核电标准、规范与法规清单

1、ASTMB353-2002核设施（除核燃料包壳外）锻制锆与锆合金无缝焊接管标准规范StandardSpecificationforWroughtZirconiumandZirconiumAlloySeamlessandWeldedTubesforNuclearService(ExceptNuclearFuelCladding)ASTMB811-2002核反应堆燃料包壳锻制锆合金无缝管标准规范StandardSpecificationforWroughtZirconiumAlloySeamlessTubesforNuclearReactorFuelCladdingANSI/ASTMC781-20

2、02高温气冷核反应堆石墨与硼酸化石墨元部件试验标准实施规程StandardPracticeforTestingGraphiteandBoronatedGraphiteComponentsforHigh-TemperatureGas-CooledNuclearReactorsASTMC986-1989制定核燃料循环培训计划DevelopingTrainingProgramsintheNuclearFuelCycleASTMC1010-1983核燃料再加工设备的验收、检测与操作前试验Acceptance,CheckoutandPre-OperationalTestingofaNuclearFuel

3、sReprocessingFacilityASTMC1011-1983核燃料生产用无电极电导仪器选择或规范SelectionorSpecificationofElectrodelessConductivityInstrumentsfortheNuclearFuelCycleASTMC1062-2000核燃料溶解装置设计、制造与安装标准指南StandardGuideforDesign,Fabrication,andInstallationofNuclearFuelDissolutionFacilitiesASTMC1128-1995核燃料循环材料分析参考材料制备标准指南StandardGuide

4、forPreparationofWorkingReferenceMaterialsforUseintheAnalysisofNuclearFuelCycleMaterialsASTMC1156-2003分析核燃料循环材料测定方法的精度建立标准指南StandardGuideforEstablishingCalibrationforaMeasurementMethodUsedtoAnalyzeNuclearFuelCycleMaterialsASTMC1297-2003核燃料循环材料分析实验室分析法鉴定标准指南StandardGuideforQualificationofLaboratoryAna

5、lystsfortheAnalysisofNuclearFuelCycleMaterialsASTMC1431-1999铝基废核燃料腐蚀试验的维护容器清理标准指南StandardGuideforCorrosionTestingofAluminum-BasedSpentNuclearFuelinSupportofRepositoryDisposalASTMC1454-2000对铀金属废核燃料自燃分析进行自燃/易燃性试验标准指南StandardGuideforPyrophoricity/CombustibilityTestinginSupportofPyrophoricityAnalysesofM

6、etallicUraniumSpentNuclearFuelASTMD3911-2003设计基本事故(DBA)的模拟条件下评价轻水核电厂用涂层的标准试验方法StandardTestMethodforEvaluatingCoatingsUsedinLight-WaterNuclearPowerPlantsatSimulatedDesignBasisAccident(DBA)ConditionsASTMD3912-1995轻水核电厂涂层耐化学性标准试验方法StandardTestMethodforChemicalResistanceofCoatingsUsedinLight-WaterNuclea

7、rPowerPlantsASTMD4082-1995测定Y射线对轻水核电厂涂层所产生影响的标准试验方法StandardTestMethodforEffectsofGammaRadiationonCoatingsforUseinLight-WaterNuclearPowerPlantsASTMD5139-1990核电厂涂层定量检杳样本制备标准规范StandardSpecificationforSamplePreparationforQualificationTestingofCoatingstobeUsedinNuclearPowerPlantsASTMD5163a-2005核电厂运行用I级涂层

8、性能监测程序制定标准指南StandardGuideforEstablishingProcedurestoMonitorthePerformanceofServiceLevelICoatingsinanOperatingNuclearPowerPlantASTMD5962-1996核反应堆I级区域内不合格涂层(油漆)维护标准指南StandardGuideforMaintainingUnqualifiedCoatings(Paints)WithinLevelIAreasofaNuclearPowerFacilityASTMD7167-2005确定核电厂安全相关覆层设备III级里衬系统运行性能监测程

9、序标准指南StandardGuideforEstablishingProcedurestoMonitorthePerformanceofSafety-RelatedCoatingServiceLevelIIILiningSystemsinanOperatingNuclearPowerPlantASTME185-2002轻水冷却核反应堆容器的监督程序设计的标准操作规程StandardPracticeforDesignofSurveillanceProgramsforLight-WaterModeratedNuclearPowerReactorVesselsASTME509-2003轻水冷却核反应

10、堆容器运转冷却过程标准指南StandardGuideforIn-ServiceAnnealingofLight-WaterCooledNuclearReactorVesselsASTME692-2000高分辨率Y射线光谱分析法照射核燃料中铯137的标准试验方法StandardTestMethodforDeterminingtheContentofCesium-137inIrradiatedNuclearFuelsbyHigh-ResolutionGamma-RaySpectralAnalysisASTME1035-2002核反应堆容器支承结构中子辐照量测定标准实施规程StandardPract

11、iceforDeterminingNeutronExposuresforNuclearReactorVesselSupportStructuresASTME2215-2002轻水核电反应堆监视舱评估标准实施规程StandardPracticeforEvaluationofSurveillanceCapsulesfromLight-WaterModeratedNuclearPowerReactorVesselsHD475Sl-1986核电仪器圆板尺寸标准DimensionsofPlanchetsusedinNuclearElectronicInstrumentsHD370S2-1987NIM标准

12、（电子核仪器用）模块插座装置与标准19英寸架式安装装置ModularPlug-inUnitandStandard19-inchRackMountingUnitBasedonNIMStandard(forElectronicNuclearInstruments)HD462Sl-1987正常操作与事故条件下轻水核反应堆液流处理监控设备ProcessStreamRadiationMonitoringEquipmentinLightWaterNuclearReactorsforNormalOperatingandIncidentConditionsANSI/IEEE7-4.3.2-2003核电厂安全系

13、统数字计算机标准CriteriaforDigitalComputersinSafetySystemsofNuclearPowerGeneratingStationsANSI/IEEE308-2001核电厂1E级电力系统标准PowerSystemsforNuclearPowerGeneratingStations,CriteriaforClass1EANSI/IEEE317-1983核电厂安全壳结构电气贯穿组件ElectricPenetrationAssembliesinContainmentStructuresforNuclearPowerGeneratingStationsANSI/IEEE

14、323-2003核电厂1E级设备质量鉴定QualifyingClass1EEquipmentforNuclearPowerGeneratingStationsANSI/IEEE334-1999核电厂1E级电动机连续负载质量鉴定QualifyingContinuousDutyClass1EMotorsforNuclearPowerGeneratingStationsANSI/IEEE344-2004核电厂1E级设备防震鉴定推荐实施规范RecommendedPracticeforSeismicQualificationofClass1EEquipmentforNuclearPowerGenerat

15、ingStationsANSI/IEEE338-1987核电厂安全系统周期监督检测准则CriteriaforthePeriodicSurveillanceTestingofNuclearPowerGeneratingStationSafetySystemsANSI/IEEE352-1994核电厂安全系统可靠性分析主要原则指南GuideforGeneralPrinciplesofReliabilityAnalysisofNuclearPowerGeneratingStationSafetySystemsANSI/IEEE379-2000核电厂安全系统中单一故障标准应用Applicationoft

16、heSingle-FailureCriteriontoNuclearPowerGeneratingStationSafetySystemsANSI/IEEE382-1996核电厂用带安全相关功能的电力操作阀组件的执行机构的合格鉴定ActuatorsforPower-OperatedValveAssemblieswithSafety-RelatedFunctionsforNuclearPower-Plants,QualificationofANSI/IEEE383-2003核电厂1E级电缆质量鉴定与现场拼接标准StandardforQualifyingClass1EElectricCablesa

17、ndFieldSplicesforNuclearPowerGeneratingStationsANSI/IEEE387-1995核电厂备用柴油发电机电源标准准则StandardCriteriaforDiesel-GeneratorUnitsAppliedasStandbyPowerSuppliesforNuclearPowerGeneratingStationsANSI/IEEE420-2001核电厂用1E级控制台、控制板及操纵板的设计和合格鉴定标准StandardfortheDesignandQualificationofClass1EControlBoards,PanelsandRacks

18、UsedinNuclearPowerGeneratingStationsANSI/IEEE497-2002核电厂用事故监测仪标准判据StandardCriteriaforAccidentMonitoringInstrumentationforNuclearPowerGeneratingStationsANSI/IEEE572-2004核电厂1E级连接组件的质量鉴定标准StandardforQualificationofClass1EConnectionAssembliesforNuclearPowerGeneratingStationsANSI/IEEE577-2004核电厂安全系统的设计及运

19、行中的可靠性分析要求ReliabilityAnalysisintheDesignandOperationofSafetySystemsforNuclearPowerGeneratingStations,RequirementsforANSI/IEEE628-2001核电厂1E级电路电缆管道系统的设计、安装和合格鉴定的标准RacewaySystemsforClass1ECircuitsforNuclearPowerGeneratingStations,CriteriafortheDesign,Installation,andQualificationofANSI/IEEE638-1992核电厂用

20、IE级变压器的合格鉴定StandardforQualificationofClass1ETransformersforNuclearPowerGeneratingStationsANSI/IEEE649-1992核电厂用合格的1E级电动机控制台QualifyingClass1EMotorControlCentersforNuclearPowerGeneratingStationsANSI/IEEE650-1991核电厂用1E级静态电池充电器与转换器的鉴定QualificationsofClass1EStaticBatteryChargersandInvertersforNuclearPower

21、GeneratingStationsANSI/IEEE690-2004核电厂1E级电路用电缆系统的设计和安装DesignandInstallationofCableSystemsforClass1ECircuitsinNuclearPowerGeneratingStationsANSI/IEEE741-2002核电厂1E类电力系统和设备防护的标准判据StandardCriteriafortheProtectionofClass1EPowerSystemsandEquipmentinNuclearPowerGeneratingStationsANSI/IEEE765-2002核电厂优先选用电源P

22、referredPowerSupplyforNuclearPowerGeneratingStationsANSI/IEEE845-1999核电厂、控制室和其他周边区域人-机系统性能评价指南GuidetoEvaluationofMan-MachinePerformanceinNuclearPowerGeneratingStations,ControlRooms,andOtherPeripheriesANSI/IEEE933-1999核电厂可靠性工作计划定义指南GuidefortheDefinitionofReliabilityProgramPlansforNuclearPowerGenerati

23、ngStationsANSI/IEEE1023-2004核电厂与其他核设施的系统、设备和装置的人体工程力学应用推荐实施规程RecommendedPracticefortheApplicationofHumanFactorsEngineeringtoSystems,Equipment,andFacilitiesofNuclearPowerGeneratingStationsandOtherNuclearFacilitiesANSI/IEEE1082-1997核电厂人类行为可靠性分析指南GuideforIncorporatingHumanActionReliabilityAnalysisforNu

24、clearPowerGeneratingStationsANSI/IEEE1205-2000核电厂1E级设备老化影响的判定、监测与减轻处理Assessing,Monitoring,andMitigatingAgingEffectsonClass1EEquipmentUsedinNuclearPowerGeneratingStationsANSI/IEEE1289-2004核电厂计算机监测与控制显示设备的人体工程力学设计应用指南GuidefortheApplicationofHumanFactorsEngineeringintheDesignofComputer-BasedMonitoringa

25、ndControlDisplaysforNuclearPowerGeneratingStationsANSI/IEEE1290-1996核电厂电动控制阀门电机应用、保护、控制与试验指南GuideforMOV(Motor-OperatedValve)MotorApplication,Protection,Control,andTestinginNuclearPowerGeneratingStationsANSI/IEEEC37.82-1987核电厂1E级装置用开关装置组件鉴定SwitchgearAssembliesforClass1EApplicationsinNuclearPowerGener

26、atingStations,QualificationofANSI/IEEEC37.105-1987核电厂1E防护继电器与附件鉴定标准QualifyingClass1EProtectiveRelaysandAuxiliariesforNuclearPowerGeneratingStationsASMEBPVCSection3Division3ASME锅炉与压力容器规程第3章：核设施元部件制造规则第3部分：消耗核燃料和高等级放射性废物用外壳系统和运输包装ASMEBoiler&PressureVesselCode-Section3:RulesforConstructionofNuclear

27、FacilityComponents;Division3;ContainmentSystemsandTransportPackagingforSpentNuclearFuelandHighLevelRadASMEBPVCSection11-2001ASME锅炉与压力容器规程第11章：核电厂部件在役监察规则ASMEBoiler&PressureVesselCode-Section11:RulesforInserviceInspectionofNuclearPowerPlantComponentsANSI/ASMEOM-1990核电厂运行与维护OperationandMaintenance

28、ofNuclearPowerPlantsASMEOMCODE-1998核电厂运行与维护规程CodeforOperationandMaintenanceofNuclearPowerPlantsANSI/ASMEOMCode-2004核电厂运行与维护规程CodeforOperationandMaintenanceofNuclearPowerPlantsASMEOMInterpretations1990-1说明：核电厂运行与维护规程Interpretations:CodeforOperationandMaintenanceofNuclearPowerPlantsASMEOMInterpretatio

29、ns1990-8说明：核电厂运行与维护规程Interpretations:CodeforOperationandMaintenanceofNuclearPowerPlantsASMEOMInterpretations1990-12说明：核电厂运行与维护规程Interpretations:CodeforOperationandMaintenanceofNuclearPowerPlantsANSI/ASMEOM-S/G-2OO3核电厂运行、维护标准与指南StandardsandGuidesforOperationandMaintenanceofNuclearPowerPlantsANSI/ASME

30、OM-S/Ga-2004核电厂运行、维护标准与指南StandardsandGuidesforOperationandMaintenanceofNuclearPowerPlantsASMEOMa-S/GAddenda-2001核电厂运行、维护标准与指南：附录StandardsandGuidesforOperationandMaintenanceofNuclearPowerPlants;AddendaANSI/ASMEOMaCode-2005核电厂运行与维护规程CodeforOperationandMaintenanceofNuclearPowerPlantsASMEOMaCODEAddenda-

31、1999核电厂运行与维护规程：附录CodeforOperationandMaintenanceofNuclearPowerPlants;AddendaANSI/ASMEOMb-S/G-2005核电厂运行、维护标准与指南StandardsandGuidesforOperationandMaintenanceofNuclearPowerPlantsASMEOMb-S/GAddenda-2002核电厂运行和维护OperationandMaintenanceofNuclearPowerPlantsASMEOMbCODEAddenda-2000核电厂的运行和维护规程：附录CodeforOperation

32、andMaintenanceofNuclearPowerPlants;AddendaASMEPTC32.2Report-1978轻水反应堆核燃料性能测试方法MethodsofMeasuringthePerformanceofNuclearReactorFuelinLightWaterReactorsANSI/ASMEQME-1-2002核电厂放射性机械设备鉴定QualificationofActiveMechanicalEquipmentforNuclearPowerPlantsASMEQME-laAddenda-1998核电厂放射性机械设备鉴定：附录QualificationofActive

33、MechanicalEquipmentforNuclearPowerPlants;AddendaASMEN45.2.1-1980核电厂流体系统和相关元件的净化处理CleaningofFluidSystemsandAssociatedComponentsforNuclearPowerPlantsASMEN45.2.2-1978核电厂零部件包装、运输、接收、储存与处理Packaging,Shipping,Receiving,Storage,andHandlingofItemsforNuclearPowerPlantsASMEN45.2.3-1973核电厂建设阶段现场清理工作Housekeeping

34、duringtheConstructionPhaseofNuclearPowerPlantsASMEN45.2.3aAddenda-1978核电厂建设阶段现场清理工作：附录HousekeepingduringtheConstructionPhaseofNuclearPowerPlants;AddendaASMEN45.2.5-1978核电厂建设阶段安装、检验并检测结构混凝土、结构钢、土质与地基附加质保规定SupplementaryQualityAssuranceRequirementsforInstallation,Inspection,andTestingofStructuralConcre

35、te,StructuralSteel,Soils,andFoundationsduringtheConstructionPhaseofNuclearPowerPlantsASMEN45.2.6-1978核电厂监察、验收与检测人员资质鉴定QualificationsofInspection,Examination,andTestingPersonnelforNuclearPowerPlantsASMEN45.2.8-1975核电厂建设阶段机械设备与系统的安装、检验与检测附加质保规定SupplementaryQualityAssuranceRequirementsforInstallation,I

36、nspectionandTestingofMechanicalEquipmentandSystemsfortheConstructionPhaseofNuclearPowerPlantsASMEN45.2.8aAddenda-1981核电厂建设阶段机械设备与系统的安装、检验与检测附加质保规定：附录SupplementaryQualityAssuranceRequirementsforInstallation,InspectionandTestingofMechanicalEquipmentandSystemsfortheConstructionPhaseofNuclearPowerPlants

37、;AddendaASMEN45.2.9-1979核电厂质保记录的收集、存放与维护规定RequirementsforCollection,Storage,andMaintenanceofQualityAssuranceRecordsforNuclearPowerPlantsASMEN45.2.11-1974核电厂设计质保规定QualityAssuranceRequirementsfortheDesignofNuclearPowerPlantsASMEN45.2.12-1977核电厂质保程序评审规定RequirementsforAuditingofQualityAssuranceProgramsf

38、orNuclearPowerPlantsASMEN45.2.13-1976核电厂零部件、劳务采购管理质保规定QualityassurancerequirementsforcontrolofprocurementofitemsandservicesfornuclearPowerPlantsASMEN45.2.15-1981核电厂部件升降、安装与运输Hoisting,Rigging,andTransportingofItemsforNuclearPowerPlantsASMEN45.2.20-1979核电厂地表下监察工作附加质保规定SupplementaryQualityAssuranceRequ

39、irementsforSubsurfaceInvestigationsforNuclearPowerPlantsASMEN45.2.23-1978核电厂质保计划监察人员资质鉴定QualificationofQualityAssuranceProgramAuditPersonnelforNuclearPowerPlantsANSI/ASMEN509-2002核电厂空气净化设备与部件NuclearPowerPlantAirCleaningUnitsandComponentsASMERA-S-2002核电厂设施风险概率评估ProbalisticRiskAssessmentforNuclearPowerPlantApplicationsANSI/ANS2.10-2003核电厂抗震仪器记录数据的处理与初始评价标准CriteriafortheHandlingandInitialEvaluationofRecordsfromNuclearPowerPlantSeismicInstrumentationANSI/ANS2.23-2002核电厂对地震情况的应对Nu