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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.”
Yonezo Tsujikura
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 141-157
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3234
Articles are hosted by Taylor and Francis Online.
When designing the safety system for the next generation of pressurized water reactors (PWRs), it is essential to rationalize the safety system by taking factors such as safety, reliability, and economy into account. To do so, a comprehensive methodology for designing an accident mitigation system was developed on the basis of the following studies. Threats to the reactor core, which are inherent to PWRs, were systematically analyzed. Following this, efforts to specify the requirements needed to mitigate the threats were made with the specification of components composing the mitigation systems. On the basis of a loss-of-coolant accident as an example of the severest accident, thermohydro analyses without any mitigation systems were made to determine the requirements needed to keep the core safe. Information related to the system's design parameters were successfully obtained. On the basis of these studies, candidates for mitigation systems that respond in accordance with the scales and phases in progress of accidents were systematically selected and discussed. In the future, the methodology presented herein may be extended to cover the structuring of overall plant safety systems.