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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Jul 2024
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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 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. 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.”
Sei-Hun Yun et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 373-378
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12383
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to obtain thermo physical properties of ZrCo and ZrCo hydride, which determine heat transfer phenomena in the hydrogen-ZrCo system. Heat capacity, thermal diffusivity and thermal conductivity of ZrCo and ZrCo hydride using Baotou ZrCo (China) are found to have U shaped curvatures with the temperature increase. In the temperature range of 300 - 500 K the thermal conductivity of ZrCoHx was found to be about 2/3 that of ZrCo and the initial hydrogen content of ZrCoHx used in this study was taken to be x=2.0.