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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
H. J. Schenk, K. L. Huppert, W. Stoll
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 174-185
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16309
Articles are hosted by Taylor and Francis Online.
In the Federal Republic of Germany (FRG), the reprocessing of spent fuel assemblies and the recycling of the recovered plutonium are essential for the final disposal of high-level nuclear waste. In addition, the recycling of uranium and plutonium is an effective measure to avoid proliferation of plutonium for weapons and to reduce the needs of uranium. Therefore, the technology of recycling has been developed in the FRG since 1966. In the prototype boiling water reactor (BWR) of Kahl, in the BWR nuclear power plant at Gundremmingen, and the pressurized water reactor plant at Obrigheim mixed-oxide fuel (MOX) assemblies have been operated with good success. Also, the experience gained at Alkem’s MOX fuel fabrication plant is very positive. Reprocessing tests of spent MOX fuel rods have indicated that a nearly homogeneous mixture of PuO2 and UO2 should be used to achieve a good solubility of MOX fuel in nitric acid. In all, very important experience in safeguarding plutonium and MOX fuel material was gained.