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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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.”
Gregg B. Swindlehurst
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 295-301
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2841
Articles are hosted by Taylor and Francis Online.
Duke Power Company has experienced high levels of steam generator tube degradation at its McGuire Nuclear Station, Units 1 and 2, and at Catawba Nuclear Station, Unit 1. Repair of the degraded tubes by sleeving and plugging has resulted in exceeding the tube plugging levels assumed in the licensing basis analyses. Consequently, the licensing basis was reanalyzed with the U.S. Nuclear Regulatory Commission-approved RETRAN-02 and VIPRE-01 methodology to justify continued operation with tube plugging levels up to 20%. A decision was also made to replace the steam generators with a design significantly different from the current steam generators. This necessitated additional analytical efforts to determine the thermal-hydraulic transients to be used in the design of the replacement steam generators, to reanalyze the licensing basis, and to re-certify the control room simulator. The RETRAN-02, RETRAN-03, VIPRE-01, GOTHIC 4.0, and RELAP5/MOD3 codes were used for these analyses. The adverse impact of increased steam generator tube plugging levels and the design of the replacement steam generators were accommodated without significantly impacting plant operation or requiring more restrictive technical specification limits.