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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 to collaborate with Atomic Alchemy on isotope production
Fast reactor developer Oklo, which recently went public on the New York Stock Exchange, announced on May 13 that it has signed a memorandum of understanding with Atomic Alchemy to cooperate on the production of radioisotopes for medical, energy, industry, and science applications.
Hangbok Choi
Nuclear Technology | Volume 204 | Number 3 | December 2018 | Pages 283-298
Technical Paper | doi.org/10.1080/00295450.2018.1484646
Articles are hosted by Taylor and Francis Online.
The performance of uranium-plutonium mixed carbide fuel was analyzed based on experimental data produced from the Japan Research Reactor No. 2, the Japan Materials Testing Reactor, and the Fast Flux Test Facility irradiation tests during 1983 to 1992. The analysis includes a review of earlier fuel irradiation test results, material property data, and physics models, and a simulation by a finite element method fuel performance code FEMAXI-6GA to predict the historic results. The simulation results were compared to the measured fission gas release, fuel swelling, and dimensional change of the cladding. The simulation results are reasonably consistent with the measurement. However, a few differences between the simulations and measurements were encountered, which are attributed to the lack of detailed experimental conditions, characteristics of fuel materials, material property data, and physics models. Based on sensitivity analyses of the results to experimental conditions and material property data, it is recommended to develop an experimental plan for the systematic measurements of thermal conductivity, including the effect of porosity, impurities, and stoichiometry, fission gas diffusion, and irradiation-induced swelling and densification, supplemented by advanced modeling and simulation techniques to support advanced fuel development in a cost-effective way.