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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.”
D. Labrune, B. Limacher, H. Guidon, G. Moll
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 676-680
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30482
Articles are hosted by Taylor and Francis Online.
Gas separation tests were performed with nitrogen containing small concentrations of deuterium or tritium on a small-scale polyimide membrane module purchased from Ube Industries, similar to that developed at the Japan Atomic Energy Research Institute (JAERI). Experimental results showed that this separation process could be potentially applied to tritium removal systems used in tritium handling facilities. It would allow to reduce significantly the gas volume to be treated by the conventional oxidation-adsorption process, and, therefore, the number or size of associated equipments. Hazards arising from handling of highly toxic tritiated water vapor due to conversion of elemental tritium, would hence be lowered.