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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.
Meyer Pobereskin, Kenneth D. Kok, William J. Madia
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 149-167
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32101
Articles are hosted by Taylor and Francis Online.
The technical feasibility of a coprocessing concept involving recovery of all the actinides in the spent fuel as a product group has been analyzed. It has been shown that this can be accomplished by a simple modification of the Purex process. The recovered actinide product group can be reconstituted as a fuel for recycle in either light water reactors (LWRs) or liquid-metal fast breeder reactors (LMFBRs), either by addition of moderately enriched uranium for the LWR case or by controlled partial partitioning of uranium in the LMFBR case. Partial partitioning of uranium from a uranium-plutonium extract (that may contain other transuranics, especially neptunium) can be carried out under Purex process conditions that preclude separation of plutonium. A steady-state fuel composition is approached in eight cycles (40 yr) for the LWRs and five cycles (20 yr) for the LMFBRs. Potential for proliferation can be greatly reduced for subnational diversion since the plutonium is not separated from its actinide homologs, nor is the recovered actinide fuel fully decontaminated from fission products. The possibility of proliferation by national diversion can be impeded. Recycle of the actinides reduces, via transmutation, the cumulative amount of actinides produced, defers the bulk of the actinide waste disposal to the end of the useful fuel lifetime, and ameliorates the high-level waste management problem.