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Merge remote-tracking branch 'origin/microxs-from-model-parallel' into microxs-from-model-parallel

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yardasol 2022-09-11 14:08:06 -05:00
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docs/source/usersguide/depletion.rst
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@ -259,12 +259,12 @@ transport-depletion calculation and follow the same steps from there.
will not be simulated.
Loading and Generating Microscopic Cross Sections
-------------------------------------
-------------------------------------------------
As mentioned earlier, any transport code could be used to calculate one-group
microscopic cross sections. The :mod:`openmc.deplete` module provides the
:class:`~openmc.deplete.MicroXS` class, which contains methods to read in
pre-caluclated cross sections from a ``.csv`` file or from data arrays::
pre-calculated cross sections from a ``.csv`` file or from data arrays::
micro_xs = MicroXS.from_csv(micro_xs_path)
@ -296,12 +296,13 @@ units of barns::
model.materials[0],
chain_file)
If you are runnnig :meth:`~openmc.deplete.MicroXS.from_model()` on a cluster
that does not share local filesystems across nodes, you'll need to set an
environment variable pointing to a directory accessible by MPI so that each
MPI process knows where to store output files used to calculate the microscopic
cross sections. In order of priority, they are `TMPDIR`. `TEMP`, and `TMP`.
Users interested in further details can read the `relevant docpage on the tempfile pacakge <https://docs.python.org/3/library/tempfile.html#tempfile.gettempdir>`_
If you are running :meth:`~openmc.deplete.MicroXS.from_model()` on a cluster
where temporary files are created on a local filesystem that is not shared
across nodes, you'll need to set an environment variable pointing to a local
directoy so that each MPI process knows where to store output files used to
calculate the microscopic cross sections. In order of priority, they are
:envvar:`TMPDIR`. :envvar:`TEMP`, and :envvar:`TMP`. Users interested in
further details can read the documentation for the `tempfile <https://docs.python.org/3/library/tempfile.html#tempfile.gettempdir>`_ module.
Caveats
@ -352,7 +353,7 @@ normalizing reaction rates:
Multiple Materials
~~~~~~~~~~~~~~~~~~
A transport-independent depletion simulation using ``source-race`` normalization
A transport-independent depletion simulation using ``source-rate`` normalization
will calculate reaction rates for each material independently. This can be
useful for running many different cases of a particular scenario. A
transport-independent depletion simulation using ``fission-q`` normalization