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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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 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. 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.”
Kenzo Ibano, Yasushi Yamamoto, Satoshi Konishi
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 243-246
Divertor & High Heat Flux Components | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12360
Articles are hosted by Taylor and Francis Online.
Plasma parameters for a low-Q tokamak reactor GNOME were studied to meet the allowable heat load constraints of the divertor component. EQLAUS/ERATO codes and DRIVER88 codes were used for the core plasma models to determine the power flux into SOL regions for this calculation. Then, the heat flux to the divertor plate was estimated with a parameter of the radiation power at SOL/divertor regions. A simple Core-SOL-Divertor (C-S-D) model has been used for this purpose. Finally, three operation regions with the required radiation power to meet the allowable peak heat load were proposed.