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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
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.”
Ch. Cavagna, O. Gastaldi, L. Martin, V. Grabon
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 274-281
Technical Note | Sodium Technology - Thermal Hydraulics | doi.org/10.13182/NT06-A3707
Articles are hosted by Taylor and Francis Online.
As part of the renovation project of the Phénix plant, the modular-type steam generators were the subject of an expert evaluation program in order to verify their condition after ~100 000 h of power operation and demonstrate their ability to continue operation for the planned lifetime extension (30 000 h).This evaluation, based on the destructive examination of several modules, showed that some parts of the superheater and reheater were affected by some delayed reheat cracking of 321 H stainless steel. Thus, the extension of the operation of the units for the prolonged lifetime of the plant could not be justified.A major repair operation was undertaken. Every superheater and reheater module was disassembled. A cleaning process was developed for removal of residual sodium inside the modules, based on the water vapor nitrogen method, and adapted to the special geometry of the component. The potentially defective parts were replaced by new ones. A specific procedure was used for welding of aged to new materials. The nonreplaced parts were controlled by a specially developed ultrasonic technique; 47 modules were successfully repaired within 1 yr.