Title of article
Thermal–hydraulicfeasibilityanalysisonupratingtheHTR–PMOriginalResearchArticle
Author/Authors
YujieDong، نويسنده , , ZuyingGao، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2006
Pages
6
From page
510
To page
515
Abstract
InordertomeetenergydemandinChina,thehightemperaturegas-cooledreactor–pebble-bedmodule(HTR–PM)isbeingdeveloped.Itadoptsatwo-zonecore,inwhichgraphiteballsareloadedinthecentralzoneandtheouterpartisfuelballzone,andcouplewithasteamcycle.Outerdiameterofthereactorcoreis4.0mandheightofthecoreis9.43m.Theheliuminletandoutlettemperatureare250and750°C,respectively.Thereactorthermalpoweris380MW.PreliminarystudiesshowthattheHTR–PMisfeasibletechnologicallyandeconomically.InordertoincreasethereactorthermalpoweroftheHTR–PM,someeffortshavebeenmade.Theseincludeincreasingtheheightofreactorcore,optimizingthethicknessoffuelzoneandbetterselectionoftheschemeofcentralgraphitezone,etc.Basicdesignconceptsandthermal–hydraulicparametersoftheHTR–PMaregiven.Measurestoincreasethethermalpowerareintroduced.Thermal–hydraulicanalysisresultsarepresented.Theresultsshowthat,fromtheviewpointofthermal–hydraulics,itispossibletoincreasethereactorpower.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2006
Journal title
Nuclear Engineering and Design Eslah
Record number
896012
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