Title of article
FractureassessmentofabrittleRPVundercoldloadingOriginalResearchArticle
Author/Authors
IradjSattari-Far، نويسنده , , LarsDahlberg، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2004
Pages
8
From page
143
To page
150
Abstract
TheoldestSwedishreactorisaboilingwaterreactor(BWR)withavesselmadeofA302GradeBwithratherhighCuandNicontent.TheseelementshaveintensifiedtheirradiationembrittlementinthebeltlineregionsothatRTNDTofcertainweldsmayexceed100°Cattheend-of-lifecondition.Apreliminarystudyofthefractureriskforthebeltlineregionshowedthatthelimitingloadingcasewouldbethecoldover-pressurizationofthereactor.Theobjectiveofthisstudywastodevelopareliablemethodologyforfractureassessmentoftheagedreactorvesselundercoldloadingscenarios.ThetestprogramcoveredexperimentsonstandardSEN(B)specimensandcladbeamsunderuniaxialandbiaxialloading.Thetestmaterialwasareactorvesselsteelpreparedwithaspecialheattreatmenttosimulatefracturetoughnesspropertiesoftheagedreactor.Nosignificanteffectsofshallowcrackandbiaxialloadingwereobservedoncleavagefracturetoughnessindifferentcladspecimens.WhiletheASMEKIcreferencecurvewasshowntobeoverlyconservative,theMasterCurvemethodologysatisfactorilypredictedtheexperimentaloutcomesofthetestprogram.TheMasterCurvemethodologyindicatedthata20-mmdeepsurfacecrackwasacceptableinthebeltlineregionunderacoldover-pressurizationscenario.ThisvaluewasthreetimesgreaterthanwhatamethodologybasedontheASMEKIcreferencecurveyielded.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2004
Journal title
Nuclear Engineering and Design Eslah
Record number
894677
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