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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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.
Hideki Takano, Kunio Kaneko
Nuclear Science and Engineering | Volume 77 | Number 2 | February 1981 | Pages 250-256
Technical Note | doi.org/10.13182/NSE81-A21358
Articles are hosted by Taylor and Francis Online.
Self-shielding factors for inelastic scattering cross sections of iron are calculated from the evaluated nuclear data flies ENDF/B-IV and JENDL-2. The effect of self-shielding by inelastic scattering on the neutron spectra is studied for fast reactor assemblies ZPR-3-54 and MZB, the fast critical assembly of the Japanese fast reactor program. The effect is very pronounced, especially in the steel reflector, where the spectrum is shifted to higher energy. The radial distribution of fission reaction rates calculated by considering that the self-shielding effect becomes smaller for 235U and 239Pu, but larger for 238U in the blanket and reflector regions.
