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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
Paul Sasa, August W. Cronenberg+, Michael G. Stevenson
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 233-250
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32470
Articles are hosted by Taylor and Francis Online.
One aspect of nuclear reactor safety assessment is a prediction of fuel behavior associated with postulated overheating events, which includes an assessment of the role of fission product inventory, contained within irradiated fuel elements, on fuel relocation potential. In general, the gaseous fission products, such as xenon and krypton, have been considered the most likely candidates for fuel relocation. However, the fissioning of UO2 fuel in both a fast and slow neutron spectrum also results in the generation of a significant quantity of such metallic fission products as barium, palladium, molybdenum, and other metal species. Metallurgical analysis of irradiated fuel indicates that such metals aggregate into inclusions found throughout the fuel matrix. During normal reactor operation, such metallic inclusions are in a solid state, but at the elevated temperatures expected for overheating accident transients, such inclusions may tend to volatilize, contributing to fuel motion. This paper involves an assessment of effect of such metallic fission product inclusions on fuel motion potential for accident analysis and is the first known attempt at such an assessment. To assess this potential, two limiting calculational assessments were made. Results indicate that if the inclusion constituents are assumed to be segregated elementally, then the presence of the highly volatile species such as antimony, palladium, and iron can result in an estimated 30% expansion just prior to fuel vaporization. However, under the more probable assumption of complete miscibility of constituents, the effect of metallic inclusion vaporization would be of little consequence to fuel motion.