ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Guido Ledergerber, Franz Ingold, Richard W. Stratton, Hans-Peter Alder, Claude Prunier, Dominique Warin, Mireille Bauer
Nuclear Technology | Volume 114 | Number 2 | May 1996 | Pages 194-204
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35249
Articles are hosted by Taylor and Francis Online.
In the fabrication of fuel containing transuranium (TRU) elements, flow sheets and techniques that allow a shielded and/or remote fabrication will probably need to be applied. One approach, which has been demonstrated on the laboratory and semiprototype scale, is the wet fabrication route of coprecipitation of the matrix element uranium mixed with plutonium to form either dense spherical particles or to produce hybrid pellets made from pressed gel microspheres. The ceramic material produced holds the TRU elements homogeneously distributed in the matrix. In conjunction with the Département d’Études des Combustibles of the French Commissariat à I’Énergie Atomique in Cadarache, France, the Paul Scherrer Institut in Switzerland is further developing a mixed nitride ceramic and mixed oxide with high concentrations (up to 50%) of plutonium with the aim of a joint irradiation test of TRU elements in the French Phénix reactor.