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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.
Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 326-340
Technical Paper | Analyse | doi.org/10.13182/NT85-A33730
Articles are hosted by Taylor and Francis Online.
During an unprotected loss-of-flow accident in a liquid-metal fast breeder reactor, the mode of fuel disruption in sodium-voided channels and the subsequent fuel and clad motion are important issues that determine the further accident sequence. To study these phenomena, a series of in-pile fuel disruption experiments, FD2/4, were performed, and the fuel behavior was recorded by high-speed cinematography. Power transients typical of a heterogeneous (e.g., Clinch River Breeder Reactor) and a homogeneous (e.g., SNR-300, Federal Republic of Germany) core design were employed. In the first case, large-scale liquid swelling was observed, whereas in the second case, disruption by solid-state breakup occurred. Both observations provided direct experimental confirmation of the assumption usually made in the accident analysis, and thus removed still existing modeling uncertainties concerning the disruption behavior.