BS EN 1668-1997 焊接用料.非合金和细晶粒钢和钨极惰性气体保护用的焊条,焊丝和沉积物.分类

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【英文标准名称】:Weldingconsumables-Rods,wiresanddepositsfortungsteninertgasweldingofnonalloyandfinegrainsteels-Classification
【原文标准名称】:焊接用料.非合金和细晶粒钢和钨极惰性气体保护用的焊条,焊丝和沉积物.分类
【标准号】:BSEN1668-1997
【标准状态】:作废
【国别】:英国
【发布日期】:1997-12-15
【实施或试行日期】:1997-12-15
【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】:焊条;符号;焊接;气体保护焊;钢;连接材料;分类系统;机械试验;化学成分;非合金钢;名称与符号;冲击强度;填充金属;填充金属丝;气体保护钨极电弧焊;抗拉强度;屈服强度;延伸
【英文主题词】:All-weldmetals;Bars(materials);Classification;Fillerwire;Finegrainsteels;Gastungsten-arcwelding;Specification(approval);Steelwelding;Unalloyedsteels;Weldingfillermetals;Weldingrods;Wires
【摘要】:Thisstandardspecifiesrequirementsforclassificationofrods,wiresandall-weldmetalintheas-weldedconditionfortungsteninertgasweldingofnonalloyandfinegrainsteelswithaminimumyieldstrengthofupto500N/mmintheas-weldedcondition.
【中国标准分类号】:J33
【国际标准分类号】:25_160_20
【页数】:10P.;A4
【正文语种】:英语


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基本信息
标准名称:海底光缆数字传输系统工程设计规范
英文名称:Fiber Optie Submarine Cable Transmission System Engineering Design Standard
中标分类: 工程建设 >> 原材料工业及通信、广播工程 >> 通信工程
替代情况:被YD 5018-2005代替
发布日期:1996-05-06
实施日期:1996-07-01
首发日期:1900-01-01
作废日期:2006-06-01
起草单位:邮电部北京设计院
出版日期:1900-01-01
页数:31页
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所属分类: 工程建设 原材料工业及通信 广播工程 通信工程
【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】: