openmc.mgxs
– MultiGroup Cross Section Generation¶
Energy Groups¶
Module Variables¶

openmc.mgxs.
GROUP_STRUCTURES
¶  “CASMOX” (where X is 2, 4, 8, 16, 25, 40 or 70) from the CASMO lattice physics code
 “XMAS172” designed for LWR analysis ([SAR1990], [SAN2004])
 “SHEM361” designed for LWR analysis to eliminate selfshielding calculations of thermal resonances ([HFA2005], [SAN2007], [HEB2008])
 activation energy group structures “VITAMINJ42”, “VITAMINJ175”, “TRIPOLI315”, “CCFE709” and “UKAEA1102”
[SAR1990] Sartori, E., OECD/NEA Data Bank: Standard Energy Group Structures of Cross Section Libraries for Reactor Shielding, Reactor Cell and Fusion Neutronics Applications: VITAMINJ, ECCO33, ECCO2000 and XMAS JEF/DOC315 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 1215, 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. 446452. [HEB2008] Hébert, Alain & Santamarina, Alain. (2008). Refinement of the SantamarinaHfaiedh energy mesh between 22.5 eV and 11.4 keV. International Conference on the Physics of Reactors 2008, PHYSOR 08. 2. 929938. Type: Dictionary of commonly used energy group structures
Classes¶
openmc.mgxs.EnergyGroups 
An energy groups structure used for multigroup crosssections. 
Multigroup Cross Sections¶
openmc.mgxs.MGXS 
An abstract multigroup cross section for some energy group structure within some spatial domain. 
openmc.mgxs.MatrixMGXS 
An abstract multigroup cross section for some energy group structure within some spatial domain. 
openmc.mgxs.AbsorptionXS 
An absorption multigroup cross section. 
openmc.mgxs.CaptureXS 
A capture multigroup cross section. 
openmc.mgxs.Chi 
The fission spectrum. 
openmc.mgxs.Current 
A current multigroup cross section. 
openmc.mgxs.DiffusionCoefficient 
A diffusion coefficient multigroup cross section. 
openmc.mgxs.FissionXS 
A fission multigroup cross section. 
openmc.mgxs.InverseVelocity 
An inverse velocity multigroup cross section. 
openmc.mgxs.KappaFissionXS 
A recoverable fission energy production rate multigroup cross section. 
openmc.mgxs.MultiplicityMatrixXS 
The scattering multiplicity matrix. 
openmc.mgxs.NuFissionMatrixXS 
A fission production matrix multigroup cross section. 
openmc.mgxs.ScatterXS 
A scattering multigroup cross section. 
openmc.mgxs.ScatterMatrixXS 
A scattering matrix multigroup cross section with the cosine of the changeinangle represented as one or more Legendre moments or a histogram. 
openmc.mgxs.ScatterProbabilityMatrix 
The grouptogroup scattering probability matrix. 
openmc.mgxs.TotalXS 
A total multigroup cross section. 
openmc.mgxs.TransportXS 
A transportcorrected total multigroup cross section. 
openmc.mgxs.ArbitraryXS 
A multigroup cross section for an arbitrary reaction type. 
openmc.mgxs.ArbitraryMatrixXS 
A multigroup matrix cross section for an arbitrary reaction type. 
openmc.mgxs.MeshSurfaceMGXS 
An abstract multigroup cross section for some energy group structure on the surfaces of a mesh domain. 
Multidelayedgroup Cross Sections¶
openmc.mgxs.MDGXS 
An abstract multidelayedgroup cross section for some energy and delayed group structures within some spatial domain. 
openmc.mgxs.MatrixMDGXS 
An abstract multidelayedgroup 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 multigroup cross section. 
openmc.mgxs.DelayedNuFissionMatrixXS 
A fission delayed neutron production matrix multigroup cross section. 
openmc.mgxs.Beta 
The delayed neutron fraction. 
openmc.mgxs.DecayRate 
The decay rate for delayed neutron precursors. 
Multigroup Cross Section Libraries¶
openmc.mgxs.Library 
A multienergygroup and multidelayedgroup cross section library for some energy group structure. 