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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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ANS continues to expand its certificate offerings
It’s almost been a full year since the American Nuclear Society held its inaugural section of Nuclear 101, a comprehensive certificate course on the basics of the nuclear field. Offered at the 2024 ANS Winter Conference and Expo, that first sold-out course marked a massive milestone in the Society’s expanding work in professional development and certification.
Julien Beaucourt, Gabriel Georgescu
Nuclear Technology | Volume 207 | Number 3 | March 2021 | Pages 323-334
Technical Paper | doi.org/10.1080/00295450.2020.1770530
Articles are hosted by Taylor and Francis Online.
Extension of the operational lifetime beyond 40 years is currently a noteworthy project in the field of nuclear safety in France, especially for 900-MW(electric) reactors that will be the first ones to go through the fourth periodic safety review. For 1300-MW(electric) reactors, the safety studies have already been engaged. Probabilistic Safety Assessments (PSAs) play an important role in this process, including assessment of the robustness of the plants against internal and external hazards. Among the hazards, internal explosion induced by hydrogen accumulation due to leakage of pipes and/or singularities, or failure of venting systems in the battery rooms is now taken into account in the PSA developed by the licensee (EDF). The PSAs are then reviewed by IRSN, which is the French Technical support organization. To achieve this purpose, IRSN develops its own Level 1 PSA studies. This paper takes into account the most recent developments of the IRSN analyses, especially regarding the Bayesian quantification of the hydrogen leak frequency derived from an original method developed by Sandia National Laboratories.