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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.
S. K. Bhattacharyya, D. C. Wade, R. G. Bucher, D. M. Smith, R. D. McKnight, L. G. LeSage
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 517-524
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32360
Articles are hosted by Taylor and Francis Online.
Integral physics parameters of several representative, idealized meltdown liquid-metal fast breeder reactor (LMFBR) configurations were measured in mockup critical assemblies on the Zero Power Reactor 9 at Argonne National Laboratory. The experiments were designed to provide data for the validation of analytical methods used in the neutronics part of LMFBR accident analyses. Large core distortions were introduced in these experiments (involving 18.5% core volume), and the reactivity worths of configuration changes were determined. The neutronics parameters measured in the various configurations showed large changes on core distortion. Both diffusion theory and transport theory methods were shown to mispredict the experimental configuration eigenvalues. In addition, diffusion theory methods were shown to result in a nonconservative misprediction of the experimental configuration change worths.