JIS L4405 AMD 1-2008 簇绒地毯(修改件1)
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【英文标准名称】:Tuftedpilecarpet(Amendment1)
【原文标准名称】:簇绒地毯(修改件1)
【标准号】:JISL4405AMD1-2008
【标准状态】:现行
【国别】:日本
【发布日期】:2008-09-20
【实施或试行日期】:
【发布单位】:日本工业标准调查会(JP-JISC)
【起草单位】:TechnicalCommitteeonConsumerLifeProducts
【标准类型】:()
【标准水平】:()
【中文主题词】:
【英文主题词】:
【摘要】:JISL4405:2008を,次のように改正する。
【中国标准分类号】:W56
【国际标准分类号】:59_080_60
【页数】:3P;A4
【正文语种】:日语
【原文标准名称】:簇绒地毯(修改件1)
【标准号】:JISL4405AMD1-2008
【标准状态】:现行
【国别】:日本
【发布日期】:2008-09-20
【实施或试行日期】:
【发布单位】:日本工业标准调查会(JP-JISC)
【起草单位】:TechnicalCommitteeonConsumerLifeProducts
【标准类型】:()
【标准水平】:()
【中文主题词】:
【英文主题词】:
【摘要】:JISL4405:2008を,次のように改正する。
【中国标准分类号】:W56
【国际标准分类号】:59_080_60
【页数】:3P;A4
【正文语种】:日语
下载地址: 点击此处下载
【英文标准名称】:ElectromagneticcompatibilityandRadiospectrumMatters(ERM)-VHFair-groundDataLink(VDL)Mode4radioequipment-Technicalcharacteristicsandmethodsofmeasurementforground-basedequipment-Part2:Datalinklayer(EndorsementoftheEnglish
【原文标准名称】:电磁兼容性和无线电频谱情况.VHF空对地数字链接(VDL)模式4无线电设备.地面设备的技术特性和测量方法.第2部分:数据链路层
【标准号】:DINEN301842-2-2003
【标准状态】:作废
【国别】:德国
【发布日期】:2003-11
【实施或试行日期】:
【发布单位】:德国标准化学会(DIN)
【起草单位】:
【标准类型】:()
【标准水平】:()
【中文主题词】:额定值;试验;电信;EMC电磁兼容性;电磁兼容性和无线电频谱情况;无线电设备;数据传送;测量技术;链路层;无线通信业务;数字连接;电磁兼容性;物理层;无线电广播网
【英文主题词】:
【摘要】:
【中国标准分类号】:L06
【国际标准分类号】:35_100_20;33_060_99;33_100_01
【页数】:1P;A4
【正文语种】:德语
【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】:
【原文标准名称】:电磁兼容性和无线电频谱情况.VHF空对地数字链接(VDL)模式4无线电设备.地面设备的技术特性和测量方法.第2部分:数据链路层
【标准号】:DINEN301842-2-2003
【标准状态】:作废
【国别】:德国
【发布日期】:2003-11
【实施或试行日期】:
【发布单位】:德国标准化学会(DIN)
【起草单位】:
【标准类型】:()
【标准水平】:()
【中文主题词】:额定值;试验;电信;EMC电磁兼容性;电磁兼容性和无线电频谱情况;无线电设备;数据传送;测量技术;链路层;无线通信业务;数字连接;电磁兼容性;物理层;无线电广播网
【英文主题词】:
【摘要】:
【中国标准分类号】:L06
【国际标准分类号】:35_100_20;33_060_99;33_100_01
【页数】:1P;A4
【正文语种】:德语
【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】:
