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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.
Masami Mayuzumi, Takeo Onchi
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 382-388
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34532
Articles are hosted by Taylor and Francis Online.
A method is developed to evaluate the maximum allowable temperature and dry storage time of spent fuel under postulated increasing temperature accident conditions, based on creep strain predicted by an empirical creep equation and the creep strain criterion. The creep equation uses the actual stress as the applied stress due to changes in internal rod pressure, fuel rod shape, and volume ratio of free to pellet fuel. It is shown that this method is more realistic and practical than one based on the life fraction rule and the creep rupture criterion. A sensitivity study of the method indicates that the maximum allowable temperature depends on the temperature increase rate, but not the initial normal storage temperature; the allowable storage time, however, depends on both.