ISO/TS 10303-1703-2010 工业自动化系统和集成.产品数据表示和交换.第1703部分:应用模块:模型参数
时间:2024-04-27 16:44:03 来源: 标准资料网 作者：标准资料网 阅读：8635
【英文标准名称】:Industrialautomationsystemsandintegration-Productdatarepresentationandexchange-Part1703:Applicationmodule:Modelparameter
【原文标准名称】:工业自动化系统和集成.产品数据表示和交换.第1703部分:应用模块:模型参数
【标准号】:ISO/TS10303-1703-2010
【标准状态】:现行
【国别】:国际
【发布日期】:2010-03
【实施或试行日期】:
【发布单位】:国际标准化组织(IX-ISO)
【起草单位】:ISO/TC184
【标准类型】:()
【标准水平】:()
【中文主题词】:应用;自动化;自动化系统;数据交换;数据表示;工业产品;信息交换;信息技术;过程自动化;产品数据;表示法
【英文主题词】:Applications;Automation;Automationsystems;Dataexchange;Datarepresentation;Industrialproducts;Informationinterchange;Informationtechnology;Processautomation;Productdata;Representations
【摘要】:
【中国标准分类号】:N18
【国际标准分类号】:35_240_50
【页数】:8P;A4
【正文语种】:英语
Product Code:SAE AS85049/23
Title:Connector Accessories, Electrical, Backshell, Nonenvironmental, 45°, Shield Termination, Category 3A (For MIL-C-5015 Crimp, MIL-C-26482 Series 2, MIL-C-81703 Series 3, and MIL-C-83723 Series III
Issuing Committee:Ae-8c1 Connectors Committee
Scope:Amendment 1 of AS85049/23.【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】: