Experimental observation of flow instability in a semi-closed two-phase natural circulation loop

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dc.contributor.authorKim, JMko
dc.contributor.authorLee, Sang Yongko
dc.date.accessioned2009-11-23T07:59:17Z-
dc.date.available2009-11-23T07:59:17Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2000-04-
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN, v.196, no.3, pp.359 - 367-
dc.identifier.issn0029-5493-
dc.identifier.urihttp://hdl.handle.net/10203/13137-
dc.description.abstractIn this experimental study, the flow instabilities within a semi-closed two-phase natural circulation loop were examined, with an emphasis placed on the role of the expansion-tank-line resistance. Six different modes of loopwise natural circulation were identified: the single-phase natural circulation, periodic two-phase natural circulation with a nonboiling period between the cycles, two-phase continuous circulation (stable circulation), and three other modes of the two-phase natural circulation characterized by different ranges of the cyclic period. The results were also shown in the instability map in the plane of the heat Aux and the heater-inlet subcooling. When the frictional resistance at the expansion-tank line becomes larger, the circulation becomes stable, especially at the high heat-flux and high inlet-subcooling conditions, and, as a whole, the stable operation region becomes larger in the instability map. Similarly, the longer expansion-tank line stabilizes the system. However, unlike the analytical prediction, the excursive instability was not identified with the semi-closed loop due to the flow restriction at the expansion-tank line. (C) 2000 Elsevier Science S.A. All rights reserved.-
dc.languageEnglish-
dc.language.isoen_USen
dc.publisherELSEVIER SCIENCE SA-
dc.subjectBOILING WATER-REACTORS-
dc.subjectSTART-UP-
dc.subject2-PHASE FLOW-
dc.subjectTHERMOHYDRAULICS-
dc.subjectOSCILLATION-
dc.titleExperimental observation of flow instability in a semi-closed two-phase natural circulation loop-
dc.typeArticle-
dc.identifier.wosid000085729300010-
dc.identifier.scopusid2-s2.0-0034174009-
dc.type.rimsART-
dc.citation.volume196-
dc.citation.issue3-
dc.citation.beginningpage359-
dc.citation.endingpage367-
dc.citation.publicationnameNUCLEAR ENGINEERING AND DESIGN-
dc.embargo.liftdate9999-12-31-
dc.embargo.terms9999-12-31-
dc.contributor.localauthorLee, Sang Yong-
dc.contributor.nonIdAuthorKim, JM-
dc.type.journalArticleArticle-
dc.subject.keywordPlusBOILING WATER-REACTORS-
dc.subject.keywordPlusSTART-UP-
dc.subject.keywordPlus2-PHASE FLOW-
dc.subject.keywordPlusTHERMOHYDRAULICS-
dc.subject.keywordPlusOSCILLATION-
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