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Bang, In Cheol
Nuclear Thermal-Hydraulics & Reactor Safety Lab
Research Interests
  • Nuclear Thermal-Hydraulics
  • Nuclear Safety
  • Nuclear System Design & Analysis
  • Nanofluids
  • Critical Heat Flux

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Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank

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Title
Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank
Author
Kim, Hyoung TaeCha, Jae EunSeo, HanBang, In Cheol
Issue Date
2015-01
Publisher
HINDAWI PUBLISHING CORPORATION
Citation
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, v.2015 , pp.439863
Abstract
In order to simulate the CANDU-6 moderator circulation phenomena during steady state operating and accident conditions, a scaled-down moderator test facility has been constructed at Korea Atomic Energy Institute (KAERI). In the present work an 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
URI
https://scholarworks.unist.ac.kr/handle/201301/17398
URL
http://www.hindawi.com/journals/stni/2015/439863/
DOI
10.1155/2015/439863
ISSN
1687-6075
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