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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.
D. Y. Hsia, P. Griffith
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 431-437
Technical Note | doi.org/10.13182/NSE81-A21380
Articles are hosted by Taylor and Francis Online.
Steam generator pressure drop versus flow rate instability during a loss-of-coolant accident in a pressurized water reactor has been investigated. The steam generator is simulated by four tubes, each with a different height, on top of a two-dimensional quarter-circle inlet plenum. This work deals with only an adiabatic air-water system. The pressure drop was found to be practically constant in the range of 3 jg 10 m/s. Within this range, the pressure drop depends only on the liquid flow rate. The plenum details do not matter. A model using an average flow for each tube does a good job in estimating the pressure drop. The flow distribution can be conservatively estimated by the proposed model based on a single, average tube pressure drop minimum.