Title of article :
TransienttestsonblowertripandrodremovalattheHTR-10OriginalResearchArticle
Author/Authors :
ShouyinHu، نويسنده , , RuipianWang، نويسنده , , ZuyingGao، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Abstract :
Safetydemonstrationtestsonthe10MWhightemperaturegas-cooledreactortestmodule(HTR-10)wereconductedtoverifytheinherentsafetyfeaturesofMHTGRsandtoobtainthecoreandprimarycoolingsystemtransientdataforvalidationofsafetyanalysiscodes.
Twosimulatedanticipatedtransientswithoutscram(ATWS)tests,loseofforcedcoolingbytripoftheheliumblowerandreactivityinsertionviacontrolrodwithdrawalwereperformed.Thispaperdescribesthetestswithdetailedtestmethod,conditionandresults.
Calculatedresultsshowthatthestronglynegativetemperaturecoefficientcausesreactorpowertocloselyfollowheatremovallevels.Maximumfueltemperaturechangesarelimitedbythelargecoreheatcapacitytobelow1230°Cduringtwotests.
ThetestoftrippingtheheliumcirculatorATWStestwasconductedonOctober15,2003.Althoughnoneof10controlrodswasmoved,thereactorpowerimmediatelydecreasedduetothenegativetemperaturecoefficient.Afterabout50min,thereactorbecamecriticalityagain.Finally,thereactorpowerwenttoastablelevelwithabout200kW.
ThetestofreactivityinsertionATWStestwasconductedtwotimes.Followingthecontrolrodwithdrawal,thereactorpowerincreasedrapidly,themaximumpowerlevelreachedto5037and7230kWfromtheinitialpowerof3000kWinaccordancewithreactivityinsertionof$0.136and0.689,respectively.Afterthereactivityintroducedwascompensatedbymeansofthestrongnegativereactivityfeedbackeffect,thereactorwenttosubcriticalandthepowerdecreased.
Journal title :
Nuclear Engineering and Design Eslah
Journal title :
Nuclear Engineering and Design Eslah