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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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.”
P. A. Finn, E. H. Van Deventer
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 783-790
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-A25230
Articles are hosted by Taylor and Francis Online.
The heterogeneous reaction between oxygen/helium gas, tritium and stainless steel was studied at the back surface of a stainless steel tube. The yield of tritiated water was determined as a function of oxygen concentration, tritium concentration, protium concentration, flow rate, and temperature. This report describes the results for two sets of runs done at 550°C with and without 15 ppm protium in the oxygen/helium gas. At oxygen concentrations of 40 ppm, the presence of excess protium in the oxygen/ helium produced a reduced yield of tritiated water. At oxygen concentrations >1000 ppm, the two yields were equivalent, 98%.
