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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
R. W. Knight, A. E. Richt
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 384-390
Technical Paper | Reactor | doi.org/10.13182/NT72-A16035
Articles are hosted by Taylor and Francis Online.
The irradiation behavior of the High Flux Isotope Reactor (HFIR) control cylinders has been assessed. After 48 000 MWd of irradiation, the nuclear worth of the control cylinder has not changed significantly. The maximum surface oxide buildup was 0.003 to 0.005 in. thick and occurred over the tantalumaluminum dispersion. The hardness of the 6061 aluminum cladding was found to have increased from 45 DPH at the low burnup end of the cylinder to 110 DPH over the tantalumaluminum region which is located ∼5 in. below the area of maximum fastneutron fluence. Extensive metallographic examination revealed no degradation or reaction in either the tantalum aluminum or Eu2O3-Al portions of the cylinder.