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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.
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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.”
C. J. Caldwell-Nichols, M. Glugla, L. Dörr, U. Berndt
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 216-219
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A915
Articles are hosted by Taylor and Francis Online.
The PETRA facility at the Tritium Laboratory Karlsruhe (TLK) has finished its useful life and the glove box and auxiliary systems are being refurbished. During the lifetime of PETRA the glove box became contaminated with a small amount of tritium but the source has not been positively identified. Removing large redundant components would be hazardous as this would require removing the glove box panels and thus exposing the inner surfaces to moist air which would release tritium. Over several months defined amounts of water have been introduced into the glove box daily which has liberated significant quantities of tritium which has subsequently been absorbed by the in-built tritium retention system. This technique has slowly reduced the tritium liberated at each step. The large components, such as a getter bed, catalyst bed and a permeator, have been detritiated as far as possible in-situ in readiness for disposal once it is safe to remove them from the glove box.