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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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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.
R. N. Anderson, N. A. D. Parlee, J. M. Gallagher
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 29-35
Technical Paper | Fuel | doi.org/10.13182/NT72-A31064
Articles are hosted by Taylor and Francis Online.
The thermodynamics and kinetics of nitrogen-nitride reactions in liquid uranium-tin alloys have been investigated experimentally. In the presence of dissolved metal impurities in the alloys, the nitrogen has been found to react with the uranium to form UN which can, under proper conditions, be precipitated as a pure phase from the melt, leaving impurities behind. Thus, the concept of nitride precipitation offers a possible metallurgical separation method applicable to the reprocessing of spent fast reactor fuels. Based on laboratory studies for uranium and the extrapolated behavior for plutonium, it appears possible to attain 99% uranium recovery and 98% plutonium recovery, with decontamination factors of 106.