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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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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.”
K. Nagarajan, T. Subramanian, B. Prabhakara Reddy, P. R. Vasudeva Rao, Baldev Raj
Nuclear Technology | Volume 162 | Number 2 | May 2008 | Pages 259-263
Technical Note | First International Pyroprocessing Research Conference | doi.org/10.13182/NT08-A3954
Articles are hosted by Taylor and Francis Online.
Reducing the cooling time of spent fast breeder reactor (FBR) fuel, thus reducing the doubling time and introducing metallic fuels into FBRs, is essential for meeting the increasing energy demand of India. Development of pyrochemical reprocessing technology for processing the spent FBR fuels is another prerequisite. Accordingly, studies on the molten salt electrorefining process for metallic fuels and the oxide electrowinning process for oxide fuels have been carried out at the Indira Gandhi Centre for Atomic Research, Kalpakkam. A laboratory-scale argon atmosphere facility for molten salt electrorefining process studies is operational. Using this facility, studies on all the unit operations of the process have been carried out on uranium alloys. A code, PRAGAMAN, based on thermochemical modeling has been developed to simulate the electrotransport behavior of elements during the electrorefining process. Based on our studies, the eutectic MgCl2-NaCl-KCl ternary salt has been proposed as the alternate electrolyte for the conventional 2CsCl-NaCl electrolyte for oxide processing. A facility to demonstrate the remotization of all the process steps of the molten salt electrorefining process flow sheet for metallic fuels at 1- to 3-kg scale is being set up. Basic electrochemical studies on the reduction behavior of the chlorides and oxychlorides of uranium and the lanthanides in molten salts have also been carried out. This paper describes the studies carried out so far and the plans for the near future.