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
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