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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
L. J. Anastasia, P. G. Alfredson, M. J. Steindler
Nuclear Technology | Volume 7 | Number 5 | November 1969 | Pages 433-442
Chemical Process | doi.org/10.13182/NT69-A28446
Articles are hosted by Taylor and Francis Online.
The fluorination step in a fluidized-bed fluoride volatility process has been studied in a 2-in.-diam reactor using BrF5 and fluorine as fluorinating agents and sintered alumina as the fluidized bed. Fuel pellets containing UO2, PUO2, and nonradioactive fission product oxides were pulverized by oxidation before uranium was selectively fluorinated with dilute BrF5; plutonium was then fluorinated with concentrated recycled fluorine. Fission product elements added to the system simulated burnups of 10 000 and 30 000 MWd/ton. Several aspects of the fluoride volatility process are discussed: effect of variations in process parameters on residual plutonium in the bed, distribution of selected fission products and 106Ru tracer, demonstration of reduced plutonium losses by reuse of a single alumina bed to process three batches of pellets at each of the simulated burnups of 10 000 and 30 000 MWd/ton, plutonium inventory in the reactor, and sampling the fuel charge for material balance and accountability. A processing step for a hybrid process incorporating leaching of the fluidized bed with nitric acid after uranium fluorination with BrF5 was also demonstrated.