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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
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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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Tomohiko Yamamoto, Atsushi Katoh, Yoshitaka Chikazawa, Hiroyuki Hara
Nuclear Technology | Volume 206 | Number 12 | December 2020 | Pages 1875-1890
Technical Paper | doi.org/10.1080/00295450.2020.1726155
Articles are hosted by Taylor and Francis Online.
To respond to seismic and other natural hazard events, designers of the Japan Sodium-cooled Fast Reactor (JSFR), an advanced loop-type reactor, are planning to adopt a steel-plate reinforced concrete structure reactor building and an advanced seismic isolation system to strengthen this building. The design changes have been initiated by lessons learned from the Fukushima Daiichi nuclear power plant (Fukushima I NPP) accident. These enhancements to the design are to ensure that the JSFR structure can withstand external hazards and a severe accident. This evaluation and countermeasure study of external hazards and severe accident response by JSFR are based on the JSFR design before the Fukushima I NPP accident (2010 JSFR design).
The method to evaluate the influence of external hazards on the JSFR design has applied Japanese codes and standards to show that the 2010 JSFR design of the building can withstand external hazards without additional countermeasures. And, for extreme conditions, few countermeasures are needed; however, the countermeasures considered have limited impact on the JSFR design because they do not significantly change the reactor building design.
This paper gives a detailed evaluation of the countermeasures for the external hazards and severe accidents that could impact the JSFR building.