DC Field | Value | Language |
---|---|---|
dc.contributor.author | Kwon, YM | ko |
dc.contributor.author | Chang, Soon-Heung | ko |
dc.date.accessioned | 2013-03-03T04:48:40Z | - |
dc.date.available | 2013-03-03T04:48:40Z | - |
dc.date.created | 2012-02-06 | - |
dc.date.created | 2012-02-06 | - |
dc.date.issued | 2000-06 | - |
dc.identifier.citation | NUCLEAR TECHNOLOGY, v.130, no.3, pp.310 - 328 | - |
dc.identifier.issn | 0029-5450 | - |
dc.identifier.uri | http://hdl.handle.net/10203/77294 | - |
dc.description.abstract | A model to predict critical heat flux (CHF) for high-heat-flux subcooled flow boiling in uniformly heated tubes is proposed. The present CHF model is based on the mechanism of wall-attached bubble coalescence. To take into account the enhanced condensation due to high subcooling and high mass velocity in small-diameter tubes, a mechanistic approach is adopted to evaluate the non-equilibrium flow quality and void fraction in the subcooled water flow boiling. Comparison of the model predictions against similar to 3100 subcooled water CHF data shows relatively good agreement over a wide range of parameters that covers the operating conditions of fusion reactor components. The operating ranges of the present database cover 0.33 less than or equal to D less than or equal to 37.5 mm, 0.002 less than or equal to L less than or equal to 4 m, 0.1 less than or equal to P less than or equal to 20 MPa, 0.37 less than or equal to G less than or equal to 134 Mg/m(2) . s, 49 less than or equal to Delta h(sub, in) less than or equal to 1659 kJ/kg, -1.25 less than or equal to x(em) < 0 and 1.05 less than or equal to q(CHF) less than or equal to 276 MW/m(2). | - |
dc.language | English | - |
dc.publisher | AMER NUCLEAR SOCIETY | - |
dc.subject | SMALL-DIAMETER TUBES | - |
dc.subject | LOW QUALITIES | - |
dc.subject | MODEL | - |
dc.subject | UPFLOW | - |
dc.title | A procedure to predict subcooled-water-flow-boiling CHF in uniformly heated tubes for high-heat-flux applications | - |
dc.type | Article | - |
dc.identifier.wosid | 000087024600007 | - |
dc.identifier.scopusid | 2-s2.0-0347644978 | - |
dc.type.rims | ART | - |
dc.citation.volume | 130 | - |
dc.citation.issue | 3 | - |
dc.citation.beginningpage | 310 | - |
dc.citation.endingpage | 328 | - |
dc.citation.publicationname | NUCLEAR TECHNOLOGY | - |
dc.contributor.localauthor | Chang, Soon-Heung | - |
dc.contributor.nonIdAuthor | Kwon, YM | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordAuthor | critical heat flux | - |
dc.subject.keywordAuthor | subcooled flow boiling | - |
dc.subject.keywordAuthor | high heat flux | - |
dc.subject.keywordPlus | SMALL-DIAMETER TUBES | - |
dc.subject.keywordPlus | LOW QUALITIES | - |
dc.subject.keywordPlus | MODEL | - |
dc.subject.keywordPlus | UPFLOW | - |
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