An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube

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dc.contributor.authorLee, YHko
dc.contributor.authorKim, DHko
dc.contributor.authorChang, Soon-Heungko
dc.date.accessioned2008-03-10T07:58:46Z-
dc.date.available2008-03-10T07:58:46Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2004-04-
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN, v.229, no.1, pp.47 - 58-
dc.identifier.issn0029-5493-
dc.identifier.urihttp://hdl.handle.net/10203/3364-
dc.description.abstractIn order to gain an understanding of the relationship between critical heat flux (CHF) and flow-induced vibration (FIV), an experimental investigation was carried out with vertical round tube at the atmosphere. In the both condition of departure from nucleate boiling (DNB) and the liquid film dryout (LFD), CHF increases up to 12.6% with vibration intensity, represented by vibrational Reynolds number (Re-v) CHF enhancement by tube vibration seems to come from the reinforced flow turbulent mixing and the increment of deposition of droplet into the liquid film. Based on the experimental results, an empirical correlation is proposed for the prediction of CHF enhancement ratio. The correlation predicts the CHF enhancement ratio (E-n) with reasonable accuracy, with an average error rate of 4.5 and 26.5% for RMS. Vibration is an effective method for heat transfer enhancement as well as CHF. Nonetheless, the risk of system failure by FIV has made it very difficult to take advantage of vibration in heat transfer facilities. Therefore, it is necessary to find out optimal fuel design enhancing the CHF but preventing FIV damage in an acceptable vibration range. (C) 2003 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.language.isoen_USen
dc.publisherELSEVIER SCIENCE SA-
dc.subjectFLOW-INDUCED VIBRATIONS-
dc.subject2-PHASE FLOW-
dc.titleAn experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube-
dc.typeArticle-
dc.identifier.wosid000220013100004-
dc.identifier.scopusid2-s2.0-1242297839-
dc.type.rimsART-
dc.citation.volume229-
dc.citation.issue1-
dc.citation.beginningpage47-
dc.citation.endingpage58-
dc.citation.publicationnameNUCLEAR ENGINEERING AND DESIGN-
dc.identifier.doi10.1016/j.nucengdes.2003.11.015-
dc.embargo.liftdate9999-12-31-
dc.embargo.terms9999-12-31-
dc.contributor.localauthorChang, Soon-Heung-
dc.contributor.nonIdAuthorLee, YH-
dc.contributor.nonIdAuthorKim, DH-
dc.type.journalArticleArticle-
dc.subject.keywordPlusFLOW-INDUCED VIBRATIONS-
dc.subject.keywordPlus2-PHASE FLOW-
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