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NuclearPowerEngineering24320036Vol.24.No.3Jun.20030258-0926(2003)03-0227-04RPV121.6100412.3(PCCv)ASTME1921-97(T0)T0T0T0(ΔT0)TL341A11984Wallin(MasterCurve)KJC(med)=30+70exp[0.019(T-T0)](1)KJCJT0ASTMIAEA1997(Weakest-linktheory)ASTME1921-97[1]ASMEN-629N-631RTT0RTNDTRTT0T0RTT0=T0+35oF(2)0.2mm/min10mm/min300mm/minJoyce[2]Yoon[3](PCCv)(RPV)3PCCvASTME1921-9722.1A[4]L[4]JSPS[5]122.22.2.1PCCv50mm10mm10mmV1mmPCCv70382001-12-182002-05-04Vol.24.No.3.2003228(0.2mm/min)3285(10mm/min1830mm/min434)2.2.220min[4]13ASTME1921-97(J(KJC)100MPa)(a0)8282910∑=++=iiaaaa(3)a1a9mm3ASTME1921-97(1)13JC(4)KJCEJKCJC=(4)EMPa(2)(5)KJCKJC(1T)[]4/1T1xJC)T1(JC2020⎟⎟⎠⎞⎜⎜⎝⎛-+=BBKK(5)B1TmmBx(PCCv)mm(3)T01wt%Table1ChemicalCompositionofMaterialswt%CSiMnPSNiCrCuMoA0.190.301.300.0150.0100.680.170.160.53L0.170.241.360.0030.0030.610.070.020.47JSPS0.240.411.520.0280.0230.430.080.190.492Table2PropertiesofMaterialsatRoomTemperature/MPa/MPaA482537632669L461603JSPS461539639704=5000()53PCCvTable3QuantitiesofPCCvSpecimensALJSPS100806013085255300mm/min810—8—810mm/min—8—————0.2mm/min10——10—8[4]RPV229a80300mm/minb8010mm/minc60300mm/min1AFig.1Load-displacementRecordsofASteel2L(-85,300mm/min)Fig.2Load-displacementRecordsofLSteel3JSPS(5300mm/min)Fig.3Load-displacementRecordsofJSPSSteel()⎥⎦⎤⎢⎣⎡--=7030ln019.01med0JCKTT(6)TKJC(med)1MPam1KJC(med)=30+70exp[0.019(T-T0)](7)4KJC(med)T044ΔT055LΔT0JSPS5,4Table4CalculatedResultsLAJSPS/mmmin1/KJC(med)/MPamT0/KJC(med)/MPamT0/KJC(med/MPamT0/85786580664560713230057726108081631308011310069700.225730Vol.24.No.3.2003230(1)(2)[1]ASTME1921-97.StandardTestMethodforDetermina-tionofReferenceTemperature,T0,forFerriticSteelsintheTransitionRange[S].1998.[2]JoyceJ.OntheUtilizationofHighRateCharpyTestResultsandtheMusterCurvetoObtainAccurateLowerBoundToughnessPredictionsintheDuctile-to-BrittleTransition[R].ASTMSTP1329,1998:253~273.[3]YoonKK.EffectofLoadingRateonFractureTough-nessofPressureVesselSteels[J].JournalofPressureVesselTechnology,2000,122:125~129.[4]OnizawaK,TobitaT,SuzukiM.InvestigationontheEvaluationofCleavageFractureToughnessUsingPCCvSpecimensintheDuctile-BrittleTransitionRangeofReactorPressureVesselSteel[R].JAERI-Research97-081,JapanAtomicEnergyResearchInstitute,1997.InvestigationofLoadingRateEffectonCleavageFractureToughnessofReactorPressureVesselSteelsBasedonMasterCurveMethodSUNYing-xue1ONIZAWAKunio21.NuclearPowerInstituteofChinaChengdu610041China2.JapanAtomicEnergyResearchInstituteTokai-muraIbaraki-ken319-1195JapanAbstractThispaperstudiestheeffectsofloadingrateoncleavagefracturetoughnessofRPVsteelsusingthreekindsofmaterialsofpre-crackedCharpy-v(PCCv)specimens.ThosePCCvspecimenshavebeentestedunderdifferentloadingratesanddifferenttemperatures.Basedonthetestdata,fracturetoughnessvaluesandreferencetemperature(T0)werecalculatedaccordingtoASTMStandardE1921-97.ThemastercurvemethodhasbeenusedtodeterminetheT0shift(ΔT0)fromstatictohighloadingrate.ItisconcludedthattheT0isdependentontheloadingrate,andincreasesatelevatedloadingrate.WhentheT0atstaticloadingrateislow,theΔT0becomeslarge.KeywordsNuclearreactorvessel;Fracturetoughness;Pre-crackedCharpy-v;ReferenceTempera-ture;Mastercurve;Loadingrate:(1968)1991(1961)5T0Table5MaterialT0ChangefromSteadyStatetoTransientConditionLAJSPST0(0.2mm/min)113700T0(0.210mm/min)6T0(0.2300mm/min)483126
本文标题:基于主曲线方法研究加载速率对RPV材料断裂韧性的影响
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