• Title of article

    ValidationoftheCFDcodefluentbypost-testcalculationofadensity-drivenROCOMexperimentOriginalResearchArticle

  • Author/Authors

    AndreasSchaffrath، نويسنده , , Klaus-ChristianFischer، نويسنده , , ThomasHahm، نويسنده , , SteffenWussow، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2007
  • Pages
    10
  • From page
    1899
  • To page
    1908
  • Abstract
    Duringthelastyears,borondilutioneventswiththepotentialofreactivitytransientswereanimportantissueofGermanPWRsafetyanalyses.Acoolantwithalow-boronconcentrationcouldbecollectedinlocalizedareasofthereactorcoolantsystem,e.g.,byseparationofaboratedreactorcoolantintohighlyconcentratedanddilutedfractions(inherentdilution)whichcanoccurduringreflux-condenserheattransferafterasmallbreaklossofcoolantaccidentwithalimitedavailabilityoftheemergencycorecoolingsystems. Duringthecourseoffollowercoreassessments,TÜVNORDSysTecappraisessafetyanalysesofborondilutioneventspresentedbytheutilities.Theseanalysesarebasedonthesimulationofborondilutionandtransportprocessesinconjunctionwithanumberofdedicatedexperiments.Theanalysesdemonstratethatborondilutioneventscannotleadtorecriticalityofthecore.Hence,theboronconcentrationatthecoreinlethastobedetermined. TÜVNORDSysTecappliestheCFDcodeFLUENTfortheinvestigationofborondilutioneventsinpressurizedwaterreactors.ToaffirmtheFLUENTabilitiesforthesimulationofborondilutionevents,avalidationagainsttheROCOMexperimentT6655_21withadensity-drivencoolantmixingwasperformed.ThisvalidationprovesthatFLUENTisabletoappropriatelysimulatetheeffectsofborontransportanddilutionsuchasstreaksofcoolantwithlowerdensityinthedowncomer.Deficitswereidentifiedinthesimulationoffluidlayeringinthecoldleg,whichfortunatelyhavearathersmallinfluenceonthepredictedcoreinletconcentration.Therefore,theboronconcentrationinthereactorcorecanbedeterminedwithsufficientaccuracytosolvethesafetyissue,regardlessofthecorebecomingcriticalornot.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2007
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    941370