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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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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.J. Maynard, W.T. Shmayda, A.G. Heics
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1391-1398
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-A30606
Articles are hosted by Taylor and Francis Online.
The effects of tritium aging on ZrCo have been characterized to determine the suitability of ZrCo as a long term tritium storage medium. Four 1 gram ZrCo storage beds were aged for three years with varying amounts of tritium. Equilibrium tritium pressures were found to increase by approximately threefold at a given temperature and composition in the range of 100–300°C. At 25°C, the pressure increase is predicted to be twenty-fold. Tritium aged ZrCo retains the majority of decay 3He within the bulk. As this 3He concentration increases, the rate of helium release increases. Longer term tritium aging may result in a 3He release rate equal to its production rate from tritium decay. In such a case, the pressure within a sealed storage bed would steadily increase. These tritium aging effects indicate that practical ZrCo storage bed design should include conservative design pressure specifications, to safely contain the maximum possible 3He pressure.
