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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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
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.”
Travis W. Knight, Jamil Khan, Tanvir Farouk (Univ of South Carolina), James Tulenko (Univ of Florida), Joshua Tarbutton (Univ of North Carolina, Charlotte)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 940-944
An experimental facility has been designed and constructed to investigate vacuum drying of used nuclear fuel for placement in dry cask storage. The motivation for this study was to demonstrate the drying of used nuclear fuel using industry practice and provide the experimental data for development of drying models. A full size BWR fuel assembly (Areva Atrium 10A) with depleted uranium rods and 12 heater rods to simulate decay heat of used fuel is utilized in experiments. The fuel assembly with an interchangeable rod and chamber are designed to examine drying of key features of concern such as failed fuel rods, a BWR water rod, a PWR guide thimble, porous neutron absorber materials, spacer disks, etc. The vacuum chamber simulating the storage cask contains structure similar to baskets for the fuel assembly and surrounding rails to center in the chamber. A test plan is currently being executed and involving separate effects tests of individual features and combined tests with selected features to provide data for the development of drying models to describe drying as a function of cask variables such as temperature, pressure, and relative humidity. The experimental plan follows typical industry practice of vacuum drying in stages stepping down in pressure and separated by hold times to provide indication of excess water retained by observation of pressure rise due to boiling of water.