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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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.
Valery V. Fedoro, Vasiliy I. Pokhmursky, Elena V. Dyomina, Marina D. Prusakova, Natalia A. Vinogradova
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1153-1158
Tritium Properties and Interaction with Material | 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-A30563
Articles are hosted by Taylor and Francis Online.
The study of hydrogen diffusion parameters in austenitic steels EP-838, Cr12Mn20W, 316 SS, 12Cr18Ni10Ti was carried out. Temperature dependences of permeability, diffusion coefficients and hydrogen dissolution were determined and their variation with the phase and structure composition of the steel were analyzed. It is shown that change of alloy composition, thermal treatment in hydrogen and modification of surface by nitriding, oxidizing and by irradiation with H+ and N+ ions can lead to a decrease in hydrogen permeability and thus reduce hydrogen isotope losses through the thermonuclear reactor first wall.
