BS ISO 26021-3-2009 道路车辆.车载烟火装置的报废期激活.工具要求
时间:2024-05-02 07:11:11 来源: 标准资料网 作者：标准资料网 阅读：9421
【英文标准名称】:Roadvehicles-End-of-lifeactivationofon-boardpyrotechnicdevices-Toolrequirements
【原文标准名称】:道路车辆.车载烟火装置的报废期激活.工具要求
【标准号】:BSISO26021-3-2009
【标准状态】:现行
【国别】:英国
【发布日期】:2009-06-30
【实施或试行日期】:2009-06-30
【发布单位】:英国标准学会(GB-BSI)
【起草单位】:BSI
【标准类型】:()
【标准水平】:()
【中文主题词】:激活;气囊;CAN;落水汽车;控制器局域网络;定义(术语);诊断;电气系统;汽车报废点;接口;寿命周期;摩托车;旧汽车;停止运转;焰火制造术;道路车辆;报废;规范(验收);试验;测试要求;工具;废弃物处置
【英文主题词】:Activation;Airbags;CAN;Carwrecks;ControllerAreaNetwork;Definitions;Diagnosis;Electricalsystems;End-oflifevehicles;Interfaces;Lifecycles;Motorvehicles;Oldautomobiles;Puttingoutofoperation;Pyrotechnics;Roadvehicles;Scrapping;Specification(approval);Testing;Testingrequirements;Tools;Wastedisposal
【摘要】:
【中国标准分类号】:T37
【国际标准分类号】:43_040_80
【页数】:24P;A4
【正文语种】:英语
Product Code:SAE AMS5730
Title:Steel Corrosion and Heat Resistant 19cr 12ni 3.2w 1cb 0.15n (Cancelled Dec 2002)
Issuing Committee:Ams F Corrosion Heat Resistant Alloys Committee
Scope:【英文标准名称】:StandardPracticeforEvaluationofSurveillanceCapsulesfromLight-WaterModeratedNuclearPowerReactorVessels
【原文标准名称】:评价轻水核电反应堆监视舱的标准实施规程
【标准号】:ASTME2215-2002
【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】:(Practice)
【标准水平】:()
【中文主题词】:
【英文主题词】:irradiation;nuclearreactorvessels(lightwatermoderated);radiationexposure;surveillance(ofnuclearreactorvessels)
【摘要】:4.1Neutronradiationeffectsareconsideredinthedesignoflight-watermoderatednuclearpowerreactors.Changesinsystemoperatingparametersmaybemadethroughouttheservicelifeofthereactortoaccountfortheseeffects.Asurveillanceprogramisusedtomeasurechangesinthepropertiesofactualvesselmaterialsduetotheirradiationenvironment.Thispracticedescribesthecriteriathatshouldbeconsideredinevaluatingsurveillanceprogramtestcapsules.4.2Priortothefirstissuedateofthisstandard,thedesignofsurveillanceprogramsandthetestingofsurveillancecapsuleswerebothcoveredinasinglestandard,PracticeE185.Betweenitsprovisionaladoptionin1961anditsreplacementlinkedtothisstandard,PracticeE185wasrevisedmanytimes(1966,1970,1973,1979,1982,1993and1998).Therefore,capsulesfromsurveillanceprogramsthatweredesignedandimplementedunderearlyversionsofthestandardwereoftentestedaftersubstantialchangestothestandardhadbeenadopted.Forclarity,thestandardpracticeforsurveillanceprogramshasbeendividedintothenewPracticeE185thatcoversthedesignofnewsurveillanceprogramsandthisstandardpracticethatcoversthetestingandevaluationofsurveillancecapsules.Afuturestandardisplannedwhichwillrecommendproceduresformodifyingandsupplementingexistingsurveillanceprogramsbothintermsofdesignandtesting.4.3Thisstandardpracticeisintendedtocovertestingandevaluationofalllight-watermoderatedreactorpressurevesselsurveillancecapsules.ThepracticeisapplicabletotestingofcapsulesfromsurveillanceprogramsdesignedandimplementedunderallpreviousversionsofPracticeE185.4.4Theradiation-inducedchangesinthepropertiesofthevesselaregenerallymonitoredbymeasuringtheCharpytransitiontemperature,theCharpyuppershelfenergyandthetensilepropertiesofspecimensfromthesurveillanceprogramcapsules.Thesignificanceoftheseradiation-inducedchangesisdescribedinPracticeE185.TheapplicationofthisdataisthesubjectofGuideE900andotherdocumentslistedinSection2.4.5Alternativemethodsexistfortestingsurveillancecapsulematerials.SomesupplementalandalternativetestingmethodsareavailableasindicatedinPracticeE636.DirectmeasurementofthefracturetoughnessisalsofeasibleusingtheToReferenceTemperaturemethoddefinedinTestMethodE1921orJ-integraltechniquesdefinedinTestMethodE1820.Additionallyhardnesstestingcanbeusedtosupplementstandardmethodsasameansofmonitoringtheradiationresponseofthematerials.4.6ThemethodologytobeusedintheanalysisandinterpretationofneutrondosimetrydataandthedeterminationofneutronfluenceisdefinedinPracticeE853.4.7GuideE900describesthebasesusedtoevaluatetheradiation-inducedchangesinCharpytransitiontemperatureforreactorvesselmaterialsandprovidesamethodologyforpredictingfuturevalues.1.1Thispracticecoverstheevaluationoftestspecimensanddosimetryfromlightwatermoderatednuclearpowerreactorpressurevesselsurveillancecapsules.1.2Thispracticeisoneofaseriesofstandardpracticesthatoutlinethesurveillanceprogramrequiredfornuclearreactorpressurevessels.Thesurveillanceprogrammonitorstheradiation-inducedchangesintheferriticsteelsthatcomprisethebeltlineofalight-watermoderatednuclearreactorpressurevessel.1.3Thispracticealongwithitscompanionsurveillanceprogrampractice,PracticeE185,isintendedforapplicationinmonitoringthepropertiesofbeltlinematerialsinanylight-watermoderatednuclearreactor.1.4ModificationstothestandardtestprogramandsupplementaltestswillbedescribedinaseparateStandardthatisunderdevelopmenttoaccompanythisstandardpracticeandPracticeE185.
【中国标准分类号】:F60
【国际标准分类号】:27_120_10
【页数】:6P.;A4
【正文语种】: