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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.
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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.”
Satoshi Fukada, Masabumi Nishikawa, Akio Sagara, Takayuki Terai
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1054-1058
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22745
Articles are hosted by Taylor and Francis Online.
Rates of the recovery of tritium from a blanket of a fusion reactor with a 1 GWt power are estimated. The recovery methods are a permeation window, a Flibe-He counter-current-extraction tower and a rotational centrifugal flow system. There is high possibility in that the rate-determining step of the permeation window is tritium diffusion in Flibe. The tritium diffusion in liquid Flibe drops is also the dominant process in the counter-current-extraction tower. The determination of the tritium diffusion rate in purified or unpurified Flibe (or actual blanket environment) is a key to estimate the tritium recovery rate accurately.