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Updated documentation
Added current to mgxs.rst and cleaned up descriptions in Current & MeshSurfaceCurrent class
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2 changed files with 4 additions and 3 deletions
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@ -33,6 +33,7 @@ Multi-group Cross Sections
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openmc.mgxs.AbsorptionXS
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openmc.mgxs.CaptureXS
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openmc.mgxs.Chi
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openmc.mgxs.Current
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openmc.mgxs.FissionXS
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openmc.mgxs.InverseVelocity
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openmc.mgxs.KappaFissionXS
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@ -5914,7 +5914,7 @@ 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 for SurfacMGXS
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Unused in MeshSurfacMGXS
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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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@ -5926,7 +5926,7 @@ class MeshSurfaceMGXS(MGXS):
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rxn_type : str
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Reaction type (e.g., 'total', 'nu-fission', etc.)
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by_nuclide : bool
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Unused for MeshSurfaceMGXS
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Unused in MeshSurfaceMGXS
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domain : Mesh
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Domain for spatial homogenization
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domain_type : {'mesh'}
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@ -6296,7 +6296,7 @@ class Current(MeshSurfaceMGXS):
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rxn_type : str
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Reaction type (e.g., 'total', 'nu-fission', etc.)
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by_nuclide : bool
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Unused for MeshSurfaceMGXS
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Unused in MeshSurfaceMGXS
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domain : Mesh
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Domain for spatial homogenization
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domain_type : {'mesh'}
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