Boiloff pattern transition during core uncovery in a small break LOCA

Cited 2 time in webofscience Cited 0 time in scopus
  • Hit : 371
  • Download : 0
DC FieldValueLanguage
dc.contributor.authorLim, ICko
dc.contributor.authorNo, Hee Cheonko
dc.date.accessioned2013-02-28T06:50:37Z-
dc.date.available2013-02-28T06:50:37Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued1996-12-
dc.identifier.citationANNALS OF NUCLEAR ENERGY, v.23, no.18, pp.1459 - 1476-
dc.identifier.issn0306-4549-
dc.identifier.urihttp://hdl.handle.net/10203/73340-
dc.description.abstractThrough the core uncovery experiments, it has been known that the low power and high power core boiloff patterns are observed in the high pressure core uncovery following a small-break loss-of-coolant accident. A criterion for the prediction of annular to intermittent flow transition in vertical flow is developed and applied to the classification of low power boiloff and high power boiloff patterns. The instability of the interface wave on the liquid film is considered as the real physical mechanism for the flow pattern transition and the instability is explained by the concept of the hyperbolicity breaking in the characteristic equation. The applicability of the developed criterion to the rod-bundle geometry is demonstrated using the flow pattern transition data taken by Bergles et al. and Venkateswararao, Finally, it is shown that the developed criterion well predicts the boundary between low power boiloff and high power boiloff through the comparisons of the predicted annular to intermittent flow transition conditions with the boiloff experiment data taken by Anklam and Osakabe. Copyright (C) 1996 Elsevier Science Ltd.-
dc.languageEnglish-
dc.publisherPERGAMON-ELSEVIER SCIENCE LTD-
dc.subjectGAS-LIQUID FLOW-
dc.subjectTUBES-
dc.titleBoiloff pattern transition during core uncovery in a small break LOCA-
dc.typeArticle-
dc.identifier.wosidA1996VE41100003-
dc.identifier.scopusid2-s2.0-0030529995-
dc.type.rimsART-
dc.citation.volume23-
dc.citation.issue18-
dc.citation.beginningpage1459-
dc.citation.endingpage1476-
dc.citation.publicationnameANNALS OF NUCLEAR ENERGY-
dc.contributor.localauthorNo, Hee Cheon-
dc.contributor.nonIdAuthorLim, IC-
dc.type.journalArticleArticle-
dc.subject.keywordPlusGAS-LIQUID FLOW-
dc.subject.keywordPlusTUBES-
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 2 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0