Title of article
AssessmentofaDNB-typetheoreticalcriticalheatfluxmodelforrodbundleswithnon-uniformaxialpowershapesOriginalResearchArticle
Author/Authors
KyuHyunHan، نويسنده , , Dae-HyunHwang، نويسنده , , SoonHeungChang، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2006
Pages
9
From page
223
To page
231
Abstract
Ageneralcriticalheatflux(CHF)predictionmethodwithawideapplicablerangeandreasonableaccuracyisessentialtothethermal-hydraulicdesignandsafetyanalysisattheconceptualdesignstageforanewpressurizedwaterreactor(PWR).Inthisstudy,theKoreaAdvancedInstituteofScienceandTechnology(KAIST)liquidsub-layerdryoutCHFpredictionmodelforDeparturefromNucleateBoiling(DNB)regionhasbeenimplementedinasub-channelanalysiscode,andinvestigatedforthemethodʹspossibleuseinarodbundleenvironmentwithvariousnon-uniformaxialpowershapes.TheKAISTmodelshowedcomparablepredictioncapabilitytoLinʹsmethodforbottom-,center-,andtop-peakedheatfluxshapes.TheKAISTmodel,withoutanycorrectionfactorsorempiricalconstants,turnedouttobesuitabletofulfilltheneedsforabasisofageneralCHFpredictionmethodascomparedtoLinʹsmethodandWestinghouse-3(W-3)correlation.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2006
Journal title
Nuclear Engineering and Design Eslah
Record number
895986
Link To Document