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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.
V. K. Dhir, W. E. Kastenberg, D. W. Varela
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 447-452
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32352
Articles are hosted by Taylor and Francis Online.
Generally, the blockages that may form in the reactor core when molten fuel is ejected into the coolant channels during a transient overpower accident can be divided into two categories. The first type of blockage forms when semi-molten fuel particles hit a wire wrap and freeze on the wire wrap, whereas the second type of blockage forms when solid or semi-solid particles get stuck in the coolant channels. The thermal-hydraulic analysis of these proposed blockages indicates that under certain specific conditions, the blockages can lead to melting of the wire wrap and cladding and also to in-channel voiding. The second type of blockage, if formed as a plug, may remelt before being quenched by subcooled or saturated sodium.