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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Yeon Soo Kim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 9-17
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3073
Articles are hosted by Taylor and Francis Online.
The literature dealing with fission gas release from UO2+x is reviewed. A simplified semiempirical model predicting fission gas release from UO2+x fuel to the fuel rod plenum as a function of stoichiometry excess x is developed to apply to the fuel of a defective light water reactor fuel rod in operation. An effective diffusion coefficient including a parabolic dependence of x is obtained based on existing data in the literature. The new diffusion coefficient is a composite expression of intrinsic, fission-enhanced, and nonstoichiometry-induced diffusion. The effective diffusion coefficient is incorporated into the Booth model to assess the time-dependent fractional fission gas release. The new model predictions are compared with existing data.