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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.