ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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
NRC moves ahead on HALEU enrichment, rulemaking, and guidance
The Nuclear Regulatory Commission is requesting comments on the regulatory basis for a proposed rule for light water reactor fuel designs featuring high-assay low-enriched uranium (HALEU), including accident tolerant fuel (ATF) designs, and on draft guidance for the environmental evaluation of ATFs containing uranium enriched up to 8 percent U-235. Some of the HALEU feedstock for those LWR fuels and for advanced reactor fuels could be produced within the first Category II fuel facility licensed by the NRC—Centrus Energy’s American Centrifuge Plant in Piketon, Ohio. On September 21, the NRC approved the start of enrichment operations in the plant’s modest 16-machine HALEU demonstration cascade.
D. Mandelli (INL), C. Wang (INL), S. Hess (Jensen Hughes), R. Sugrue (Jensen Hughes), D. Morton (Northwestern Univ.), I. Popova (Texas State Univ.), C. Pope (Idaho State Univ.), J. Miller (Idaho State Univ.), S. Ercanbrack (Idaho State Univ.), D. Cole (Univ. of Pittsburgh), J. Yurko (Univ. of Pittsburgh)
Proceedings | 2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021) | Virtual Meeting | Pages 299-308