OpenMC/docs/source/pythonapi/deplete.rst
Andrew Johnson 72471d249f
Expand openmc.deplete documentation: minimal example and ABCs
Slight reformatting of the depletion documentation. The "Primary API"
is presented at the top, including integrators and the Operator.
This section is followed by a "Minimal Example" that demonstrates
how one might instantiate an Operator, and use it for depletion.
The comm communicator is moved into the "Internal Classes and Functions"
section, as the end-user is less likely to interact with this directly.
Lastly, a section on "Abstract Base Classes" is provided and expanded,
documenting the purpose of specific ABCs.
2019-09-17 14:56:31 -05:00

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5.3 KiB
ReStructuredText

.. _pythonapi_deplete:
----------------------------------
:mod:`openmc.deplete` -- Depletion
----------------------------------
.. module:: openmc.deplete
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:: Python
>>> 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 <http://mpi4py.scipy.org>`_, 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 functions are used to solve the depletion equations, with
:func:`cram.CRAM48` being the default.
.. 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.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 can be developed by subclassing from the following abstract
base classes:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myintegrator.rst
abc.Integrator
abc.SIIntegrator