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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.”
Kyungdoo Kim, Won-Pyo Chang, Kun-Joong Yoo, Seon-Hwa Lee, Chong-Bae Lee
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 125-131
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2856
Articles are hosted by Taylor and Francis Online.
A multiple failure event, a stuck-open pressurizer spray valve along with pressurizer pressure transmitter failure, which occurred on February 25, 1995, at Kori nuclear unit 2, is simulated using the best-estimate thermal-hydraulic computer code RETRAN03/MOD000. The simulation was performed to validate the predictive capabilities of RETRAN03 against plant data. The results would be useful in evaluation of the emergency operation procedures. The transient was simulated for 5000 s until the reactor coolant system pressure was stabilized and hot standby condition could be achieved. The simulation results and their corresponding plant data, especially for the evolutions of all the major thermal-hydraulic parameters, are compared and analyzed. Relatively good agreement between the plant data and the code prediction has been obtained; however, the simulation cannot duplicate the plant data for the low-flow condition that was encountered near the end of the transient.