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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
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.