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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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Study on critical heat flux enhancement in flow boiling of SiC nanofluids under low pressure and low flow conditions

Author(s)
Lee, SWPark, SDKang, SKim, SMSeo, HLee, DWBang, In Cheol
Issued Date
2012-06-24
URI
https://scholarworks.unist.ac.kr/handle/201301/36992
Citation
International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, v.4, pp.2182 - 2190
Abstract
Critical heat flux (CHF) is the thermal limit of a phenomenon in which a phase change occurs during heating (such as bubbles forming on a metal surface used to heat water), which suddenly decreases the heat transfer efficiency, thus causing localized overheating of the heating surface. The enhancement of CHF can increase the safety margins and allow operation at higher heat fluxes; thus, it can increase the economy. A very interesting characteristics of nanofluids is their ability to significantly enhance the CHF. Nanofluids are nanotechnology-based colloidal dispersions engineered through stable suspending of nanoparticles. All experiments were performed in round tubes with an inner diameter of 0.01041 m and a length of 0.5 m under low pressure and low flow (LPLF) conditions at a fixed inlet temperature using water, 0.01 vol. % Al 2O 3/water and SiC/water nanofluids. It was found that the CHF of the nanofluids was enhanced and the CHF of the SiC/water nanofluid was more enhanced than that of the Al 2O 3/water nanofluid.
Publisher
International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012
ISBN
978-162276210-1

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