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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 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.
S. R. Bierman, B. M. Durst, E. D. Clayton, B. W. Howes
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 40-46
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT80-A32504
Articles are hosted by Taylor and Francis Online.
Criticality experiments with Fast Test Reactor (FTR) fuel pin lattices in water and reflected with concrete have provided benchmark-type data for lattice pitches of 9.53, 12.63, 15.41, and 19.06 mm (water-to-fuel volume ratios of 3.34, 6.92,10.99, and 17.55, respectively). At these center-to-center fuel pin spacings, 554, 260, 191, and 152 fuel pins were required for criticality in rectangular lattices 28, 18, 18, and 14 fuel pins wide, respectively. This corresponds to a decrease of ∼7% from that previously observed in similar lattices with full water reflection. However, the FTR fuel pin design essentially limited the concrete reflection to only the four sides of each fuel lattice.
