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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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.”
Sham Sunder
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 211-221
Technical Paper | Radiation | doi.org/10.13182/NT98-A2863
Articles are hosted by Taylor and Francis Online.
Alpha, beta, and gamma dose rates in water, in contact with the reference used fuel in the Canadian Nuclear Fuel Waste Management Program (i.e., Bruce A CANDU fuel, burnup 685 GJ/kg U), are calculated as a function of cooling time. Procedures to calculate the dose rates for used CANDU fuels of different burnups from results obtained for the reference fuel are described. These procedures can be adapted to estimate dose rates for fuels other than CANDU fuel. The dose rate information is needed to compare the results of leaching and corrosion experiments, conducted by different groups, with used fuels of different burnups and/or cooling times and to predict the effects of radiolysis of groundwater on used fuel oxidation and dissolution in a disposal vault.
