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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.
Satoshi Konishi, Masahide Hara, Kenji Okuno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 890-894
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963050
Articles are hosted by Taylor and Francis Online.
Electrolytic reactor that converts methane and water simultaneously to liberate hydrogen isotopes at very high conversion ratio was developed and tested. Addition of the second zirconia cell provides the capability of processing broad mixing ratio between water and methane by supplying or extracting oxygen. Combination of palladium permeation and electrolytic reactions was tested under reactor relevant tritium concentration in an integrated loop. Satisfactory processing of simulated plasma exhaust processing and tritium recovery was verified. Based on the result, a concept of the fuel processing system for fusion reactor is proposed and discussed.