• 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