Title of article
AnalysesonfluidflowandheattransferinsideCalandriavesselofCANDU-6usingCFDOriginalResearchArticle
Author/Authors
ManwoongKim، نويسنده , , Seon-OhYu، نويسنده , , HhoJungKim، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2006
Pages
10
From page
1155
To page
1164
Abstract
InaCANadaDeuteriumUranium(CANDU)reactor,fuelchannelintegritydependsonthecoolabilityofthemoderatorasanultimateheatsinkundertransientconditionssuchasalossofcoolantaccident(LOCA)withacoincidenceofalossofemergencycorecooling(LOECC),aswellasanormaloperatingcondition.Thisstudypresentstheassessmentsofmoderatorthermal–hydrauliccharacteristicsinthenormaloperatingconditionandonetransientconditionforCANDU-6reactors,usingageneralpurposethree-dimensionalcomputationalfluiddynamicscode.Thisstudyconsistsoftwosteps.First,anoptimizedcalculationschemeisobtainedbymany-sidedcomparisonsofthepredictedresultswiththerelatedexperimentaldata,andbyevaluatingthefluidflowandtemperaturedistributions.Then,inthesecondstep,withtheoptimizedscheme,theanalysesforrealCANDU-6ofnormaloperatingconditionandtransitionconditionhavebeenperformed.Thepresentmodelhassuccessfullypredictedtheexperimentalresultsandalsoreasonablyassessedthethermal–hydrauliccharacteristicsoftherealCANDU-6with380fuelchannels.FlowregimemapwithmajorparametersrepresentingtheflowpatterninsideCalandriavesselhasalsoproposedtobeusedasoperationaland/orregulatoryguidelines.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2006
Journal title
Nuclear Engineering and Design Eslah
Record number
896068
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