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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.”
Kuo-Hsiang Chien, Wei-Keng Lin, Yih-Chean Tsai
Nuclear Technology | Volume 120 | Number 2 | November 1997 | Pages 171-178
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35425
Articles are hosted by Taylor and Francis Online.
The development of a practical and simple on-line void fraction measurement of two-phase flow is of prime interest in applications for nuclear reactor safety research and chemical engineering plants. Experiments were performed at a system pressure of 1 atm. The test sections were made of transparent vertical acrylic pipe with three inner diameters of 1.9, 2, and 2.54 cm. The void fraction was measured by different sizes of side tubes in an air-water two-phase flow; and the void fraction was also compared with the data, which were measured from the liquid holdup between two quick-close valves. The experiment results showed a good agreement for void fractions <0.3, but the error could be large when the flow was in the slug regime.