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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.
R. C. Kern, M. V. Bonaca
Nuclear Technology | Volume 9 | Number 6 | December 1970 | Pages 796-806
Fuels Cycle | doi.org/10.13182/NT70-A28711
Articles are hosted by Taylor and Francis Online.
Two models which are designed to perform fuel inventory calculations without the use of detailed and expensive computer programs have been developed. The accuracies of these models have been evaluated by comparing results obtained with them to measurements of discharged fuel from the Yankee Rowe reactor. In general, the models predict the 235U depletion to within ±2% of the measured values and the total plutonium production to within ±5% for fuel batches consisting of about 70 fuel assemblies. Uncertainties in the computational results have been ascertained to be about ±2% for the total 235U content and ±3% for the total plutonium production.