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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.
A. D. Emery, D. B. Scott, J. R. Stewart
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 474-478
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30844
Articles are hosted by Taylor and Francis Online.
A series of simulated transient tests was performed to evaluate the effects of heating rates and pressures on the expansion of Zircaloy-4 fuel tube cladding during a period of overheating similar to that which might occur in certain hypothetical coolant failure accidents. The fuel tubes, which were filled with Al2O3 pellets to simulate UO2, were internally pressurized to various pressures. They were inductively heated in a helium atmosphere, so that the temperature increased with time, for 30 sec or until tube failure occurred. Consequently, the range of heating times considered significant for the postulated class of accidents (from a few seconds to 30 sec) was covered, the time for any particular test being determined by the level of pressurization and the applied heating rate. For the test conditions described, maximum swelling occurred at a heating rate and pressure combination that caused perforation in just 30 sec.