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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.
Lianfa Wang, Mingjun Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian (Xi’an Jiaotong Univ)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 33-43
The lateral flow in top core region and upper plenum is detrimental for power control. The temperature heterogeneity in hot-legs induces the deviation of estimation of power level. Therefore, to investigate the lateral flow at the core outlet and temperature heterogeneity in the hot-legs of AP1000, a CFD analysis of the domain from the core inlet to hot-leg outlet was conducted. The core region was simulated by introducing additional source term in the momentum equations instead of being reconstructed in detail. A volumetric power density of hot full power derived from AP1000 middle of life was applied to the active core zone. The main internal components including control guide tubes with eight large opening windows on it and support columns were kept, while other little components including control rod assemblies were omitted to decrease the total mesh quantity. The Reynolds-averaged Navier-Stokes equations was solved with Realizable k-? turbulence model using commercial CFD code FLUENT. The coolant temperature map at the core outlet and the extent of the hot-leg suction effect on the top core region were obtained. Compared with the temperature field at core outlet, the maximum temperature difference at the entrance of the hot-leg drops 10K after the mixing in the upper plenum. The hotter coolant from central fuel assemblies remains at the upper part of the hot-leg, while the cooler coolant from peripheral fuel assemblies stays in the lower part of the hot-leg. The temperature heterogeneity and its evolvement along the hot-leg were analyzed.