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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
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.”
G. R. Smolik, S. J. Piet, R. M. Neilson, Jr.
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1398-1402
Safety | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29538
Articles are hosted by Taylor and Francis Online.
Postulated long-term loss of coolant accidents (LOCA) for the International Thermonuclear Experimental Reactor (ITER) may involve the ingress of air or steam into the plasma chamber. Reactions of these gases with the hot plasma facing components will cause oxidation, transport, and release of activated species. To predict radioactivity releases, we measured volatility rates from a tungsten alloy. Tests were performed in air or steam between 600 and 1200°C for 1 to 20 h. We used these volatilization rates to calculate radioactivity releases from severe hypothetical ITER accidents. We found that both the first wall and divertor plates fabricated from or coated with tungsten may release significant radioactivity in severe hypothetical LOCAs. Without radioactivity confinement or credit for in-plant deposition, the site boundary Early Effective Dose Equivalent (EDE) acceptance criterion of 100 mSv (10 rem) is exceeded by a factor of about thirty in either an air or steam accident. With radioactivity confinement and reference LOCA conditions of 700°C for the divertor plates and 600°C for the first wall, air and steam provide doses of 50 and 30 mSv, respectively. We conclude that tungsten-bearing components are not attractive from a passive safety standpoint. With radioactivity confinement and reference conditions, however, these components can meet the anticipated regulatory criterion.