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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
R. A. Schrack, C. D. Bowman
Nuclear Science and Engineering | Volume 75 | Number 3 | September 1980 | Pages 275-277
Technical Note | doi.org/10.13182/NSE80-A19059
Articles are hosted by Taylor and Francis Online.
Theoretical calculations and experimental measurements have been made to look for reported chemical dependence in the yield of delayed neutrons from thermal-neutron-induced fission in 235U. Using an Einstein model of the lattice phonon distribution, calculations have been made that indicate no significant dependence of the fission cross section on the lattice phonon distribution. Two types of experimental measurements were made. The fission fragment yield was compared for thermal-neutron-induced fission in U3O8 and UO2. The delayed neutron yields from U3O8 and UO2 were also compared. In neither measurement was there a significant difference in yield for the two chemical states of uranium.
