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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.
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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.
M. D. Freshley
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 209-228
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31146
Articles are hosted by Taylor and Francis Online.
The defect performance of Zircaloy-clad mixed-oxide fuel operating in a pressurized-water environment was studied from the standpoint of fission product activity release to the coolant and the effects of a defect on fuel behavior. The defect experiment described in this paper, which operated satisfactorily, was conducted over a range of linear heat rating conditions, including those that resulted in fuel melting, to investigate the effects of different operating parameters. The results show that the activity release characteristics of the fuel rod are sensitive to the operating mode and that the major species re leased to the coolant are the fission product gases, iodine, the alkali metals, and tellurium. There were no localized dimensional perturbations associated with the cladding in the defect region although the ingress of steam vapor into the rod resulted in oxidation of the mixed-oxide fuel. Comparison of fuel structures formed in the defected rod and in a companion nondefected rod indicates that within the experimental uncertainties associated with this experiment, the effect of defecting on the melting heat rating is <10% and possibly insignificant. An oxygen-rich atmosphere in the interior of the fuel rod during irradiation prevented massive hydriding of the cladding.