ASTM E185-2010 轻水中型核动力反应堆罐监测计划设计的标准实施规程
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【英文标准名称】:StandardPracticeforDesignofSurveillanceProgramsforLight-WaterModeratedNuclearPowerReactorVessels
【原文标准名称】:轻水中型核动力反应堆罐监测计划设计的标准实施规程
【标准号】:ASTME185-2010
【标准状态】:现行
【国别】:美国
【发布日期】:2010
【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】:Nuclearapplications/materials--steel;Nuclearreactorvessels--light-watercooled;Nuclearreactorvessels--surveillance;Radiationexposure--nuclearmaterials/applications;Repairbywelding(forsteelfornuclear/specialapplications);Steelscreens
【摘要】:Predictionsofneutronradiationeffectsonpressurevesselsteelsareconsideredinthedesignoflight-watermoderatednuclearpowerreactors.Changesinsystemoperatingparametersoftenaremadethroughouttheservicelifeofthereactorvesseltoaccountforradiationeffects.Duetothevariabilityinthebehaviorofreactorvesselsteels,asurveillanceprogramiswarrantedtomonitorchangesinthepropertiesofactualvesselmaterialscausedbylong-termexposuretotheneutronradiationandtemperatureenvironmentofthereactorvessel.Thispracticedescribesthecriteriathatshouldbeconsideredinplanningandimplementingsurveillancetestprogramsandpointsoutprecautionsthatshouldbetakentoensurethat:(1)capsuleexposurescanberelatedtobeltlineexposures,(2)materialsselectedforthesurveillanceprogramaresamplesofthosematerialsmostlikelytolimittheoperationofthereactorvessel,and(3)thetestspecimentypesareappropriatefortheevaluationofradiationeffectsonthereactorvessel.ThemethodologytobeusedinestimationofneutronexposureobtainedforreactorvesselsurveillanceprogramsisdefinedinGuideE482.Thedesignofasurveillanceprogramforagivenreactorvesselmustconsidertheexistingbodyofdataonsimilarmaterialsinadditiontothespecificmaterialsusedforthatreactorvessel.Theamountofsuchdataandthesimilarityofexposureconditionsandmaterialcharacteristicswilldeterminetheirapplicabilityforpredictingradiationeffects.1.1Thispracticecoversproceduresfordesigningasurveillanceprogramformonitoringtheradiation-inducedchangesinthemechanicalpropertiesofferriticmaterialsinlight-watermoderatednuclearpowerreactorvessels.Thispracticeincludestheminimumrequirementsforthedesignofasurveillanceprogram,selectionofvesselmaterialtobeincluded,andtheinitialscheduleforevaluationofmaterials.1.2Thispracticewasdevelopedforalllight-watermoderatednuclearpowerreactorvesselsforwhichthepredictedmaximumfastneutronfluence(E>1MeV)attheendoflicense(EOL)exceeds1x00D7;1021neutrons/m2(1x00D7;1017n/cm2)attheinsidesurfaceofthereactorvessel.1.3Thispracticeappliesonlytotheplanninganddesignofsurveillanceprogramsforreactorvesselsdesignedandbuiltaftertheeffectivedateofthispractice.PreviousversionsofPracticeE185applytoearlierreactorvessels.1.4Thispracticedoesnotprovidespecificproceduresformonitoringtheradiationinducedchangesinpropertiesbeyondthedesignlife,buttheproceduredescribedmayprovideguidancefordevelopingsuchasurveillanceprogram.1.5ThevaluesstatedinSIunitsaretoberegardedasthestandard.Thevaluesgiveninparenthesesareforinformationonly.Note18212;Theincreasedcomplexityoftherequirementsforalight-watermoderatednuclearpowerreactorvesselsurveillanceprogramhasnecessitatedtheseparationoftherequirementsintothreerelatedstandards.PracticeE185describestheminimumrequirementsforasurveillanceprogram.PracticeE2215describestheproceduresfortestingandevaluationofsurveillancecapsulesremovedfromasurveillanceprogramasdefinedinthecurrentorpreviouseditionsofPracticeE185.GuideE......
【中国标准分类号】:F74
【国际标准分类号】:27_120_10
【页数】:8P.;A4
【正文语种】:英语
【原文标准名称】:轻水中型核动力反应堆罐监测计划设计的标准实施规程
【标准号】:ASTME185-2010
【标准状态】:现行
【国别】:美国
【发布日期】:2010
【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】:Nuclearapplications/materials--steel;Nuclearreactorvessels--light-watercooled;Nuclearreactorvessels--surveillance;Radiationexposure--nuclearmaterials/applications;Repairbywelding(forsteelfornuclear/specialapplications);Steelscreens
【摘要】:Predictionsofneutronradiationeffectsonpressurevesselsteelsareconsideredinthedesignoflight-watermoderatednuclearpowerreactors.Changesinsystemoperatingparametersoftenaremadethroughouttheservicelifeofthereactorvesseltoaccountforradiationeffects.Duetothevariabilityinthebehaviorofreactorvesselsteels,asurveillanceprogramiswarrantedtomonitorchangesinthepropertiesofactualvesselmaterialscausedbylong-termexposuretotheneutronradiationandtemperatureenvironmentofthereactorvessel.Thispracticedescribesthecriteriathatshouldbeconsideredinplanningandimplementingsurveillancetestprogramsandpointsoutprecautionsthatshouldbetakentoensurethat:(1)capsuleexposurescanberelatedtobeltlineexposures,(2)materialsselectedforthesurveillanceprogramaresamplesofthosematerialsmostlikelytolimittheoperationofthereactorvessel,and(3)thetestspecimentypesareappropriatefortheevaluationofradiationeffectsonthereactorvessel.ThemethodologytobeusedinestimationofneutronexposureobtainedforreactorvesselsurveillanceprogramsisdefinedinGuideE482.Thedesignofasurveillanceprogramforagivenreactorvesselmustconsidertheexistingbodyofdataonsimilarmaterialsinadditiontothespecificmaterialsusedforthatreactorvessel.Theamountofsuchdataandthesimilarityofexposureconditionsandmaterialcharacteristicswilldeterminetheirapplicabilityforpredictingradiationeffects.1.1Thispracticecoversproceduresfordesigningasurveillanceprogramformonitoringtheradiation-inducedchangesinthemechanicalpropertiesofferriticmaterialsinlight-watermoderatednuclearpowerreactorvessels.Thispracticeincludestheminimumrequirementsforthedesignofasurveillanceprogram,selectionofvesselmaterialtobeincluded,andtheinitialscheduleforevaluationofmaterials.1.2Thispracticewasdevelopedforalllight-watermoderatednuclearpowerreactorvesselsforwhichthepredictedmaximumfastneutronfluence(E>1MeV)attheendoflicense(EOL)exceeds1x00D7;1021neutrons/m2(1x00D7;1017n/cm2)attheinsidesurfaceofthereactorvessel.1.3Thispracticeappliesonlytotheplanninganddesignofsurveillanceprogramsforreactorvesselsdesignedandbuiltaftertheeffectivedateofthispractice.PreviousversionsofPracticeE185applytoearlierreactorvessels.1.4Thispracticedoesnotprovidespecificproceduresformonitoringtheradiationinducedchangesinpropertiesbeyondthedesignlife,buttheproceduredescribedmayprovideguidancefordevelopingsuchasurveillanceprogram.1.5ThevaluesstatedinSIunitsaretoberegardedasthestandard.Thevaluesgiveninparenthesesareforinformationonly.Note18212;Theincreasedcomplexityoftherequirementsforalight-watermoderatednuclearpowerreactorvesselsurveillanceprogramhasnecessitatedtheseparationoftherequirementsintothreerelatedstandards.PracticeE185describestheminimumrequirementsforasurveillanceprogram.PracticeE2215describestheproceduresfortestingandevaluationofsurveillancecapsulesremovedfromasurveillanceprogramasdefinedinthecurrentorpreviouseditionsofPracticeE185.GuideE......
【中国标准分类号】:F74
【国际标准分类号】:27_120_10
【页数】:8P.;A4
【正文语种】:英语
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