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Nuclear Criticality Safety
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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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.
John W. Prados, J. L. Scott
Nuclear Technology | Volume 3 | Number 8 | August 1967 | Pages 488-494
Technical Paper and Note | doi.org/10.13182/NT67-A27780
Articles are hosted by Taylor and Francis Online.
The Prados-Scott model for coated-particle behavior has been modified to include the effects of irradiation-induced creep on the stress-strain history of pyrolytic-carbon coatings. Calculations are performed in a stepwise fashion, with double trial-and-error iterations required for each time (or fluence) increment. Lack of accurate information on the mechanical behavior of pyrolytic carbons under irradiation still limits the quantitative applicability of the results; however, the computational sequence has been designed to permit simple updating of mechanical behavior subroutines as more reliable data are obtained. Using the best available creep information, we found that the performance of typical pyrolytic-carbon-coated particles is significantly improved by creep under conditions of irradiation which will obtain in advanced high-temperature gas-cooled reactors. On the other hand, with the high burnup rates and low fast fluences characteristic of most coated-particle proof tests, the effects of creep are small and are likely to be undetectable. In such cases, an elastic model can be used effectively to predict failure.