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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.conferencePlace US -
dc.citation.conferencePlace Chicago -
dc.citation.endPage 2190 -
dc.citation.startPage 2182 -
dc.citation.title International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 -
dc.citation.volume 4 -
dc.contributor.author Lee, SW -
dc.contributor.author Park, SD -
dc.contributor.author Kang, S -
dc.contributor.author Kim, SM -
dc.contributor.author Seo, H -
dc.contributor.author Lee, DW -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-20T02:06:44Z -
dc.date.available 2023-12-20T02:06:44Z -
dc.date.created 2013-07-02 -
dc.date.issued 2012-06-24 -
dc.description.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. -
dc.identifier.bibliographicCitation International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012, v.4, pp.2182 - 2190 -
dc.identifier.isbn 978-162276210-1 -
dc.identifier.scopusid 2-s2.0-84869013166 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/36992 -
dc.language 영어 -
dc.publisher International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 -
dc.title Study on critical heat flux enhancement in flow boiling of SiC nanofluids under low pressure and low flow conditions -
dc.type Conference Paper -
dc.date.conferenceDate 2012-06-24 -

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