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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.
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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.
Takanori Nagasaki, Satoshi Konishi, Hiroji Katsuta, Yuji Naruse
Fusion Science and Technology | Volume 9 | Number 3 | May 1986 | Pages 506-509
Technical Note | Tritium System | doi.org/10.13182/FST86-A24739
Articles are hosted by Taylor and Francis Online.
An intermetallic compound of zirconium-cobalt was prepared, and the pressure-composition isotherms for the ZrCo-H system were measured in the pressure range from 10 Pa (0.1 Torr) to ∼130 kPa (1000 Torr) and in the temperature range from 130 to 400°C. The equilibrium hydrogen pressures of plateaus under the experimental conditions were one or two orders of magnitude higher than that of a uranium-hydrogen system. A pronounced hysteresis between hydrogenating isotherms and dehydrogenating ones was observed. Based on the results, ZrCo is proposed as a substitute for uranium for the purpose of recovering, storing, and supplying gaseous tritium.
