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Update openmc/mgxs/mgxs.py

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Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
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Miriam (Rathbun) Kreher 2020-08-15 22:28:44 -06:00 • committed by GitHub
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openmc/mgxs/mgxs.py
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@ -6260,6 +6260,7 @@ class MeshSurfaceMGXS(MGXS):
class Current(MeshSurfaceMGXS):
r"""A current multi-group cross section.
This class can be used for both OpenMC input generation and tally data
post-processing to compute surface- and energy-integrated
multi-group current cross sections for multi-group neutronics calculations. At
@ -6268,12 +6269,14 @@ class Current(MeshSurfaceMGXS):
reaction rates over the specified domain are generated automatically via the
:attr:`Current.tallies` property, which can then be appended to a
:class:`openmc.Tallies` instance.
For post-processing, the :meth:`MGXS.load_from_statepoint` will pull in the
necessary data to compute multi-group cross sections from a
:class:`openmc.StatePoint` instance. The derived multi-group cross section
can then be obtained from the :attr:`Current.xs_tally` property.
For a spatial domain :math:`S` and energy group :math:`[E_g,E_{g-1}]`, the
total cross section is calculated as:
.. math::
\frac{\int_{r \in S} dS \int_{E_g}^{E_{g-1}} dE \;
J(r, E)}{\int_{r \in S} dS \int_{E_g}^{E_{g-1}} dE}.