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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.
Steven T. Polkinghorne, Thomas K. Larson, Brent J. Buescher
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 240-251
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34508
Articles are hosted by Taylor and Francis Online.
The RELAP5 computer code is used to simulate four small-scale loss-of-coolant accident (LOCA) experiments conducted at Idaho National Engineering Laboratory (INEL). The purpose of the study is to help assess RELAP5 under conditions similar to those expected during a large-break LOCA at INEL’s Advanced Test Reactor (ATR). During an ATR large-break LOCA, it is expected that the primary system pressure will rapidly decrease from the initial operating pressure (∼2.55 MPa) to subatmospheric conditions governed by the primary coolant temperature. Flashing will occur in the high points of the system and air ingress from the break is possible. The RELAP5 code had not previously been assessed under these conditions. The results show that RELAP5 accurately predicted pressures, water levels, and air ingress behavior, thus providing confidence in the ability of the code to simulate an ATR large-break LOCA.