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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.”
Y. Hirooka, J. Won, S. Keller, R. Boivin, M. Khandagle, J. N. Brooks
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 540-545
Fusion Material and Plasma-Facing Component | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40213
Articles are hosted by Taylor and Francis Online.
Divertor materials erosion and lifetime is a critical issue in designing plasma-facing components (PFCs) for ITER. Currently, three materials are considered as candidates to be used for the divertor target plate, namely, beryllium, carbon and tungsten. In this paper, major issues associated with the use of these candidates are reviewed and relevant data obtained from recent PISCES experiments will be discussed with the main emphasis on the wall lifetime issue.