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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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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.”
Igor Salamun, Andrej Stritar
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 118-137
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2913
Articles are hosted by Taylor and Francis Online.
Diagnostic methodologies for nuclear power plants (NPPs) are usually based on mathematical models and generation of residuals. To avoid complicated, time-consuming, and costly diagnostic simulations of the physical phenomena in NPPs, an algorithm that determines a significant pattern for major transients is investigated. Coefficients of the transfer function between the observed parameters are used as the pattern features. The algorithm uses a recurring least-squares method known from the literature to determine the transfer functions. The case study includes 30 different scenarios in the primary and secondary systems. Each scenario produces its own significant recognized pattern. The RELAP5/MOD3.2 code is used to simulate the input data for the Krsko pressurized water reactor NPP. The algorithm recognizes the prepared scenarios, and it classifies them into groups.