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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.”
Ioannis A. Papazoglou
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 329-350
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3097
Articles are hosted by Taylor and Francis Online.
A special Markov reliability model is used to simulate the effects of frequency of testing and allowable bypass time of the analog channels and logic trains on the performance of a pressurized water reactor, reactor protection system (RPS). The effects of these technical specifications (TSs) on the unavailability of the RPS and on the frequencies of spurious scrams, core damage, anticipated transients without scram, and large early releases are assessed. The use of these results to support decision making concerning changing the TSs in light of the relevant policy statement by the U.S. Nuclear Regulatory Commission on risk-informed decision making is demonstrated. The analysis includes point-value calculations sensitivity and uncertainty analysis.