• Title of article

    Analysisoflarge-scaletestsforAP-600passivecontainmentcoolingsystemOriginalResearchArticle

  • Author/Authors

    W.T.Sha، نويسنده , , T.H.Chien، نويسنده , , J.G.Sun، نويسنده , , B.T.Chao، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2004
  • Pages
    20
  • From page
    197
  • To page
    216
  • Abstract
    Allnext-generationlightwaterreactorsutilizepassivesystemstoremoveheatvianaturalcirculationandaresignificantlydifferentfrompastandcurrentnuclearplantdesigns.OneuniquefeatureoftheAP-600isitspassivecontainmentcoolingsystem(PCCS),whichisdesignedtomaintaincontainmentpressurebelowthedesignlimitfor72hwithoutactionbythereactoroperator.Duringadesign-basisaccident(DBA),i.e.,eitheraloss-of-coolantoramain-steam-linebreakaccident,steamescapesandcomesincontactwiththemuchcoolercontainmentvesselwall.Heatistransferredtotheinsidesurfaceofthesteelcontainmentwallbyconvectionandcondensationofsteamandthroughthecontainmentsteelwallbyconduction.Heatisthentransferredfromtheoutsideofthecontainmentsurfacebyheatingandevaporationofathinliquidfilmthatisformedbyapplyingwateratthetopofthecontainmentvesseldome.Airintheannularspaceisheatedbybothconvectionandinjectionofsteamfromtheevaporatingliquidfilm.Theheatedairandvaporriseasaresultofnaturalcirculationandexittheshieldbuildingthroughtheoutletsabovethecontainmentshell.AlloftheanalyticalmodelsthataredevelopedforandusedintheCOMMIX-1DcodeforpredictingperformanceofthePCCSwillbedescribed.Thesemodelscovergoverningconservationequationsformulticomponentssingle-phaseflow,transportequationsforthek−ɛtwo-equationturbulencemodel,auxiliaryequations,liquid-filmtrackingmodelforbothinside(condensate)andoutside(evaporatingliquidfilm)surfacesofthecontainmentvesselwall,thermalcouplingbetweenflowdomainsinsideandoutsidethecontainmentvessel,andheatandmasstransfermodels.VariouskeyparametersoftheCOMMIX-1DresultsandcorrespondingAP-600PCCSexperimentaldataarecomparedandtheagreementisgood.Significantfindingsfromthisstudyaresummarized.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2004
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    894790