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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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Fusion Science and Technology
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.
Asashi Kitamoto, Y. Takashima, M. Shimizu
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2048-2053
Fusion Reactor | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24586
Articles are hosted by Taylor and Francis Online.
The composite packing with the hydrophobic platinum catalyst for the isotope exchange reaction in H2O-H2 system was improved to be appreciably active. Therefore, it bacame realistic to design a process for tritium recovery by the dual-temperature exchange method. The separation performance of dual-temperature 5-stage cascade (S3-E2) was simulated. The process was desinged to be operated under the condition of P = 0.1 MPa, TH = 70 °C, TC = 15∼20 °C. The cascade could attain tritium recovery ratio of 0.99 and enriching ratio larger than 103.
