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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
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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Nuclear Science and Engineering
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July 2025
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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.
W. Y. Kato, R. J. Armani, R. P. Larsen, P. E. Moreland, L. A. Mountford, J. M. Gasidlo, R. J. Popek, C. D. Swanson
Nuclear Science and Engineering | Volume 45 | Number 1 | July 1971 | Pages 37-46
Technical Paper | doi.org/10.13182/NSE71-A20343
Articles are hosted by Taylor and Francis Online.
Integral values of the capture-to-fission cross-section ratio for 239Pu and 233U have been measured in a soft spectrum fast reactor critical assembly using mass spectrometric techniques to determine the capture rate. Values of 0.363 ± 0.024 and 0.10 ± 0.04 were obtained for 239Pu and 233U, respectively. The value of 0.363 ± 0.024 is in good agreement with the value calculated using the revised Gwin differential cross-section data for 239Pu. The value for 233U is within experimental error in agreement with the value calculated using ENDF/B data.
