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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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
SC Nuclear Summit focuses on V.C. Summer
The second annual South Carolina Nuclear Summit held last week featured utility executives and legislators from the state, as well as leaders from Brookfield Asset Management, which is being considered to restart construction on the two abandoned reactors at the V.C. Summer nuclear power plant in Fairfield County. The summit, at the University of South Carolina’s Colonial Life Arena, attracted more than 350 attendees. The event was hosted by the university’s Molinaroli College of Engineering and Computing.
Mingzhong Zhao, Moeko Nakata, Fei Sun, Yuji Hatano, Yoji Someya, Kenji Tobita, Yasuhisa Oya
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 246-251
Technical Paper | doi.org/10.1080/15361055.2019.1705727
Articles are hosted by Taylor and Francis Online.
The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal desorption spectroscopy showed that dislocation loops and voids were formed in damaged W. It was found that the D permeation behavior in W was affected by irradiation defects. The effective diffusivity and permeability in the damaged W were lower than that in undamaged W. However, the difference in effective diffusivity and permeability between the undamaged sample and the damaged sample was reduced with increasing the heating temperature. Under 965 K, which was enough for D detrapping from voids, the permeability for damaged W was consistent with that for undamaged W.
