• Title of article

    ExperimentalresearchprogressoncriticalheatfluxofChinesePWROriginalResearchArticle

  • Author/Authors

    XiaoZejun، نويسنده , , SongXianhui، نويسنده , , LangXuemei، نويسنده , , BaiXuesong، نويسنده , , MaJieliang، نويسنده , , WangPengfei، نويسنده , , ChenBingde، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2004
  • Pages
    10
  • From page
    213
  • To page
    222
  • Abstract
    Oneofthemostimportantrequirementsinthedesignofpressurizedwaterreactor(PWR)istoavoidtheoccurrenceofcriticalheatflux(CHF).ThedesigncriteriaforPWRspecifythattheymustbeoperatedatacertainpercentagebelowCHFatalltimesandlocationssoastothecladdingtemperatureoffuelelementatsafevalues.Sointheprocessofsafetyassessment,CHFisoneofimportantthermal-hydraulicparameterslimitingtheavailablepower,whosesizedirectlyaffectssafetyandeconomyofPWRnuclearpowerplant.ThispaperdealswithasummaryofexperimentalresearchprogressonCHFofChinesePWR.ItmainlypresentsCHFexperimentalresearchesofΦ10fuelassembly,CHFexperimentalresearchesofstandardfuelassembly,andCHFexperimentalprogressofnon-uniformheatedrodbundles.ItshouldbeemphasizedthatitalsopresentsexperimentalresearchprogramsonCHFofChineseadvancedfuelassemblywithself-reliancecopyright.AllCHFdataobtainedwillbeusedfordesignimprovementofChinesePWRandR&DprogramofNewGeneration1000MWePWR.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2004
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    894713

    • Link To Document
    https://search.isc.ac/dl/search/defaultta.aspx?DTC=10&DC=894713