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
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