DC Field | Value | Language |
---|---|---|
dc.contributor.author | Han, KH | ko |
dc.contributor.author | Hwang, DH | ko |
dc.contributor.author | Chang, Soon-Heung | ko |
dc.date.accessioned | 2008-03-10T02:26:09Z | - |
dc.date.available | 2008-03-10T02:26:09Z | - |
dc.date.created | 2012-02-06 | - |
dc.date.created | 2012-02-06 | - |
dc.date.issued | 2006-02 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231 | - |
dc.identifier.issn | 0029-5493 | - |
dc.identifier.uri | http://hdl.handle.net/10203/3345 | - |
dc.description.abstract | A general critical heat flux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis at the conceptual design stage for a new pressurized water reactor (PWR). In this study, the Korea Advanced Institute of Science and Technology (KAIST) liquid sub-layer dryout CHF prediction model for Departure from Nucleate Boiling (DNB) region has been implemented in a sub-channel analysis code. and investigated for the method's possible use in a rod bundle environment with various non-uniform axial power shapes. The KAIST model showed comparable prediction capability to Lin's method for bottom-. center-. and top-peaked heat flux shapes. The KAIST model. without any correction factors or empirical constants, turned out to be suitable to fulfill the needs for a basis of a general CHF prediction method as compared to Lin's method and Westinghouse-3 (W-3) correlation. (C) 2005 Published by Elsevier B.V. | - |
dc.language | English | - |
dc.language.iso | en_US | en |
dc.publisher | ELSEVIER SCIENCE SA | - |
dc.subject | LOW-QUALITY FLOW | - |
dc.subject | PREDICTION | - |
dc.subject | TUBES | - |
dc.subject | MICROLAYER | - |
dc.title | Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes | - |
dc.type | Article | - |
dc.identifier.wosid | 000236986700001 | - |
dc.identifier.scopusid | 2-s2.0-31144453558 | - |
dc.type.rims | ART | - |
dc.citation.volume | 236 | - |
dc.citation.issue | 3 | - |
dc.citation.beginningpage | 223 | - |
dc.citation.endingpage | 231 | - |
dc.citation.publicationname | NUCLEAR ENGINEERING AND DESIGN | - |
dc.identifier.doi | 10.1016/j.nucengdes.2005.08.005 | - |
dc.embargo.liftdate | 9999-12-31 | - |
dc.embargo.terms | 9999-12-31 | - |
dc.contributor.localauthor | Chang, Soon-Heung | - |
dc.contributor.nonIdAuthor | Han, KH | - |
dc.contributor.nonIdAuthor | Hwang, DH | - |
dc.type.journalArticle | Article | - |
dc.subject.keywordPlus | LOW-QUALITY FLOW | - |
dc.subject.keywordPlus | PREDICTION | - |
dc.subject.keywordPlus | TUBES | - |
dc.subject.keywordPlus | MICROLAYER | - |
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