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make statements about multiple materials and env vars more precise

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yardasol 2022-09-11 14:03:23 -05:00
parent 8cdce03828
commit 15a75284f4
1 changed files with 12 additions and 10 deletions
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docs/source/usersguide/depletion.rst
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@ -298,10 +298,10 @@ units of barns::
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 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>`_
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>`_
Caveats
@ -325,7 +325,7 @@ normalizing reaction rates:
the cross sections by the ``source-rate``.
2. ``fission-q`` normalization, which uses the ``power`` or ``power_density``
provided by the time integrator to obtain reaction rates by computing a value
for the flux based on this power. The general equation for the flux is
for the flux based on this power. The equation we use for this calculation is
.. math::
:label: fission-q
@ -354,11 +354,13 @@ Multiple Materials
A transport-independent depletion simulation using ``source-race`` normalization
will calculate reaction rates for each material independently. This can be
useful for running many different cases of a particular scenario. A depletion
simulation using ``fission-q`` normalization will sum the energy values from
each material into :math:`Q` in Equation :math:numref:`fission-q`, which is
used to normalize the reaction rates for all materials. This behavior may
change in the future.
useful for running many different cases of a particular scenario. A
transport-independent depletion simulation using ``fission-q`` normalization
will sum the fission energy values across all materials into :math:`Q_i` in
Equation :math:numref:`fission-q`, and Equation :math:numref:`fission-q`
provides the flux we use to calculate the reaction rates in each material.
This can be useful for running a scenario with multiple depletable materials
that are part of the same reactor. This behavior may change in the future.
Time integration
~~~~~~~~~~~~~~~~