OpenMC/docs/source/pythonapi/deplete.rst
2025-02-21 12:47:38 -05:00

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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 calculating 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:`CoupledOperator` class is provided to obtain reaction rates via tallies
through OpenMC's transport solver, and the :class:`IndependentOperator` class is
provided to obtain reaction rates from cross-section data. 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::
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:template: myintegrator.rst
PredictorIntegrator
CECMIntegrator
CELIIntegrator
CF4Integrator
EPCRK4Integrator
LEQIIntegrator
SICELIIntegrator
SILEQIIntegrator
Each of these classes expects a "transport operator" to be passed. OpenMC
provides the following transport operator classes:
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CoupledOperator
IndependentOperator
The :class:`CoupledOperator` and :class:`IndependentOperator` classes must also
have some knowledge of how nuclides transmute and decay. This is handled by the
:class:`Chain` class.
The :class:`IndependentOperator` class requires a set of fluxes and microscopic
cross sections. The following function can be used to generate this information:
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get_microxs_and_flux
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()
>>> model = openmc.model.Model(geometry, settings)
# Representation of a depletion chain
>>> chain_file = "chain_casl.xml"
>>> operator = openmc.deplete.CoupledOperator(
... model, 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:
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Chain
DecayTuple
Nuclide
ReactionTuple
FissionYieldDistribution
FissionYield
The :class:`Chain` class uses information from the following module variable:
.. data:: chain.REACTIONS
Dictionary that maps transmutation reaction names to information needed when
a chain is being generated: MT values, the change in atomic/mass numbers
resulting from the reaction, and what secondaries are produced.
:type: dict
The following classes are used during a depletion simulation and store auxiliary
data, such as number densities and reaction rates for each material.
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AtomNumber
MicroXS
OperatorResult
ReactionRates
Results
StepResult
The following class and functions are used to solve the depletion equations,
with :func:`cram.CRAM48` being the default.
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cram.IPFCramSolver
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cram.CRAM16
cram.CRAM48
pool.deplete
.. data:: pool.USE_MULTIPROCESSING
Boolean switch to enable or disable the use of :mod:`multiprocessing`
when solving the Bateman equations. The default is to use
:mod:`multiprocessing`, but can cause the simulation to hang in
some computing environments, namely due to MPI and networking
restrictions. Disabling this option will result in only a single
CPU core being used for depletion.
:type: bool
.. data:: pool.NUM_PROCESSES
Number of worker processes used for depletion calculations, which rely on the
:class:`multiprocessing.pool.Pool` class. If set to ``None`` (default), the
number returned by :func:`os.cpu_count` is used.
The following classes are used to help the :class:`openmc.deplete.CoupledOperator`
compute quantities like effective fission yields, reaction rates, and
total system energy.
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helpers.AveragedFissionYieldHelper
helpers.ChainFissionHelper
helpers.ConstantFissionYieldHelper
helpers.DirectReactionRateHelper
helpers.EnergyScoreHelper
helpers.FissionYieldCutoffHelper
helpers.FluxCollapseHelper
The :class:`openmc.deplete.IndependentOperator` uses inner classes subclassed
from those listed above to perform similar calculations.
The following classes are used to define transfer rates to model continuous
removal or feed of nuclides during depletion.
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transfer_rates.TransferRates
Intermediate Classes
--------------------
Specific implementations of abstract base classes may utilize some of
the same methods and data structures. These methods and data are stored
in intermediate classes.
Methods common to tally-based implementation of :class:`FissionYieldHelper`
are stored in :class:`helpers.TalliedFissionYieldHelper`
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helpers.TalliedFissionYieldHelper
Methods common to OpenMC-specific implementations of :class:`TransportOperator`
are stored in :class:`openmc_operator.OpenMCOperator`
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openmc_operator.OpenMCOperator
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 prior to depleting
materials
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abc.TransportOperator
The following classes are abstract classes used to pass information from
transport simulations (in the case of transport-coupled depletion) or to
simply calculate these quantities directly (in the case of
transport-independent depletion) back on to the :class:`abc.TransportOperator`
.. autosummary::
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abc.NormalizationHelper
abc.FissionYieldHelper
abc.ReactionRateHelper
Custom integrators or depletion solvers can be developed by subclassing from
the following abstract base classes:
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abc.Integrator
abc.SIIntegrator
abc.DepSystemSolver
D1S Functions
-------------
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d1s.prepare_tallies
d1s.time_correction_factors
d1s.apply_time_correction