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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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May 2025
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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.
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 138-148
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Material | doi.org/10.13182/NT78-A26710
Articles are hosted by Taylor and Francis Online.
The impact of swelling and creep phenomena, as expressed in the various Nuclear Systems Materials Handbook correlations and their updates, on liquid-metal fast breeder reactor (LMFBR) fuel assembly duct design and LMFBR performance was investigated. As more data on irradiation-induced creep and swelling became available, the predicted creep and swelling rates increased. This leads to increases in interassembly gaps required for the same duct life. Penalties in breeding ratio, doubling times, and fuel cycle cost are the result of the increased interassembly gaps. The most significant penalties are encountered when the updated correlations on creep and swelling are used to update the duct life calculation. To compensate for increases in predicted duct dilation, the duct lifetime has to be reduced significantly.