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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
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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.
J.-J. Huet, L. Coheur, A. De Bremaecker, L. De Wilde, J. Gedopt, W. Hendrix, W. Vandermeulen
Nuclear Technology | Volume 70 | Number 2 | August 1985 | Pages 215-219
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33645
Articles are hosted by Taylor and Francis Online.
Ferritic steels are interesting for fast reactor core application because of the absence of swelling. As canning material, because of the higher temperature involved, new ferritic steels with oxide dispersion strengthening were developed. Fabrication methods are given and their mechanical irradiation and sodium compatibility properties are reviewed.
