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This presentation focus on AMPX development for 2024 it also touches on ENDF/B-VIII.1. The slides touches on Thermal Neutron Scattering Library, AMPX Development Highlights, and Transport libraries for SCALE 7.0.0.
The priority for AMPX development for FY2024 has been to support processing the ENDF/B-VIII.1 library. This includes the development to support Thermal Neutron Scattering Library, GNDS-2.1 support and AMPX maintenance, and transport libraries for SCALE 7.0.0.
The AMPX nuclear data processing code reads evaluated nuclear data files and prepares libraries in continuous energy (CE) and multigroup (MG) formats. These libraries are used by the transport and depletion codes in the SCALE code system.
In natural uranium, the 234 U isotope represents only 0.0055%, however, this minor isotope can affect highly enriched uranium metal benchmark calculations. In fact, enriched uranium contains more 234 U than natural uranium as the result of the uranium enrichment process. Therefore, the n+ 234 U nuclear data evaluation is one of the milestones of the APPENDIX B within the Nuclear Criticality Safety Program (NCSP).
Many advanced reactor concepts being considered are characterized by a thermal neutron energy spectrum, which traditional light water reactor systems utilized. Beryllium metal, a material with a long-standing operational history in reactor environments, continues to be of significant interest due to its large scattering cross section, low absorption cross section, and well-characterized behavior under irradiation conditions.