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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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.
J. R. DiStefano, J. H. Devan
Nuclear Technology | Volume 8 | Number 1 | January 1970 | Pages 29-44
Fuel | doi.org/10.13182/NT70-A28631
Articles are hosted by Taylor and Francis Online.
Refluxing capsule tests were conducted to evaluate the corrosion properties of alloys Nb, Nb-1% Zr, Nb-10% W-1% Zr, Ta-8% W-2% Hf, Mo-0.5% Ti-0.1% Zr, Nb-10% W-10% Hf-0.5% Y, and W-26% Re in boiling potassium at 1100 to 1400°C. Nb-1% Zr was also evaluated in refluxing sodium, rubidium, and cesium at 1200°C. Alloys of niobium or tantalum that contained strong oxide formers, such as zirconium or hafnium, showed negligible corrosion effects up to 1300°C for times as long as 5000 h. Nb-1% Zr exposed to the other alkali metals was similar. Weight changes in insert specimens from condenser sections were small and in most tests were traced to the migration of oxygen in the system. Unalloyed niobium, on the other hand, was very heavily attacked under similar conditions. Mass transfer of tungsten was observed in a W-26% Re capsule. Capsule geometry can be an important variable in comparing the results between various corrosion investigations.