ASTM E2215-2002 评价轻水核电反应堆监视舱的标准实施规程
作者:标准资料网 时间:2024-05-03 01:18:43 浏览:9421
来源:标准资料网
下载地址: 点击此处下载
【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】:
【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】:
下载地址: 点击此处下载