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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. Berger, G. Koehly, C. Musikas, R. Pottier, R. Sontag
Nuclear Technology | Volume 8 | Number 4 | April 1970 | Pages 371-379
Chemical Processing | doi.org/10.13182/NT70-A28663
Articles are hosted by Taylor and Francis Online.
Four slugs containing a sum total of 20.950 g of plutonium as Al-Pu 10% alloy have been irradiated in the EL-3 reactor to an integrated flux of 5 × 1021 n/cm2. After 2.5 years of cooling, the processing has been carried out in the hot cell “Petrus.” It consisted of (a) an alkaline and/or nitric dissolution of the “napkin-rings,” (b) a plutonium separation by two extraction cycles with trilaurylamine (5 vol%), each consisting of a plutonium extraction from a nitric medium and stripping by a solution containing sulfuric and nitric acids, (c) a transplutonium element separation by two HDEHP (8 vol %) extraction cycles, each consisting of an actinide-lanthanide extraction from an aluminum and lithium nitrate solution and a selective stripping of the transplutonium elements by a lithium nitrate solution containing diethylenetriaminopentaacetic ions (DTPA), and (d) an americium/curium separation by anion exchange resin using a nitric solution containing a complexing agent as eluent. From these runs 2.6 g of plutonium, 150 mg of americium, and 15 mg of curium have been recovered. The overall yields of plutonium and transplutonium elements were >97 and 98%, respectively, and the β - γ decontamination factors >105. In general, these results show clearly the effectiveness of solvent extraction in actinide reprocessing.
