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ASTM B 646-1994 铝合金断裂韧性试验

作者:标准资料网 时间:2024-05-19 01:45:05  浏览:9535   来源:标准资料网
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【英文标准名称】:FractureToughnessTestingofAluminumAlloys
【原文标准名称】:铝合金断裂韧性试验
【标准号】:ASTMB646-1994
【标准状态】:作废
【国别】:美国
【发布日期】:1994
【实施或试行日期】:
【发布单位】:美国材料与试验协会(ASTM)
【起草单位】:ASTM
【标准类型】:()
【标准水平】:()
【中文主题词】:铝;抗裂纹扩张;合金;裂纹;断裂;铝合金;韧性;平面应变断裂韧性试验;金属;有色金属;试验
【英文主题词】:alloys;aluminium;fracture;testing;metals;flaws;planestrainfracturetoughnesstests;aluminiumalloys;toughness;non-ferrousmetals;crack-extension-resistant
【摘要】:
【中国标准分类号】:H22
【国际标准分类号】:77_120_10
【页数】:
【正文语种】:英语


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【英文标准名称】:Metallicmaterials-Knoophardnesstest-Verificationandcalibrationoftestingmachines
【原文标准名称】:金属材料.努氏硬度试验.试验机械的检验和校准
【标准号】:BSENISO4545-2-2006
【标准状态】:现行
【国别】:英国
【发布日期】:2006-01-30
【实施或试行日期】:2006-01-30
【发布单位】:英国标准学会(BSI)
【起草单位】:BSI
【标准类型】:()
【标准水平】:()
【中文主题词】:校正;硬度测量;硬度测试仪;努氏(硬度);努氏硬度;材料试验机;材料试验;测量设备;测量不确定度;金属材料;金属;渗透探伤;渗透冲模;试验周期;试验力;试验;试验条件;验证
【英文主题词】:
【摘要】:ThispartofISO4545specifiesthemethodofverificationoftestingmachinesfordeterminingKnoophardnessformetallicmaterialsinaccordancewithISO4545-1-1.Itcoverstestforcesfrom0,09807Nto19,614N.Themethodisrecommendedonlyforindentationswithdiagonals≥0,020mm.Itspecifiesadirectverificationmethodforcheckingthemainfunctionsofthemachine,andanindirectverificationmethodsuitablefortheoverallcheckingofthemachine.Theindirectverificationmethodmaybeusedonitsownforperiodicroutinecheckingofthemachineinservice.Ifatestingmachineisalsotobeusedforothermethodsofhardnesstesting,itshouldbeverifiedindependentlyforeachmethod.
【中国标准分类号】:H22
【国际标准分类号】:77_040_10
【页数】:24P;A4
【正文语种】:英语


【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】:



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