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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
Robert C. Doerner, Theodore H. Bauer,Charles L. Fink, William F. Murphy, Arthur E. Wright
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 465-482
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32981
Articles are hosted by Taylor and Francis Online.
Received September 28, 1981 Accepted for Publication February 26, 1982 Issues related to the potential for a large-scale sodium vapor explosion in a carbide-fueled liquid-metal fast breeder reactor accident were addressed in the AX1 test in the Transient Reactor Test Facility. Test design and operating conditions were selected to meet the spontaneous nucleation temperature criterion for an energetic, explosive molten fuel-sodium interaction. Although that criterion appears to have been achieved, thermal and mechanical analyses of the test data indicate that the interaction was not especially energetic. Comparison to similar tests on oxide fuel indicates that, under the particular test conditions employed, the conversion of thermal energy to mechanical work is similar for the two fuel types. Transient bulk fuel motion was extensive, with axial fuel motion generally coinciding in time and space with the ejection of the coolant from the original fuel region. Posttest examination of the hardware revealed that nearly all of the fuel had mixed on a microscopic scale with the stainless steel cladding. Relative proportions of iron, chromium, and nickel in the mixture varied widely. The melting point of the mixture was apparently much lower than that of stainless steel.