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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.
Michel Colin, Michel Coquerelle, Ian L. F. Ray, Claudio Ronchi, Clive T. Walker, Hubert Blank
Nuclear Technology | Volume 63 | Number 3 | December 1983 | Pages 442-460
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33271
Articles are hosted by Taylor and Francis Online.
A detailed analysis of hyperstoichiometric carbide fuel, which operated under sodium-bonding conditions up to 12.5 at. % burnup in the Rapsodie reactor, yields the description of the four contributions to geometric fuel swelling as functions of temperature and burnup: (a) solid fission products and cesium, (b) fission gas swelling, (c) coarse porosity, and (d) the sum of all direct and indirect statistical swelling effects arising from the fracturing of the pellets. Fission gas swelling has to be separated into the contributions of three bubble populations and gas in solution. Between 7 and 11 at.% burnup, the relative amounts of the four swelling contributions are about the same and do not vary with burnup. The total amount of the cross-sectional swelling ΓA of a pellet can be approximately represented as a function of burnup F and linear heat rating x byΓA = b×Fn,where b and n are empirical constants and b decreases as a function of fuel composition in the order MC > MC M2C3 > M(C,N) > MN. The carbide pins investigated in this work, having a smear density of 72% and maximum linear heat rating of 88 kW/m at a cladding temperature of 820 K, reach a maximum burnup of 12.5 at.% with very little fuel-cladding mechanical interaction. The most promising development potential for carbide fuel lies in improving its mechanical properties, i.e., in reducing the propensity of the pellets to fracture.