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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.”
Kan Ashida, Masao Matsuyama, Kuniaki Watanabe
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 735-740
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25222
Articles are hosted by Taylor and Francis Online.
Graphite is the primary candidate for the first wall of magnetically confined fusion devices. For this application, it is important to know the surface properties and trap/release behavior of hydrogen isotopes to understand fuel recycling/inventory in the graphite first wall. The surface analysis of as-received graphite revealed that the inherent hydrogen content is larger in isotropic compared to the anisotropic graphite. This is due to the presence of non-graphitized carbon atoms in the isotropic graphite which act as the trapping sites of hydrogen atoms. Ion bombardment causes the reduction of the crystallite size of graphite (damage modification), leading to amorphous-like structure. The thermal desorption spectra of hydrogen isotopes consisted of three desorption peaks for the modified graphite. The desorption mechanisms and parameters of three peaks are determined. These parameters were used to estimate the fuel inventory in the graphite.