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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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
William L. Baldewicz, Ahmed R. Wazzan, David Okrent
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 263-267
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32326
Articles are hosted by Taylor and Francis Online.
Grain size is one of the most important parameters affecting fission gas release and swelling of nuclear fuels. On the other hand, fission gas bubbles in previously irradiated fuel interact with moving grain boundaries and affect subsequent grain growth. Equations are developed that describe equiaxed grain growth in oxide fuel that has undergone previous irradiation (burnup) at temperatures too low to promote grain growth. The resulting expressions relate the grain growth rate at the new high temperature to the percent burnup (or fission gas content) experienced during the prior low-temperature period.