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
Pages
11
From page
11
To page
21
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
Serial Year
2004
Journal title
Nuclear Engineering and Design Eslah
Record number
894800
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