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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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Latest News
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.
G. L. Copeland, M. M. Martin
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 547-552
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32913
Articles are hosted by Taylor and Francis Online.
A common plate-type fuel for research and test reactors is U3O8 dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the 235U enrichment from above 90% to below 20%) for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. Work at Oak Ridge National Laboratory has determined the maximal uranium loading for these fuels that can be fabricated with commercially proven materials and techniques and that can be expected to perform satisfactorily in service. Assuming satisfactory performance in irradiation tests to the required burnup, we anticipate being able to increase the uranium loading in U3O8-Al dispersions to the 3.1 Mg U/m3 level (75 wt% U3O8). This loading level will allow many research reactors to be fueled by uranium of <20% enrichment.