Title of article :
HydraulicflowtestsofAPWRreactorinternalsforsafetyanalysisOriginalResearchArticle
Author/Authors :
TadashiMorii، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2008
Pages :
13
From page :
469
To page :
481
Abstract :
AconceptofradialneutronreflectorofAPWRbringsaboutsafetyproblemsrelevanttotheflowinducedvibrationandthermaldeformation.TheCFDcodehasbeenexpectedtosolvethembycalculatingpressurefluctuationsofturbulentflowinthedowncomerandtheflowdistributionintotheneutronreflector.AseriesofhydraulicflowtestswasconductedbyNUPECfrom1998to2002todemonstratethenewdesignoftheneutronreflectorandtoobtaintestdataforvalidatingtheCFDcode.ThemeasuredpressurefluctuationsinthedowncomerandtheirstatisticswereutilizedforvalidatingthespecificturbulentmodeltobeabletocalculateaspectrumofpressurefluctuationsuchastheLESmodel.Themeasuredflowratesatinletholesofthelowercoreplatewereutilizedforvalidatingforthegeneralturbulentmodel,forexample,thek–ɛturbulentmodel.ThecalculatedresultswiththeLESmodelagreedwellwiththemeasuredpressurefluctuationsandtheirspectrum,butdidnotagreewiththecorrelationbetweenadjacentpressurefluctuations.Ontheotherhand,thecalculationresultswiththek–ɛturbulentmodelagreedwellwiththemeasuredflowratesatinletholesofthelowercoreplate.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2008
Journal title :
Nuclear Engineering and Design Eslah
Record number :
895020
Link To Document :
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