ASTM E900-2002(2007) 在反应堆容器材料中预测辐射感应变化导致温度的变化的标准指南,E706(IIF)

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【英文标准名称】:StandardGuideforPredictingRadiation-InducedTransitionTemperatureShiftinReactorVesselMaterials,E706(IIF)
【原文标准名称】:在反应堆容器材料中预测辐射感应变化导致温度的变化的标准指南,E706(IIF)
【标准号】:ASTME900-2002(2007)
【标准状态】:现行
【国别】:
【发布日期】:2002
【实施或试行日期】:
【发布单位】:美国材料与试验协会(US-ASTM)
【起草单位】:E10.02
【标准类型】:(Guide)
【标准水平】:()
【中文主题词】:中子;损伤;核能;辐射;压力容器
【英文主题词】:
【摘要】:Operationofcommercialpowerreactorsmustconformtopressure-temperaturelimitsduringheatupandcooldowntopreventover-pressurizationattemperaturesthatmightcausenonductilebehaviorinthepresenceofaflaw.Radiationdamagetothereactorvesselbeltlineregioniscompensatedforbyadjustingthepressure-temperaturelimitstohighertemperatureastheneutrondamageaccumulates.ThepresentpracticeistobasethatadjustmentontheincreaseintransitiontemperatureproducedbyneutronirradiationasmeasuredattheCharpyV-notch30-ftx00B7;lbf(41-J)energylevel.Toestablishpressuretemperatureoperatinglimitsduringtheoperatinglifeoftheplant,apredictionofadjustmentintransitiontemperaturemustbemade.4.1.1Intheabsenceofsurveillancedataforagivenreactor(seePracticeE185),theuseofcalculativeprocedureswillbenecessarytomaketheprediction.Evenwhencrediblesurveillancedataareavailable,itwillusuallybenecessarytoextrapolatethedatatoobtainanadjustmentintransitiontemperatureforaspecifictimeintheplantoperatinglife.Theembrittlementcorrelationpresentedhereinhasbeendevelopedforthosepurposes.Researchhasestablishedthatcertainelements,notablycopperandnickel,causeavariationinradiationsensitivityofsteels.Theimportanceofotherelements,suchasphosphorus(P),remainsasubjectofadditionalresearch.Copperandnickelarethekeychemistryparametersusedindevelopingthecalculativeproceduresdescribedhere.Onlypowerreactorsurveillancedatawereusedinthederivationoftheseprocedures.Themeasureoffastneutronfluenceusedintheprocedureisn/cm2(E>1MeV).Differencesintheneutronfluencerateandneutronenergyspectraexperiencedinpowerreactorsandtestreactorshavenotbeenappliedintheseprocedures.Themannerinwhichthesefactorswereconsideredisaddressedelsewhere.31.1Thisguidepresentsamethodforpredictingreferencetransitiontemperatureadjustmentsforirradiatedlight-watercooledpowerreactorpressurevesselmaterialsbasedonCharpyV-notch30-ftlbf(41-J)data.RadiationdamagecalculativeprocedureshavebeendevelopedfromastatisticalanalysisofanirradiatedmaterialdatabasethatwasavailableasofMay2000.Theembrittlementcorrelationusedinthisguidewasdevelopedusingthefollowingvariables:copperandnickelcontents,irradiationtemperature,andneutronfluence.Theformofthemodelwasbasedoncurrentunderstandingfortwomechanismsofembrittlement:stablematrixdamage(SMD)andcopper-richprecipitation(CRP);saturationofcoppereffects(fordifferentweldmaterials)wasincluded.Thisguideisapplicableforthefollowingspecificmaterials,copper,nickel,andphosphoruscontents,rangeofirradiationtemperature,andneutronfluencebasedontheoveralldatabase:1.1.1MaterialsA533TypeBClass1and2,A302GradeB,A302GradeB(modified),A508Class2and3.Submergedarcwelds,shieldedarcwelds,andelectroslagweldsformaterialsin.1.1.2Coppercontentswithintherangefrom0to0.50wt%.1.1.3Nickelcontentwithintherangefrom0to1.3wt%.1.1.4Phosphoruscontentwithintherange0to0.025wt%.1.1.5Irradiationexposuretemperaturewithintherangefrom500to570F(260to299C).1.1.6Neutronfluencewithintherangefrom11016to81019n/cm2(E>1MeV).1.1.7Neutronenergyspectrawithintherangeexpectedatthereactorvesselcorebeltlineregionoflightwatercooledreactorsandfluenceratewithintherangefrom2108to11012n/cm2s(E>1MeV).1.2Thebasisforthemethodofadjustingthe......
【中国标准分类号】:F60
【国际标准分类号】:27_120_10
【页数】:4P.;A4
【正文语种】: