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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
M. Ishii, W. L. Chen, M. A. Grolmes
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 297-318
Technical Paper | doi.org/10.13182/NSE79-2
Articles are hosted by Taylor and Francis Online.
During an unprotected undercooling accident in a liquid-metal fast breeder reactor, the motion and relocation of the molten fuel cladding can be important because of their potentially significant effect on reactivity, blockage formation, and subsequent fuel motion. The present study analyzes the cladding relocation problem based on a multichannel film flow model. The important aspects considered in the analysis are the nonuniform transverse cladding melting pattern and sodium vapor flow diversions within a subassembly. It has been shown that the motion of molten fuel cladding and subsequent blockage formations can be significantly influenced by this interconnected channel effect. Several sample calculations have been made to demonstrate these points.