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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
J. Novak, Ian J. Hastings, Elio Mizzan, Real J. Chenier
Nuclear Technology | Volume 63 | Number 2 | November 1983 | Pages 254-265
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33285
Articles are hosted by Taylor and Francis Online.
Irradiated UO2 fuel elements with and without deliberately induced 0.8-mm-diam defects were heated in air at 220, 230, and 250°C for times up to 685 h. Pretest burnup was typically 190 MW·h/kg U (7600 MW·d/TeU) at a maximum linear power of 45 kW/m; cooling times were 1 to 3 yr. In fuel elements with six defects, diametral increases in excess of 5% and sheath splitting occurred after ∼200 h at 250°C, consistent with oxidation to U3O8. There was a maximum 2% increase in elements with one defect at 250°C, but no change in an irradiated but undefected control. Dimensional increases in defected elements at 220 and 230°C were typically <1% for times in excess of 600 h, consistent with oxidation primarily to nonswelling U3O7. The rate of weight change at 230 and 250°C was up to 50 times greater in defected irradiated elements, compared with that for defected unirradiated elements. There was no significant effect of power history or cooling time in the elements studied.