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Update openmc/mgxs/mgxs.py
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
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@ -5917,7 +5917,7 @@ class MeshSurfaceMGXS(MGXS):
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energy_groups : openmc.mgxs.EnergyGroups
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The energy group structure for energy condensation
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by_nuclide : bool
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Unused in MeshSurfacMGXS
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Unused in MeshSurfaceMGXS
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name : str, optional
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Name of the multi-group cross section. Used as a label to identify
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tallies in OpenMC 'tallies.xml' file.
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