openmc.mgxs.MGXS |
An abstract multi-group cross section for some energy group structure within some spatial domain. |
openmc.mgxs.AbsorptionXS |
An absorption multi-group cross section. |
openmc.mgxs.CaptureXS |
A capture multi-group cross section. |
openmc.mgxs.Chi |
The fission spectrum. |
openmc.mgxs.FissionXS |
A fission multi-group cross section. |
openmc.mgxs.InverseVelocity |
An inverse velocity multi-group cross section. |
openmc.mgxs.KappaFissionXS |
A recoverable fission energy production rate multi-group cross section. |
openmc.mgxs.MultiplicityMatrixXS |
The scattering multiplicity matrix. |
openmc.mgxs.NuFissionMatrixXS |
A fission production matrix multi-group cross section. |
openmc.mgxs.ScatterXS |
A scattering multi-group cross section. |
openmc.mgxs.ScatterMatrixXS |
A scattering matrix multi-group cross section with the cosine of the change-in-angle represented as one or more Legendre moments or a histogram. |
openmc.mgxs.ScatterProbabilityMatrix |
The group-to-group scattering probability matrix. |
openmc.mgxs.TotalXS |
A total multi-group cross section. |
openmc.mgxs.TransportXS |
A transport-corrected total multi-group cross section. |