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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Aaron J. Friedland
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 85-87
Technical Note | doi.org/10.13182/NSE73-A22595
Articles are hosted by Taylor and Francis Online.
Three-region restructured fuel, with given thermal characteristics, may be represented by an effective conductivity integral function Y(T). For any fuel surface temperature Ts and linear heat generation rate q, the maximum fuel temperature Tv is found from the relation Yv - Ys = q. Region radii and molten fuel fraction appear in the groups qR2/R and qF as functions of Yv - Ye.