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Division Spotlight
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.
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.”
Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 253-264
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3760
Articles are hosted by Taylor and Francis Online.
Containment flooding is an important strategy for severe accident management of a conventional boiling water reactor (BWR) system. The execution of containment flooding requires information about the water level in the primary containment. However, there is no instrument to measure the drywell water level for most Mark-III systems. Furthermore, because of the design feature of the Mark-III containment, the water level in the containment does not necessarily guarantee that there is an equivalent water level in the drywell. Therefore, the development of a drywell water level computational aid becomes very useful. The purpose of this work is to develop and validate the drywell water level computational aid and to investigate the implementation of the proposed computational aid on the containment flooding strategy of a Mark-III system. The Kuosheng nuclear power plant (NPP) is a typical BWR-6 NPP with Mark-III containment, and the Severe Accident Management Guideline (SAMG) of the Kuosheng NPP has been developed based on the BWR Owners' Group Emergency Procedure Guidelines and Severe Accident Guidelines, Revision 2. Therefore, the Kuosheng NPP is selected as the plant for study, and the MAAP4 code is chosen as the tool for analysis.