Title of article :
PerformancetestofHTTROriginalResearchArticle
Author/Authors :
ShigeakiNakagawa، نويسنده , , YukioTachibana، نويسنده , , KuniyoshiTakamatsu، نويسنده , , ShoheiUeta، نويسنده , , SatoshiHanawa، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2004
Pages :
10
From page :
291
To page :
300
Abstract :
Thehightemperaturegas-cooledreactor(HTGR)isparticularlyattractiveduetoitscapabilityofproducinghightemperatureheliumgasandduetoitsinherentsafetycharacteristics.Thehightemperatureengineeringtestreactor(HTTR),whichisthefirstHTGRinJapan,wassuccessfullyconstructedattheOaraiResearchEstablishmentoftheJapanAtomicEnergyResearchInstitute. TheHTTRachievedfullpowerof30MWatareactoroutletcoolanttemperatureofabout850°Con7December2001duringthe‘rise-to-powertests’.Twokindsoftestswerecarriedoutduringthe‘rise-to-powertests’.Oneiscommissioningtesttogetoperationpermitbythegovernmentandanotheristesttoconfirmaperformanceofthereactor,heatexchanger,andcontrolsystem. Fromthetestresultsofthe‘rise-to-powertests’upto30MW,thefunctionalityofthereactorandthecoolingsystemwereconfirmed,anditwasalsoconfirmedthatanoperationofreactorfacilitycouldbeperformedsafely.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2004
Journal title :
Nuclear Engineering and Design Eslah
Record number :
894825
Link To Document :
https://search.isc.ac/dl/search/defaultta.aspx?DTC=10&DC=894825
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