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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.
Heiner Meldner
Nuclear Science and Engineering | Volume 69 | Number 3 | March 1979 | Pages 438-441
Technical Note | doi.org/10.13182/NSE79-A19963
Articles are hosted by Taylor and Francis Online.
Inertial confinement fusion (ICF) pellet center burnup of fission reactor waste, namely, 14-MeV neutron fission of the very long-lived actinides that pose storage problems, is calculated for realistic target designs. A major advantage of pellet center burnup is safety: Only milligram quantities of highly toxic and active material need to be present in the fusion chamber, whereas blanket burnup reqUires the continued presence of tons of actinides in a small volume. One ICP plant can transmute the actinide waste of up to ten power equivalent fission reactors, i.e., large-scale development appears to provide a foreseeable-future technology that greatly reduces the necessity of high integrity waste storage (burial) time: from 107 to just over 102 yr.