Title of article
Inter-subassemblyheattransferofsodiumcooledfastreactors:ValidationoftheNETFLOWcodeOriginalResearchArticle
Author/Authors
HiroyasuMochizuki، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2007
Pages
14
From page
2040
To page
2053
Abstract
ThispaperdescribesthepredictionoftemperatureattheexitofsubassembliesofasodiumcooledfastreactorusingtheNETFLOWcode.Untilpresenttime,thisplantdynamicscalculationcodeisexpectedasatoolofnucleareducation,andhasbeenvalidatedusingdataobtainedatfacilitiesorreactorscooledwithwaterorsodium.Anaturalcirculationtestwasconductedintheexperimentalfastreactor‘Joyo’witha100MWirradiationcore.Alsoaturbinetriptestwasconductedintheprototypefastbreederreactor‘Monju’.Thesetestswerechosentovalidateamodeltocalculateinter-subassemblyheattransferconsistingofheatconductionandheattransferbyinter-wrapperflow.Basedonthecalculationforthenaturalcirculationtestinprimaryandsecondaryloopsof‘Joyo’,themodeltocalculatetheheattransferinradialdirectionoftheinter-subassembliessimulatedreasonablesodiumtemperaturebehaviorsattheexitofsubassemblies.Goodagreementwasalsoobtainedinpredictionoftemperaturesattheexitofthe‘Monju’subassemblies.Throughthesevalidations,itwasshownthattheone-dimensionalplantdynamicscodeNETFLOWcouldtracetemperaturesattheexitofthesubassembliesoffastreactorswiththeinter-subassemblyheattransfermodel.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2007
Journal title
Nuclear Engineering and Design Eslah
Record number
941424
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