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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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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.
W. J. Lackey, F. J. Homan, A. R. Olsen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 120-142
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31181
Articles are hosted by Taylor and Francis Online.
Thermal-gradient-induced redistribution of porosity and fuel components during irradiation of (U,Pu)O2 alters the fuel thermal conductivity, melting point, mechanical properties, and radial heat generation profile sufficiently to influence fast breeder reactor fuel pin performance. Analytical models, which should prove useful in design and analysis of such fuel pins, were developed for predicting radial porosity and Pu: (U + Pu) profiles. The interrelated porosity and actinide redistribution models are kinetic and based on the evaporation-condensation mechanism of material transport. The models were shown to yield predictions in accord with experimentally measured porosity and actinide profiles for an irradiated pin containing stoichiometric fuel. The volume-averaged porosity of the columnar grain region of irradiated pins was 5.9 and ≥3.8% after burnups of 0.7 and 4.2% FIMA, respectively. The columnar grains are thus more porous than previously believed.