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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
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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.
Douglas K. Warinner, S. C. Saxena
Nuclear Science and Engineering | Volume 76 | Number 3 | December 1980 | Pages 361-366
Technical Note | doi.org/10.13182/NSE80-A21328
Articles are hosted by Taylor and Francis Online.
The method-of-Ergun fluidization theory is applied to a postulated porous blockage in the core of a liquid-metal fast breeder reactor (LMFBR). By the parallel flow channeling through the subassemblies of the reactor, a definite pressure gradient is imposed across each subassembly. This pressure gradient is found to be sufficient to fluidize (and entrain particles from) any postulated loose-particle-formed blockage. A parametric study that considers a range of reactor materials and sodium coolant temperatures demonstrates that a radially large planar blockage cannot be reasonably postulated to exist in an LMFBR. Further, any radially large particulate blockage would be subjected to fluidization and ultimate destruction by entrainment and turbulent flow forces. Thus, flow starvation via a slowly growing blockage can be dismissed as an incredible event.