We are planning to construct a scaled-down moderator test facility to simulate the CANDU-6 moderator circulation phenomena during steady state operation and accident conditions at the Korea Atomic Energy Research Institute. In the present work a preliminary experiment using a 1/40 scaled-down moderator tank has been performed to identify the potential problems of the flow visualization and measurement in the scaled-down moderator test facility. With a transparent moderator tank model, a flow field is visualized with a Particle Image Velocimetry (PIV) technique under an isothermal state, and the temperature field is measured using a Laser Induced Fluorescence (LIF) technique. A preliminary CFD analysis is also performed to find out the flow, thermal, and heating boundary conditions with which the various flow patterns expected in the prototype CANDU-6 moderator tank can be reproduced in the experiment.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5581-2
PROCEEDINGS PAPER
Measurement of Velocity and Temperature Profiles in the Scaled-Down CANDU-6 Moderator Tank
Hyoung Tae Kim,
Hyoung Tae Kim
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
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Jae Eun Cha,
Jae Eun Cha
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
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Bo Wook Rhee,
Bo Wook Rhee
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
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Hwa-Lim Choi,
Hwa-Lim Choi
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
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Han Seo,
Han Seo
Ulsan National Institute of Science & Technology (UNIST), Ulsan, Republic of Korea
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In Cheol Bang
In Cheol Bang
Ulsan National Institute of Science & Technology (UNIST), Ulsan, Republic of Korea
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Hyoung Tae Kim
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Jae Eun Cha
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Bo Wook Rhee
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Hwa-Lim Choi
Korea Atomic Energy Research Institute (KAERI), Daejeon, Republic of Korea
Han Seo
Ulsan National Institute of Science & Technology (UNIST), Ulsan, Republic of Korea
In Cheol Bang
Ulsan National Institute of Science & Technology (UNIST), Ulsan, Republic of Korea
Paper No:
ICONE21-15620, V004T09A050; 7 pages
Published Online:
February 7, 2014
Citation
Kim, HT, Cha, JE, Rhee, BW, Choi, H, Seo, H, & Bang, IC. "Measurement of Velocity and Temperature Profiles in the Scaled-Down CANDU-6 Moderator Tank." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 4: Thermal Hydraulics. Chengdu, China. July 29–August 2, 2013. V004T09A050. ASME. https://doi.org/10.1115/ICONE21-15620
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