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NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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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.
D. R. Marr, D. A. Cantley, J. C. Chandler, D. C. McCurry, R. P. Omberg
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 133-143
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Fuel Cycle | doi.org/10.13182/NT79-A32143
Articles are hosted by Taylor and Francis Online.
Three studies were performed to evaluate the breeding ratio of fast breeders containing thorium. In a study of a small breeder, thorium metal and thorium oxide core designs were found to have similar breeding ratios. The slight advantage exhibited by the metal design was not considered significant, since the design was based on a limited amount of thorium metal swelling data. In a study of a 1200-MW(electric) plant, a plutonium-uranium oxide design was compared to a uranium-thorium metal design. The uranium-thorium design had a lower breeding ratio but also had a negative sodium void effect. In the third study, the effect of replacing thorium oxide radial blankets with thorium metal radial blankets was evaluated. This was found to have little effect on the breeding ratio.