openmc.mgxs
– Multi-Group Cross Section Generation¶
Energy Groups¶
Module Variables¶
- openmc.mgxs.GROUP_STRUCTURES¶
Dictionary of commonly used energy group structures:
“CASMO-X” (where X is 2, 4, 8, 16, 25, 40 or 70) from the CASMO lattice physics code
“SHEM-361” designed for LWR analysis to eliminate self-shielding calculations of thermal resonances ([HFA2005], [SAN2007], [HEB2008])
“SCALE-44” designed for criticality analysis ([ZAL1999])
“ECCO-1968” designed for fine group reactor cell calculations for fast, intermediate and thermal reactor applications ([SAR1990])
activation energy group structures “VITAMIN-J-42”, “VITAMIN-J-175”, “TRIPOLI-315”, “CCFE-709” and “UKAEA-1102”
- SAR1990(1,2)
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¶
An energy groups structure used for multi-group cross-sections. |
Multi-group Cross Sections¶
An abstract multi-group cross section for some energy group structure within some spatial domain. |
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An abstract multi-group cross section for some energy group structure within some spatial domain. |
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An absorption multi-group cross section. |
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A capture multi-group cross section. |
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The fission spectrum. |
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A current multi-group cross section. |
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A diffusion coefficient multi-group cross section. |
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A fission multi-group cross section. |
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An inverse velocity multi-group cross section. |
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A recoverable fission energy production rate multi-group cross section. |
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The scattering multiplicity matrix. |
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A fission production matrix multi-group cross section. |
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A reduced absorption multi-group cross section. |
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A scattering multi-group cross section. |
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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. |
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The group-to-group scattering probability matrix. |
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A total multi-group cross section. |
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A transport-corrected total multi-group cross section. |
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A multi-group cross section for an arbitrary reaction type. |
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A multi-group matrix cross section for an arbitrary reaction type. |
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An abstract multi-group cross section for some energy group structure on the surfaces of a mesh domain. |
Multi-delayed-group Cross Sections¶
An abstract multi-delayed-group cross section for some energy and delayed group structures within some spatial domain. |
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An abstract multi-delayed-group cross section for some energy group and delayed group structure within some spatial domain. |
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The delayed fission spectrum. |
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A fission delayed neutron production multi-group cross section. |
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A fission delayed neutron production matrix multi-group cross section. |
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The delayed neutron fraction. |
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The decay rate for delayed neutron precursors. |
Multi-group Cross Section Libraries¶
A multi-energy-group and multi-delayed-group cross section library for some energy group structure. |