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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


Surface wettability change during pool boiling of nanofluids and its effect on critical heat flux

DC Field Value Language Kim, S. J. ko Bang, In Cheol ko Buongiorno, J. ko Hu, L. W. ko 2014-10-16T01:54:25Z - 2014-10-15 ko 2007-09 ko
dc.identifier.citation INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.50, no.19-20, pp.4105 - 4116 ko
dc.identifier.issn 0017-9310 ko
dc.identifier.uri -
dc.description.abstract The pool boiling characteristics of dilute dispersions of alumina, zirconia and silica nanoparticles in water were studied. Consistently with other nanofluid studies, it was found that a significant enhancement in critical heat flux (CHF) can be achieved at modest nanoparticle concentrations (<0.1% by volume). Buildup of a porous layer of nanoparticles on the heater surface occurred during nucleate boiling. This layer significantly improves the surface wettability, as shown by a reduction of the static contact angle on the nanofluid-boiled surfaces compared with the pure-water-boiled surfaces. A review of the prevalent CHF theories has established the nexus between CHF enhancement and surface wettability changes caused by nanoparticle deposition. This represents a first important step towards identification of a plausible mechanism for boiling CHF enhancement in nanofluids. ko
dc.description.statementofresponsibility close -
dc.language 영어 ko
dc.title Surface wettability change during pool boiling of nanofluids and its effect on critical heat flux ko
dc.type ARTICLE ko
dc.identifier.scopusid 2-s2.0-34248354656 ko
dc.identifier.wosid 000247750800038 ko
dc.type.rims ART ko
dc.description.wostc 254 *
dc.description.scopustc 273 * 2015-05-06 * 2014-10-15 *
dc.identifier.doi 10.1016/j.ijheatmasstransfer.2007.02.002 ko
dc.identifier.url ko
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