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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.”
Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 324-336
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2844
Articles are hosted by Taylor and Francis Online.
The RETRAN analyses of three areas of thermal-hydraulic concerns are presented. The first evaluated whether a 360-deg through-wall crack could be detected based on system response with leakage through the crack. The second analysis was to identify the hydraulic load on the shroud and possible consequences early in the main steam-line break. The last was the evaluation of the thermal limit (CPR) of limiting transients with leakage. Some of the analyses were used for justification of continued operation of the current cycle, and some will be useful in the evaluation of the repair design.