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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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A wave of new U.S.-U.K. deals ahead of Trump’s state visit
President Trump will arrive in the United Kingdom this week for a state visit that promises to include the usual pomp and ceremony alongside the signing of a landmark new agreement on U.S.-U.K. nuclear collaboration.
N. E. Stauff, L. Buiron, B. Fontaine, G. Rimpault
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 241-250
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A15781
Articles are hosted by Taylor and Francis Online.
Sodium-cooled fast reactors (SFRs) remain the favorite candidate in France for a Generation IV (Gen IV) reactor fleet to be deployed within this century. Compared with earlier generations (Phénix, Superphénix, and European fast reactor), Gen IV SFRs require attractive economics together with enhanced safety and nonproliferation criteria. An innovative approach named Mathematical Estimation of Transients for Reactor design Orientation (METRO) has been developed with the objective of taking into account both SFR core economic performance and SFR transient incident behavior at an early stage of the core design process. Loss-of-flow, loss-of-heat-sink, and overpower transients are evaluated. Simplified modeling of transients has been developed and benchmarked against reference calculations with satisfactory results. The METRO approach to assessing the efficiency of design orientations is described in the following and applied to a carbide-fueled reactor core.