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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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Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coating

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Title
Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coating
Author
Lee, Min HoHeo, HyoBang, In Cheol
Issue Date
2018-12
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Citation
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.127, no.Part B, pp.1102 - 1111
Abstract
Critical heat flux (CHF) enhancement is needed to ensure a proper safety margin for the in-vessel retention through external reactor vessel cooling (IVR-ERVC), which is a decay heat removal strategy in the nuclear power plants. To enhance the cooling capability of IVR-ERVC, graphene oxide (GO) was coated on a boiling surface, with a reduced geometry to that of the reactor pressure vessel (RPV). This study experimentally investigated the effect of the GO coating on the CHF. A R-123 refrigerant was used as a working fluid to mitigate the wetting effect. Various concentrations of nanofluids were used in the experiments (0.01, 0.03, and 0.05 vol%) to examine the effect of thermal activity on the CHF. Because the thermal effusivity of the GO coating layer was higher than that of the copper heater, the thermal activity of the surface increased with thicker GO coating layers. The CHF limit of the GO-coated surface was enhanced by 38% compared to that of the bare surface due to increased thermal activity. Periodic bubble behavior was also observed near the CHF and visual criterion for CHF observation is detailed herein. (C) 2018 Elsevier Ltd. All rights reserved.
URI
https://scholarworks.unist.ac.kr/handle/201301/25138
URL
https://www.sciencedirect.com/science/article/pii/S0017931018308317
DOI
10.1016/j.ijheatmasstransfer.2018.07.151
ISSN
0017-9310
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