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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.
K.H. Schrader, A. Perujo
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1416-1419
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30610
Articles are hosted by Taylor and Francis Online.
This paper presents the design and first tests of a portable uranium getter bed where the drawbacks of the standard available transport getters have been either mitigated or eliminated. The heating of the bed is made internally, ie, heating the uranium by a close contact of the heater element with the material, therefore reducing the temperature of the wall that is shielded from the heat source. Keeping the wall relatively cold reduces the tritium losses by permeation and the heat load to the glovebox. With this design the maximum operating temperature of the external wall is ≈ 373 K, this corresponds to a nominal reduction in permeation of four orders of magnitude.