Assessment of a tube-based bundle CHF prediction method using a subchannel code

Cited 9 time in webofscience Cited 0 time in scopus
  • Hit : 527
  • Download : 0
DC FieldValueLanguage
dc.contributor.authorChun, THko
dc.contributor.authorHwang, DHko
dc.contributor.authorBaek, WPko
dc.contributor.authorChang, Soon-Heungko
dc.date.accessioned2013-03-03T04:47:37Z-
dc.date.available2013-03-03T04:47:37Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued1998-09-
dc.identifier.citationANNALS OF NUCLEAR ENERGY, v.25, no.14, pp.1159 - 1168-
dc.identifier.issn0306-4549-
dc.identifier.urihttp://hdl.handle.net/10203/77290-
dc.description.abstractAt the conceptual design stage for advanced water-cooled reactors (AWCRs), a general critical heat Aux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis. A basic idea for general CHF prediction is to utilize the tube-based CHF models covering wide applicable ranges with the help of supplementary terms for bundle effects. In this study, feasibility assessments have been performed with the bundle CHF data relevant ro pressurized water reactors. A subchannel analysis is adopted in order to be able to consider the geometrical variations properly even in unrested fuel bundle geometries. As a result, a CHF look-up table method (i.e., the use or a round tube CHF table with appropriate bundle effect factors) turns out to be a promising Way to fulfill the needs in many aspects among some selected correlations and theoretical models. Though improvements of the supplementary factors, especially for the cold wall and the bundle heated length effects, are desirable to make better predictions, the tube-based bundle CHF prediction method clearly shows a potential as a general CHF predictor. (C) 1998 Published by Elsevier Science Ltd. All rights reserved.-
dc.languageEnglish-
dc.publisherPERGAMON-ELSEVIER SCIENCE LTD-
dc.subjectCRITICAL HEAT-FLUX-
dc.titleAssessment of a tube-based bundle CHF prediction method using a subchannel code-
dc.typeArticle-
dc.identifier.wosid000074786400005-
dc.identifier.scopusid2-s2.0-0032168259-
dc.type.rimsART-
dc.citation.volume25-
dc.citation.issue14-
dc.citation.beginningpage1159-
dc.citation.endingpage1168-
dc.citation.publicationnameANNALS OF NUCLEAR ENERGY-
dc.contributor.localauthorChang, Soon-Heung-
dc.contributor.nonIdAuthorChun, TH-
dc.contributor.nonIdAuthorHwang, DH-
dc.contributor.nonIdAuthorBaek, WP-
dc.type.journalArticleArticle-
dc.subject.keywordPlusCRITICAL HEAT-FLUX-
Appears in Collection
NE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.
This item is cited by other documents in WoS
⊙ Detail Information in WoSⓡ Click to see webofscience_button
⊙ Cited 9 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0