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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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Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
John A. Palmer, C. J. Bridgman, D. M. Verrelli
Nuclear Technology | Volume 2 | Number 2 | April 1966 | Pages 81-88
Technical Paper | doi.org/10.13182/NT66-A27484
Articles are hosted by Taylor and Francis Online.
A method is described that predicts the kinetic response of a circulating-water-cooled and -moderated reactor to large changes in reactivity. This response is displayed in the form of time histories of power, peak fuel plate temperature, energy, reactivity, and period. The validity of the method is verified by the agreement of calculated and experimental data when it is applied directly to the SPERT-IV reactor. The general applicability and usefulness of the method are illustrated by the analysis of the Air Force Nuclear Engineering Test Reactor. A comparison with SPERT-IV, a parametric study, and an accident evaluation are shown as sample results.
