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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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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.
Harold E. Clark, Grover Tuck
Nuclear Technology | Volume 9 | Number 6 | December 1970 | Pages 814-820
Chemical Processing | doi.org/10.13182/NT70-A28713
Articles are hosted by Taylor and Francis Online.
An empirical formula has been developed for determining the individual diameter of essentially unreflected cylinders in a critical planar array. The formula is. The independent variables are N, the number of cylinders in the array; S, the edge-to-edge spacing between adjacent cylinders; H, the solution height in the array; C, the concentration of the solution [U ∼93 wt% 235U]; G, the geometry factor determined by the shape of the array; and ki (i = 1, 2, ... , 8), the constants determined by the type of solution, either uranyl nitrate or uranyl fluoride. These independent variables, the formula ranges, and approximations are discussed. The critical cylinder diameter, calculated by this formula, is within ±8% of the experimentally measured diameter for 112 experimental data points. Therefore, the formula can be used as a guideline for nuclear criticality safety.