Title of article :
OverviewofHTTRdesignfeaturesOriginalResearchArticle
Author/Authors :
S.Shiozawa، نويسنده , , S.Fujikawa، نويسنده , , Tatsuo Iyoku، نويسنده , , K.Kunitomi، نويسنده , , Y.Tachibana، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2004
Abstract :
TheJapanAtomicEnergyResearchInstitute(JAERI)designedandconstructedthehightemperatureengineeringtestreactor(HTTR)inordertoestablishandupgradethetechnologybasisforthehightemperaturegas-cooledreactor(HTGR)anddevelopthetechnologyforhightemperatureheatapplications.TheHTTRisahelium-cooledandgraphite-moderatedHTGRwithathermalpowerof30MWandamaximumreactoroutletcoolanttemperatureof950°C.ThefirstcriticalitywasattainedonNovember10,1998andtheratedpoweroperationwiththereactoroutletcoolanttemperatureof850°CwasachievedonDecember7,2001.Since2002,safetydemonstrationtestssimulatinganticipatedoperationaloccurrencessuchasdecreaseofprimarycoolantflow-rateandreactivityinsertionhavebeencarriedouttoensuresafetyduringoff-normalconditions.From2005,variousirradiationtestsforfuelsandmaterialswillstart.Inaddition,ahydrogenproductiontestfacilitywillbecoupledwiththeHTTRby2015toproducehydrogenbynuclear.
Journal title :
Nuclear Engineering and Design Eslah
Journal title :
Nuclear Engineering and Design Eslah
