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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Technical Session|Panel|Sponsored by FCWMD
Tuesday, June 15, 2021|12:00–1:45PM EDT
Session Chair:
Benjamin B. Cipiti (Sandia National Laboratories)
Session Organizers:
Christina Leggett (Booz Allen Hamilton)
Alternate Chair:
Staff Producer:
Mich Leana (ANS)
The advent of advanced and small reactor designs has led to the need for new, non-traditional fuels such as accident-tolerant fuel, fuel salts, and TRISO fuels, many of which will use HALEU. As such, new fuel cycle needs have arisen for fabricating, storing, and transporting these fuels. For example, molten salt reactors may require a centralized salt processing facility. Moreover, since used HALEU fuel still contains valuable HALEU, it may prove economical to recycle HALEU fuel. This panel session explores front- and back-end fuel cycle needs to enable successful deployment of small and advanced reactors.
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