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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
DOE-NE opens HALEU Consortium with focus on information exchange
The Department of Energy’s Office of Nuclear Energy announced December 7 that its new HALEU Consortium is open for membership. And not just from U.S. enrichers, fuel fabricators, and others working in the front-end fuel cycle, but from “any U.S. entity, association, and government organization involved in the nuclear fuel cycle,” and—at the DOE’s discretion—“organizations whose facilities are in ally or partner nations.” The HALEU Consortium will essentially serve as an information clearinghouse to meet DOE-NE’s ongoing needs for firm supply and demand data as it supports the development of a commercial domestic high-assay low-enriched uranium (HALEU) infrastructure to fuel advanced reactors. The consortium is open for business almost one full year after the DOE first requested public input on its structure.
Technical Session|Panel|Sponsored by RPD
Tuesday, November 15, 2022|1:00–2:45PM MST|Sonoran 7
Samuel E. Bays
The Reactor Physics Division is hosting a panel discussion of the need for and development of a standard to address the initial fuel loading and startup testing of a demonstration first-of-a-kind reactor. Members of this expert panel will include program leaders from actual past reactors. The panel will include commercial reactor physics software developers with NQA-1 software quality experience. The panel will also include regulatory authority on advanced reactor licensing.
Modeling software being used to design advanced reactors (fission batter, micro-, SMRs) today is typically validated using pre-existing peer reviewed integral benchmarks. Although benchmarking activities are very rigorous, the propagated uncertainties for as-built reactor systems can still be quite large. Additionally, the advanced reactor systems being considered today frequently have significant differences when compared with the historical reactor systems for which benchmarks are founded.
Physics testing during reactor startup is the final opportunity for characterizing data uncertainty before hot full power operation. Therefore, a best practices standard is needed to provide guidance on how to leverage traditional startup procedures with software validation methods.
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