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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
G. Kennedy, K. Van Tichelen (SCK-CEN), J. Pacio (KIT), I. Di Piazza (ENEA), H. Uitslag-Doolaard (NRG)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 505-519
In recent years, extensive thermal-hydraulic experimental tests have been performed on the LBE-cooled, wire-wrapped fuel assembly of MYRRHA. These thermal-hydraulic tests were performed using fuel assembly mock-ups, in large-scale LBE experimental test facilities at SCK•CEN (Belgium), ENEA (Italy) and KIT (Germany). The fuel assembly pressure drop characteristics and flow induced vibration characteristics were tested with a full-scale 127-pin mock-up test section. The existing pressure drop correlations of Rehme and Cheng and Todreas (simplified model) predict the experimental pressure drop data very well and are considered suitable for use in the design and safety analysis of the MYRRHA system. Flow induced vibrations are very limited in the wire-wrapped bundle and fuel pin fatigue damage from vibration during operation is not expected. Further analysis and testing is required to determine if damage from fretting corrosion could be expected.
Heat transfer characteristics of the fuel assembly were investigated experimentally in two separate 19-pin heated rod test sections, cooled by LBE. The existing Kazimi-Carelli correlation predicts the global average Nusselt numbers very well, but the correlation is not developed to capture local hot-spots. For the fuel assembly safety analysis, a hot-spot factor is defined and analysed to determine the hot-spot temperature penalty, to further determine operational safety margins.