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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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May 2025
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June 2025
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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Brighton I/II
Session Chair:
Alex Levinsky
Alternate Chair:
Chang-ho Lee (ANL)
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Modeling and Analysis of a Micro-Reactor Using the DireWolf Code Suite
Nathan Roskoff (Westinghouse Electric Co.), Vefa Kucukboyaci (Westinghouse Electric Co.), Alex Levinsky (Westinghouse Electric Co.), Vincent Laboure (INL), Jackson Harter (INL), Adam Zabriskie (INL), Lise Charlot (INL)
Paper
Simulation of a TRISO-Fueled Heat-Pipe Microreactor Using MOOSE-Based Reactor Physics Code Griffin
Yan Cao (ANL), Nicolas Stauff (ANL), Yinbin Miao (ANL), Kun Mo (ANL), Justin Thomas (ANL), Bo Feng (ANL), Zhaopeng Zhong (ANL), Chang-ho Lee (ANL)
Preliminary Neutronic-Thermal-Mechanical Coupling of a Small Heat-Pipe Reactor Using OpenMC and MOOSE
William Reed Kendrick (MIT), Benoit Forget (MIT)
Presentation Video (Visible to Attendees)
Design, Simulation, and Analysis of a Microreactor Experiment at the National Criticality Experiments Research Center
Mikaela Blood (LANL), Alexis Maldonado (LANL), Nicholas Thompson (LANL), Holly Trellue (LANL)
Attachment — ppt
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