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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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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.”
S. Isomura, K. Suzuki, M. Shibuya
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 518-523
Tritium Processing | 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-A25185
Articles are hosted by Taylor and Francis Online.
In order to recover tritium from light water, research and development was carried out concerning a tritium separation process based on the principle of hydrogen-water isotopic exchange reaction. The performance and durability of unit operations for the process were studied. A pilot plant having a capacity of 1 m3/year (3.6 L/day) was designed and fabricated based on the results of the tests and studies. Using this plant, tritiated water could be concentrated to the order of a magnitude of 104. Furthermore, the effect of the various operating conditions on the tritium concentration factor was calculated by applying a data analysis program for the pilot plant. This study offered the prospect of a practical application of the process by the hydrogen vapor isotopic exchange reaction to recovery of tritium from light water.