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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.”
Thierry Cadiou, Jacky Louvet
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 256-263
Technical Paper | Sodium Technology - Reactor Safety | doi.org/10.13182/NT06-A3705
Articles are hosted by Taylor and Francis Online.
Upon request of the French Safety Authorities, the transient phase, initiated by a total instantaneous blockage (TIB) in a Phénix reactor fuel assembly, has been investigated. Based on an experimental program performed with the SCARABEE reactor, the phenomenology of the accident is first presented. The SIMMER code, which models fast reactor core disruptive accidents, is then used to analyze the transient phase in order to establish the chronology of the events occurring in the faulty assembly after its blockage. This study concludes that the time between the TIB and the onset of structure melting in the neighboring assemblies is sufficient to scram the reactor by control rod insertion before propagation of the accident to the rest of the core.