ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.”
Zhengming Zhang, Shuyan He
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 170-177
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3890
Articles are hosted by Taylor and Francis Online.
Leak-before-break analysis of pressurized vessels and pipes is an important technique to guarantee the safety of reactor pressurized components. This analytical method involves many technical problems that need intensive study. Among these problems, the leak rate of the coolant is far from being well understood. The results of the current leak-rate models may have large errors. Little study has been carried out on the leak rate of gas coolant used in a high-temperature gas-cooled reactor (HTGR). This paper introduces experimental and theoretical studies on the leak rate of a gas medium. The focus is on the results of the experimental studies. A series of experiments for the leak rate of a gas medium were conducted based on preliminary simulation of the penetrated crack. Systematic data were obtained. The laws of a gas medium flowing through a narrow slit are summarized.