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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.”
K. Samec, R. Z. Milenkovic
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 288-303
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A8964
Articles are hosted by Taylor and Francis Online.
The successful outcome of the liquid-metal leak test was a key event in the MEGAPIE (MEGAwatt PIlot Target Experiment) project, a multinational endeavor aimed at developing a reliable neutron spallation source operating with dense liquid metal. Indeed, the leak test validated the containment design, which was a regulatory requirement for demonstrating that a liquid-metal source could be operated safely. Furthermore, unique temperature and stress measurements were recorded that agreed well with test predictions published ahead of the test. This paper outlines the approach taken for predicting the consequences of a liquid-metal leak, with particular emphasis on a simplified one-phase calculation method that may be useful in the future for predicting the impact of accidental liquid-metal leaks at modest expense in terms of CPU time.Most of the assumptions underpinning the original analytical predictions necessarily erred on the conservative side. Therefore, the boundary conditions applied to the original analysis, such as the exit flow rate of the liquid-metal jet, are critically reviewed in this paper to improve on the existing agreement between the predictions and the experimental data.