Title of article
ModelingofdebriscoolingwithannulargapinthelowerRPVandverificationbasedonALPHAexperimentsOriginalResearchArticle
Author/Authors
YukimitsuOkano، نويسنده , , TamioKohriyama، نويسنده , , YoshitakaYoshida، نويسنده , , MichioMurase، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2003
Pages
14
From page
145
To page
158
Abstract
Forsevereaccidentassessmentinalightwaterreactor,heattransfermodelsinanarrowannulargapbetweentheoverheatedcoredebrisandthereactorpressurevessel(RPV)areimportantforevaluatingRPVintegrityandemergencyprocedures.Usingexistingdata,theauthorsdevelopedheattransfermodelsontheaveragecriticalheatflux(CHF)restrictedbycountercurrentflowlimitation(CCFL)andlocalboilingheatfluxes,andshowedthattheaverageCHFdependedonthesteam–waterflowpatterninthenarrowgapandthatthelocalheatfluxesweresimilartothepoolboilingcurve.WeevaluatedthevalidityofheattransfermodelsbysimplecalculationsforALPHAexperimentsperformedatJapanAtomicEnergyResearchInstitute.Calculatedresultsshowedthatheatfluxesonthecrustsurfacewererestrictedmainlybythermalresistanceofthecrustafterthecrustformation,andemissivityonthecrustsurfacedidnothavemucheffectontheheatfluxes.Thecalculatedvesseltemperatureduringtheheat-upprocessandpeakvesseltemperatureagreedwellwiththemeasurements,whichconfirmedthevalidityoftheaverageCHFcorrelation.However,thevesselcoolingratewasunderestimatedmainlyduetounderestimationofthegapsize.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2003
Journal title
Nuclear Engineering and Design Eslah
Record number
894558
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