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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 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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Latest News
DOE seeks proposals for AI data centers at Paducah
The Department of Energy’s Office of Environmental Management has issued a request for offer (RFO) seeking proposals from U.S. companies to build and power AI data centers on the DOE’s Paducah Site in Kentucky. Companies are being sought to potentially enter into one or more long-term leasing agreements at the site that would be solely funded by the applicants.
Dieter Porsch, Walter Stach, Pascal Charmensat, Michel Pasquet
Nuclear Technology | Volume 151 | Number 2 | August 2005 | Pages 159-167
Technical Paper | Advances in Nuclear Fuel Management - Use of Alternate Fuels in Light Water Reactors | doi.org/10.13182/NT05-A3640
Articles are hosted by Taylor and Francis Online.
The civil and military utilization of nuclear power results in continuously increasing stockpiles of spent fuel and separated plutonium. Since fast breeder reactors are at present not available, the majority of spent fuel discharged from commercial nuclear reactors is intended for direct final disposal or designated for interim storage. An effective form of intermediate plutonium storage is recycling in thermal reactors. Recycling of the recovered plutonium in commercial light water reactors (LWRs) is currently practiced in Belgium, France, Germany, and Switzerland. The number of mixed-oxide (MOX) assemblies reloaded each year in a large variety of reactors demonstrates that plutonium recycling in LWRs has reached industrial maturity. The status of experience gained today at Framatome ANP confirms the reliability of the design codes and the suitability of fuel assembly and core designs. The validation database for increasing exposures of MOX fuel is being continuously expanded. This provides the basis for further extending the discharge exposures of MOX assemblies and for licensing the use of higher plutonium concentrations. Options to support the weapons plutonium reduction programs and for the development of advanced MOX assembly designs are investigated.