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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.endPage 436 -
dc.citation.number 4 -
dc.citation.startPage 429 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 44 -
dc.contributor.author Lee, Seung Won -
dc.contributor.author Park, Seong Dae -
dc.contributor.author Kang, Sarah -
dc.contributor.author Kim, Seong Man -
dc.contributor.author Seo, Han -
dc.contributor.author Lee, Dong Won -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-22T05:10:12Z -
dc.date.available 2023-12-22T05:10:12Z -
dc.date.created 2013-06-12 -
dc.date.issued 2012-05 -
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 characteristic of nanofluids is their ability to significantly enhance the CHF. Nanofluids are nanotechnology-based colloidal dispersions engineered through the stable suspension 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.% Al2O3/water nanofluid, and SiC/water nanofluid. 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 Al2O3/water nanofluid. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.44, no.4, pp.429 - 436 -
dc.identifier.doi 10.5516/NET.04.2012.516 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-84862562264 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/3093 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84864505427 -
dc.identifier.wosid 000305368900011 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Critical heat flux enhancement in flow boiling of Al 2O 3 and SiC nanofluids under low pressure and low flow conditions -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Critical Heat Flux -
dc.subject.keywordAuthor Flow Boiling -
dc.subject.keywordAuthor Nanofluids -
dc.subject.keywordAuthor Low Pressure and Low Flow -
dc.subject.keywordPlus LOOK-UP TABLE -
dc.subject.keywordPlus SURFACE -
dc.subject.keywordPlus TUBES -

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