Experimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids

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dc.contributor.authorLee, Kwi Limko
dc.contributor.authorChang, Soon-Heungko
dc.date.accessioned2013-03-12T00:11:25Z-
dc.date.available2013-03-12T00:11:25Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2010-10-
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN, v.240, no.10, pp.3397 - 3404-
dc.identifier.issn0029-5493-
dc.identifier.urihttp://hdl.handle.net/10203/100761-
dc.description.abstractAn experimental study was performed using R-134a in an annulus channel to investigate the heat transfer characteristics in the post-CHF region. The experiments were conducted under the outlet pressures of 1.1-2.0 MPa, the mass fluxes of 100-400 kg/m(2)s and the inlet temperatures of 25-51 degrees C. Experiments were conducted in three cases of the annular channel test without spacers, the test with I-type spacer grids, and the test with split-swirl type spacer grids. The empirical correlation of the heat transfer in the post-CHF region was developed with 301 data point obtained in the annular test without spacer grids. The heat transfer coefficient was calculated based on the heater-rod temperature and the saturated vapor property. The average and root-mean-square (RMS) errors of the predictions were 0.17 and 3.4%, respectively. I-type spacer grids and split-swirl mixing vanes (with blockage-area ratios of 4.0 and 5.8%) were tested, which showed the enhancing effects on the heat transfer at the downstream location of the spacers and the results from the spilt-swirl-type mixing vane tests were more effective than the I-type grid tests. (C) 2010 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE SA-
dc.subjectDRYOUT REGIME-
dc.subjectNONEQUILIBRIUM-
dc.subjectPREDICTION-
dc.titleExperimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids-
dc.typeArticle-
dc.identifier.wosid000284079000110-
dc.identifier.scopusid2-s2.0-77957699059-
dc.type.rimsART-
dc.citation.volume240-
dc.citation.issue10-
dc.citation.beginningpage3397-
dc.citation.endingpage3404-
dc.citation.publicationnameNUCLEAR ENGINEERING AND DESIGN-
dc.contributor.localauthorChang, Soon-Heung-
dc.contributor.nonIdAuthorLee, Kwi Lim-
dc.type.journalArticleArticle; Proceedings Paper-
dc.subject.keywordPlusDRYOUT REGIME-
dc.subject.keywordPlusNONEQUILIBRIUM-
dc.subject.keywordPlusPREDICTION-
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