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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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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.
Eugen Wild, Klaus J. Mack
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 216-223
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32152
Articles are hosted by Taylor and Francis Online.
The friction and wear behavior of various material combinations was studied in a liquid-sodium loop up to fluid temperatures of 900 K to guarantee selfalignment and safe operation of liquid-metal-cooled fast breeder reactor (LMFBR) components, such as subassemblies, control and shutdown units, instruments, and centering pads. Pin-on-disk, plate-on-plate, and tilting plane test section systems were used. Numerous material combinations exhibiting good corrosion resistances in liquid sodium were investigated under identical operating conditions. Those revealing the lowest wear rates and the lowest friction coefficients were subject to parameter tests. The influences on friction and wear behavior of friction velocity, contact force, sodium temperature, equipment criteria, and tribochemistry were studied. The experimental results are shown for a Stellite 6-Stellite 6 combination. They revealed friction and wear coefficients to be clearly below the set limits. However, this material combination has a high cobalt content and is therefore no optimum choice with respect to contamination problems of the primary system of an LMFBR. Other experiments are necessary to develop materials with zero contamination effects.