Title of article :
ModelingofdebriscoolingwithannulargapinthelowerRPVandverificationbasedonALPHAexperimentsOriginalResearchArticle
Author/Authors :
YukimitsuOkano، نويسنده , , TamioKohriyama، نويسنده , , YoshitakaYoshida، نويسنده , , MichioMurase، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2003
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
Journal title :
Nuclear Engineering and Design Eslah
