mod:`openmc.mgxs` -- Multi-Group Cross Section Generation
----------------------------------------------------------
Energy Groups
-------------
Module Variables
++++++++++++++++
.. autodata:: openmc.mgxs.GROUP_STRUCTURES
:annotation:
Classes
+++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.mgxs.EnergyGroups
Multi-group Cross Sections
--------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclassinherit.rst
openmc.mgxs.MGXS
openmc.mgxs.AbsorptionXS
openmc.mgxs.CaptureXS
openmc.mgxs.Chi
openmc.mgxs.FissionXS
openmc.mgxs.InverseVelocity
openmc.mgxs.KappaFissionXS
openmc.mgxs.MultiplicityMatrixXS
openmc.mgxs.NuFissionMatrixXS
openmc.mgxs.ScatterXS
openmc.mgxs.ScatterMatrixXS
openmc.mgxs.ScatterProbabilityMatrix
openmc.mgxs.TotalXS
openmc.mgxs.TransportXS
Multi-delayed-group Cross Sections
----------------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclassinherit.rst
openmc.mgxs.MDGXS
openmc.mgxs.ChiDelayed
openmc.mgxs.DelayedNuFissionXS
openmc.mgxs.DelayedNuFissionMatrixXS
openmc.mgxs.Beta
openmc.mgxs.DecayRate
Multi-group Cross Section Libraries
-----------------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.mgxs.Library

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-------------------------------------
:mod:`openmc.model` -- Model Building
-------------------------------------
Convenience Functions
---------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.model.borated_water
openmc.model.cylinder_from_points
openmc.model.hexagonal_prism
openmc.model.rectangular_prism
openmc.model.subdivide
openmc.model.pin
TRISO Fuel Modeling
-------------------
Classes
+++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.model.TRISO
Functions
+++++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.model.create_triso_lattice
openmc.model.pack_spheres
Model Container
---------------
Classes
+++++++
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.model.Model

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---------------------------------------------------------
:mod:`openmc.openmoc_compatible` -- OpenMOC Compatibility
---------------------------------------------------------
Core Classes
------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.openmoc_compatible.get_openmoc_material
openmc.openmoc_compatible.get_openmc_material
openmc.openmoc_compatible.get_openmoc_surface
openmc.openmoc_compatible.get_openmc_surface
openmc.openmoc_compatible.get_openmoc_cell
openmc.openmoc_compatible.get_openmc_cell
openmc.openmoc_compatible.get_openmoc_universe
openmc.openmoc_compatible.get_openmc_universe
openmc.openmoc_compatible.get_openmoc_lattice
openmc.openmoc_compatible.get_openmc_lattice
openmc.openmoc_compatible.get_openmoc_geometry
openmc.openmoc_compatible.get_openmc_geometry

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.. _pythonapi_stats:
---------------------------------
:mod:`openmc.stats` -- Statistics
---------------------------------
Univariate Probability Distributions
------------------------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.stats.Univariate
openmc.stats.Discrete
openmc.stats.Uniform
openmc.stats.Maxwell
openmc.stats.Watt
openmc.stats.Tabular
openmc.stats.Legendre
openmc.stats.Mixture
openmc.stats.Normal
openmc.stats.Muir
Angular Distributions
---------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.stats.UnitSphere
openmc.stats.PolarAzimuthal
openmc.stats.Isotropic
openmc.stats.Monodirectional
Spatial Distributions
---------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.stats.Spatial
openmc.stats.CartesianIndependent
openmc.stats.Box
openmc.stats.Point