openmc.mgxs – Multi-Group Cross Section Generation

Energy Groups

Module Variables

[SAR1990]Sartori, E., OECD/NEA Data Bank: Standard Energy Group Structures of Cross Section Libraries for Reactor Shielding, Reactor Cell and Fusion Neutronics Applications: VITAMIN-J, ECCO-33, ECCO-2000 and XMAS JEF/DOC-315 Revision 3 - DRAFT (December 11, 1990).
[SAN2004]Santamarina, A., Collignon, C., & Garat, C. (2004). French calculation schemes for light water reactor analysis. United States: American Nuclear Society - ANS.
[HFA2005]Hfaiedh, N. & Santamarina, A., “Determination of the Optimized SHEM Mesh for Neutron Transport Calculations,” Proc. Top. Mtg. in Mathematics & Computations, Supercomputing, Reactor Physics and Nuclear and Biological Applications, September 12-15, Avignon, France, 2005.
[SAN2007]Santamarina, A. & Hfaiedh, N. (2007). The SHEM energy mesh for accurate fuel depletion and BUC calculations. Proceedings of the International Conference on Safety Criticality ICNC 2007, St Peterburg (Russia), Vol. I pp. 446-452.
[HEB2008]Hébert, Alain & Santamarina, Alain. (2008). Refinement of the Santamarina-Hfaiedh energy mesh between 22.5 eV and 11.4 keV. International Conference on the Physics of Reactors 2008, PHYSOR 08. 2. 929-938.
Type:Dictionary of commonly used energy group structures


openmc.mgxs.EnergyGroups An energy groups structure used for multi-group cross-sections.

Multi-group Cross Sections

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.

Multi-delayed-group Cross Sections

openmc.mgxs.MDGXS An abstract multi-delayed-group cross section for some energy and delayed group structures within some spatial domain.
openmc.mgxs.ChiDelayed The delayed fission spectrum.
openmc.mgxs.DelayedNuFissionXS A fission delayed neutron production multi-group cross section.
openmc.mgxs.DelayedNuFissionMatrixXS A fission delayed neutron production matrix multi-group cross section.
openmc.mgxs.Beta The delayed neutron fraction.
openmc.mgxs.DecayRate The decay rate for delayed neutron precursors.

Multi-group Cross Section Libraries

openmc.mgxs.Library A multi-energy-group and multi-delayed-group cross section library for some energy group structure.