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API used by the Operator:
- generate_tallies
- weighted_yields [abstract]
- update_nuclides_from_operator
- unpack
generate_tallies and unpack are empty methods, provided
so that a consistent API can be found on helpers
with tallies.
Sorts nuclides into two dictionaries: those with a single
set of fission yields, and those with multiple sets.
The former can is exposed through the
constant_yields property, returning a copy of the fission
yield dictionary {parent: {product: yield}}
The Operator now looks for/uses the weighted_yields and
update_nuclides_from_operator methods instead of the old
compute_yields and set_fissionable_nuclides methods
121 lines
2.9 KiB
ReStructuredText
121 lines
2.9 KiB
ReStructuredText
.. _pythonapi_deplete:
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----------------------------------
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:mod:`openmc.deplete` -- Depletion
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----------------------------------
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.. module:: openmc.deplete
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Several classes are provided that implement different time-integration
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algorithms for depletion calculations, which are described in detail in Colin
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Josey's thesis, `Development and analysis of high order neutron
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transport-depletion coupling algorithms <http://hdl.handle.net/1721.1/113721>`_.
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myintegrator.rst
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PredictorIntegrator
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CECMIntegrator
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CELIIntegrator
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CF4Integrator
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EPCRK4Integrator
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LEQIIntegrator
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SICELIIntegrator
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SILEQIIntegrator
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Each of these classes expects a "transport operator" to be passed. An operator
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specific to OpenMC is available using the following class:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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Operator
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When running in parallel using `mpi4py <http://mpi4py.scipy.org>`_, the MPI
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intercommunicator used can be changed by modifying the following module
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variable. If it is not explicitly modified, it defaults to
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``mpi4py.MPI.COMM_WORLD``.
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.. data:: comm
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MPI intercommunicator used to call OpenMC library
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:type: mpi4py.MPI.Comm
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Internal Classes and Functions
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------------------------------
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During a depletion calculation, the depletion chain, reaction rates, and number
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densities are managed through a series of internal classes that are not normally
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visible to a user. However, should you find yourself wondering about these
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classes (e.g., if you want to know what decay modes or reactions are present in
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a depletion chain), they are documented here. The following classes store data
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for a depletion chain:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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Chain
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DecayTuple
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Nuclide
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ReactionTuple
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FissionYieldDistribution
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FissionYield
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The following classes are used during a depletion simulation and store auxiliary
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data, such as number densities and reaction rates for each material.
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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AtomNumber
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ChainFissionHelper
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DirectReactionRateHelper
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OperatorResult
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ReactionRates
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Results
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ResultsList
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The following classes are abstract classes that can be used to extend the
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:mod:`openmc.deplete` capabilities:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myclass.rst
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EnergyHelper
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FissionYieldHelper
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ReactionRateHelper
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TransportOperator
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Custom integrators can be developed by subclassing from the following abstract
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base classes:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myintegrator.rst
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Integrator
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SIIntegrator
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Each of the integrator classes also relies on a number of "helper" functions
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as follows:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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cram.CRAM16
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cram.CRAM48
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