Title of article
TransienttestsonblowertripandrodremovalattheHTR-10OriginalResearchArticle
Author/Authors
ShouyinHu، نويسنده , , RuipianWang، نويسنده , , ZuyingGao، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2006
Pages
4
From page
677
To page
680
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
Serial Year
2006
Journal title
Nuclear Engineering and Design Eslah
Record number
896028
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