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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Jan Ru Tang, Neil E. Todreas, Michael J. Driscoll
Nuclear Technology | Volume 107 | Number 1 | July 1994 | Pages 49-62
Technical Paper | Special on ANP ’92 Conference / Fission Reactor | doi.org/10.13182/NT94-A34997
Articles are hosted by Taylor and Francis Online.
Key conceptual features are developed for a passive light water cooled and moderated pressure tube reactor having a total thermal output of 4029 MW(thermal) and net electric power of 1260 MW(electric), compatible with passive safety features that can ensure integrity of the fuel and reusability of the major reactor components without the requirement of delivery of emergency coolant makeup inventory. The concept of passive heat removal applied in this design combines heat storage, thermal conduction, radiation, natural circulation of light water in a moderator system under one atmosphere, and a natural draft air cooling system. Feasibility studies concerning normal heat transport, accident decay heat removal, materials compatibility, and reactor physics for criticality and feedback effects were carried out for the associated design features. The basic feasibility of the subject concept was confirmed by these analyses.