openmc.mgxs – Multi-Group Cross Section Generation

Energy Groups

Module Variables

openmc.mgxs.GROUP_STRUCTURES

Dictionary of commonly used energy group structures:

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.

ZAL1999

K. Záleský and L. Marková (1999), Assessment of Nuclear Data Needs for Broad-Group SCALE Library Related to VVER Spent Fuel Applications, IAEA.

Classes

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.MatrixMGXS

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.Current

A current multi-group cross section.

openmc.mgxs.DiffusionCoefficient

A diffusion coefficient multi-group cross section.

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.

openmc.mgxs.ArbitraryXS

A multi-group cross section for an arbitrary reaction type.

openmc.mgxs.ArbitraryMatrixXS

A multi-group matrix cross section for an arbitrary reaction type.

openmc.mgxs.MeshSurfaceMGXS

An abstract multi-group cross section for some energy group structure on the surfaces of a mesh domain.

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.MatrixMDGXS

An abstract multi-delayed-group cross section for some energy group and delayed group structure 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.