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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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Fusion Science and Technology
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.”
Ph. Cetier, J. Charuau, Y. Belot, S. Fauvel, C.H. Wu
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1148-1152
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30562
Articles are hosted by Taylor and Francis Online.
This presentation describes experiments to investigate the sorption of tritium on carbon dust of different particle sizes and specific surface areas. The conditions of exposure were determined at the first wall of the tokamak. These conditions include low tritium pressures and depending on the operation phase, temperatures varying between 25°C and 1000°C. The simulation of these conditions inside an exposure chamber were necessary in order to design and construct a specific exposure device that could be adapted to these unusual conditions. Initial sorption data were obtained for carbon dust derived from a JET first-wall tile. The amount of tritium sorbed into or onto the carbon dust is between 0.1 and 10 mg T per kg C for a 24 hour-exposure duration. It increases with dust temperature. Other determinations, dealing particularly on the influence of exposure duration, are required to interpret this initial data.