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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.
Keynotes Session
Wednesday, August 23, 2023|8:00–8:50AM EDT|Columbia 5-8
Session Chair:
Igor Bolotnov (NCSU)
Dr. Nam Dinh is a professor of nuclear engineering at North Carolina State University. Prior to NCSU, Dr. Dinh was a chair professor of nuclear power safety at Sweden’s Royal Institute of Technology, and a Laboratory Fellow at the Idaho National Laboratory. Professor Dinh research in nuclear reactor thermal hydraulics contributed to severe accident management in LWRs and ALWS plants. Professor Dinh's current research is focused on data-driven modeling and validation of advanced simulation codes, applications of machine learning and artificial intelligence in nuclear reactor engineering and safety. He is a Fellow of the American Nuclear Society (ANS) and a recipient of the ANS Thermal-Hydraulics Division’s Technical Achievement Award.
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Attachment — Dinh Description
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