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.
Brent J. Lewis, Anne C. Harnden-Gillis, Leslie G. I. Bennett
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 366-380
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34937
Articles are hosted by Taylor and Francis Online.
Increasing, but still low, radiation fields due to a release of fission products have been observed in the light-water-filled reactor container of SLOWPOKE-2 reactors fueled with a highly enriched uranium alloy. To investigate this phenomenon, samples of water coolant and headspace gas from the reactor container have been examined by gamma spectroscopy methods for several reactors with various burnup. A model has been developed to describe the kinetic behavior of the activity concentrations of the short-lived iodine and noble gas species in the reactor container water, and the noble gas concentrations in the reactor container headspace. The most likely source of the fission product release is an area of uranium-bearing material exposed to the coolant at the end weld line of the fuel elements that originated at the time of fuel fabrication. The fission product release analysis is consistent with observations from an underwater visual examination of a high-burnup core and a metallographic examination of archived fuel elements.