Title of article :
Developmentofathermalhydraulicanalysiscodeforgas-cooledreactorswithannularfuelsOriginalResearchArticle
Author/Authors :
KyuHyunHan، نويسنده , , Kyong-WonSeo، نويسنده , , Dae-HyunHwang، نويسنده , , SoonHeungChang، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Pages :
15
From page :
164
To page :
178
Abstract :
Gas-cooledreactorshavebeenhighlightedasapromisingoptionfornextgenerationreactortechnology.Athermalhydraulicanalysiscodeforgas-cooledreactorshasbeendevelopedwithaheattransfermodelofablockelement,whichissolvedimplicitlywiththeheliumenergyequation.Validationwascarriedoutthroughcomparisonwithbothexperimentalandanalyticalresults.Acomputationmoduleforannularfuelrodshasbeencoupledtothecodeforcomparativeanalysesofanannularfuel-basedblockelement.Atnormaloperation,theannularfuelshows80°ClowerpeaktemperaturethanthesolidfuelforthesamepowerinJapanʹshightemperatureengineeringtestreactor(HTTR),eventhoughthepressuredropishigherintheannularfuel.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2006
Journal title :
Nuclear Engineering and Design Eslah
Record number :
895982
Link To Document :
https://search.isc.ac/dl/search/defaultta.aspx?DTC=10&DC=895982
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