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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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 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.”
Dong Won Lee, Suk Kwon Kim, Young-Dug Bae, Yang Il Jung, Jeong Yong Park, Yong Hwan Jeong, Byung Yoon Kim
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 165-169
ITER Systems | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12346
Articles are hosted by Taylor and Francis Online.
For the second qualification of the blanket First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m2. In order to investigate the fabrication procedure and methods, two types of mock-up were fabricated; one was with twelve Be tiles for high heat flux test to check the joining integrity between Be tiles and the bending Cu block and the other was for testing the thermal-hydraulic prediction by commercial code, ANSYS-CFX when it has a complex geometry such as hypervapotron, which was used for designing the semi-prototype. The former was successfully fabricated and the test conditions were obtained through the preliminary analysis with ANSYS-CFX. The later was successfully fabricated and the test with KoHLT-2 (Korea Heat Load Test facility) was performed; mass flow rate of inlet coolant was the same as the ITER condition and heat flux was loaded up to 0.65 MW/m2. The results show that the temperature of the mock-up can be predicted using the ANSYS-CFX even with the complex geometry.