ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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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.”
Sang-Yong Lee, Chang-Hwan Ban
Nuclear Technology | Volume 148 | Number 3 | December 2004 | Pages 335-347
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3571
Articles are hosted by Taylor and Francis Online.
Several researchers have endeavored to develop methodologies to extrapolate the uncertainties gathered from reduced-size facilities to the full-size nuclear power plant. They are all based on the general guideline of the code scaling, applicability, and uncertainty (CSAU) method. Although there is an extensive compilation of experimental and theoretical databases and a detailed guide about the best-estimate calculation of loss-of-coolant accidents, these applications are dissimilar to each other. The absence of a procedure to implement the requirement of direct data comparison with integral- and separate-effects tests in determining the code uncertainty is the main cause of the differences. To overcome this problem, a code-accuracy-based uncertainty estimation (CABUE) technique has been developed, in which the code accuracy becomes the measure of the selection of code parameters and the determination of the ranges of them. An application of this technique to a Westinghouse three-loop nuclear power plant has been successfully performed.