核电标准、规范与法规清单.docx

ASTM B353-2002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Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding)ASTM B811-2002核反应堆燃料包壳锻制锆合金无缝管标准规范Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel CladdingANSI/ASTM C781-2002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Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear ReactorsASTM C986-1989制定核燃料循环培训计划Developing Training Programs in the Nuclear Fuel CycleASTM C1010-1983核燃料再加工设备的验收、检测与操作前试验Acceptance, Checkout and Pre-Operational Testing of a Nuclear Fuels Reprocessing FacilityASTM C1011-1983核燃料生产用无电极电导仪器选择或规范Selection or Specification of Electrodeless Conductivity Instruments for the Nuclear Fuel CycleASTM C1062-2000核燃料溶解装置设计、制造与安装标准指南Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution FacilitiesASTM C1128-1995核燃料循环材料分析参考材料制备标准指南Standard Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle MaterialsASTM C1156-2003分析核燃料循环材料测定方法的精度建立标准指南Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle MaterialsASTM C1297-2003核燃料循环材料分析实验室分析法鉴定标准指南Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle MaterialsASTM C1431-1999铝基废核燃料腐蚀试验的维护容器清理标准指南Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository DisposalASTM C1454-2000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Standard Guide for Pyrophoricity/Combustibility Testing in Support of Pyrophoricity Analyses of Metallic Uranium Spent Nuclear FuelASTM D3911-2003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Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) ConditionsASTM D3912-1995轻水核电厂涂层耐化学性标准试验方法Standard Test Method for Chemical Resistance of Coatings Used in Light-Water Nuclear Power PlantsASTM D4082-1995测定射线对轻水核电厂涂层所产生影响的标准试验方法Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Light-Water Nuclear Power PlantsASTM D5139-1990核电厂涂层定量检查样本制备标准规范Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power PlantsASTM D5163a-2005核电厂运行用I级涂层性能监测程序制定标准指南Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power PlantASTM D5962-1996核反应堆 I级区域内不合格涂层（油漆）维护标准指南Standard Guide for Maintaining Unqualified Coatings (Paints) Within Level I Areas of a Nuclear Power FacilityASTM D7167-2005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序标准指南Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power PlantASTM E185-2002轻水冷却核反应堆容器的监督程序设计的标准操作规程Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor VesselsASTM E509-2003轻水冷却核反应堆容器运转冷却过程标准指南Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor VesselsASTM E692-2000高分辨率射线光谱分析法照射核燃料中铯137的标准试验方法Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral AnalysisASTM E1035-2002核反应堆容器支承结构中子辐照量测定标准实施规程Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support StructuresASTM E2215-2002轻水核电反应堆监视舱评估标准实施规程Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor VesselsHD 475 S1-1986核电仪器圆板尺寸标准Dimensions of Planchets used in Nuclear Electronic InstrumentsHD 370 S2-1987NIM标准(电子核仪器用)模块插座装置与标准19英寸架式安装装置Modular Plug-in Unit and Standard 19-inch Rack Mounting Unit Based on NIM Standard (for Electronic Nuclear Instruments)HD 462 S1-1987正常操作与事故条件下轻水核反应堆液流处理监控设备Process Stream Radiation Monitoring Equipment in Light Water Nuclear Reactors for Normal Operating and Incident ConditionsANSI/IEEE 7-4.3.2-2003核电厂安全系统数字计算机标准Criteria for Digital Computers in Safety Systems of Nuclear Power Generating StationsANSI/IEEE 308-2001核电厂1E级电力系统标准Power Systems for Nuclear Power Generating Stations, Criteria for Class 1EANSI/IEEE 317-1983核电厂安全壳结构电气贯穿组件Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating StationsANSI/IEEE 323-2003核电厂1E级设备质量鉴定Qualifying Class 1E Equipment for Nuclear Power Generating StationsANSI/IEEE 334-1999核电厂1E级电动机连续负载质量鉴定Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating StationsANSI/IEEE 344-2004核电厂1E级设备防震鉴定推荐实施规范Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating StationsANSI/IEEE 338-1987核电厂安全系统周期监督检测准则Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety SystemsANSI/IEEE 352-1994核电厂安全系统可靠性分析主要原则指南Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety SystemsANSI/IEEE 379-2000核电厂安全系统中单一故障标准应用Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety SystemsANSI/IEEE 382-1996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Actuators for Power-Operated Valve Assemblies with Safety-Related Functions for Nuclear Power-Plants, Qualification ofANSI/IEEE 383-2003核电厂1E级电缆质量鉴定与现场拼接标准Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating StationsANSI/IEEE 387-1995核电厂备用柴油发电机电源标准准则Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating StationsANSI/IEEE 420-2001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Standard for the Design and Qualification of Class 1E Control Boards, Panels and Racks Used in Nuclear Power Generating StationsANSI/IEEE 497-2002核电厂用事故监测仪标准判据Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating StationsANSI/IEEE 572-2004核电厂1E级连接组件的质量鉴定标准Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating StationsANSI/IEEE 577-2004核电厂安全系统的设计及运行中的可靠性分析要求Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations, Requirements forANSI/IEEE 628-2001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Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations, Criteria for the Design, Installation, and Qualification ofANSI/IEEE 638-1992核电厂用IE级变压器的合格鉴定Standard for Qualification of Class 1E Transformers for Nuclear Power Generating StationsANSI/IEEE 649-1992核电厂用合格的1E级电动机控制台Qualifying Class 1E Motor Control Centers for Nuclear Power Generating StationsANSI/IEEE 650-1991核电厂用1E级静态电池充电器与转换器的鉴定Qualifications of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating StationsANSI/IEEE 690-2004核电厂1E级电路用电缆系统的设计和安装Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating StationsANSI/IEEE 741-2002核电厂1E 类电力系统和设备防护的标准判据Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating StationsANSI/IEEE 765-2002核电厂优先选用电源Preferred Power Supply for Nuclear Power Generating StationsANSI/IEEE 845-1999核电厂、控制室和其他周边区域人-机系统性能评价指南Guide to Evaluation of Man-Machine Performance in Nuclear Power Generating Stations, Control Rooms, and Other PeripheriesANSI/IEEE 933-1999核电厂可靠性工作计划定义指南Guide for the Definition of Reliability Program Plans for Nuclear Power Generating StationsANSI/IEEE 1023-2004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Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear FacilitiesANSI/IEEE 1082-1997核电厂人类行为可靠性分析指南Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating StationsANSI/IEEE 1205-2000核电厂1E级设备老化影响的判定、监测与减轻处理Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating StationsANSI/IEEE 1289-2004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Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating StationsANSI/IEEE 1290-1996核电厂电动控制阀门电机应用、保护、控制与试验指南Guide for MOV (Motor-Operated Valve) Motor Application, Protection, Control, and Testing in Nuclear Power Generating StationsANSI/IEEE C37.82-1987核电厂1E级装置用开关装置组件鉴定Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations, Qualification ofANSI/IEEE C37.105-1987核电厂1E防护继电器与附件鉴定标准Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating StationsASME BPVC Section 3 Division 3ASME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ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components; Division 3; Containment Systems and Transport Packaging for Spent Nuclear Fuel and High Level RadASME BPVC Section 11-2001ASME锅炉与压力容器规程第11章：核电厂部件在役监察规则ASME Boiler & Pressure Vessel Code - Section 11: Rules for Inservice Inspection of Nuclear Power Plant ComponentsANSI/ASME OM-1990核电厂运行与维护Operation and Maintenance of Nuclear Power PlantsASME OM CODE-1998核电厂运行与维护规程Code for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM Code-2004核电厂运行与维护规程Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-1说明：核电厂运行与维护规程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-8说明：核电厂运行与维护规程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsASME OM Interpretations 1990-12说明：核电厂运行与维护规程Interpretations: Code for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM-S/G-2003核电厂运行、维护标准与指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OM-S/Ga-2004核电厂运行、维护标准与指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsASME OMa-S/G Addenda-2001核电厂运行、维护标准与指南：附录Standards and Guides for Operation and Maintenance of Nuclear Power Plants; AddendaANSI/ASME OMa Code-2005核电厂运行与维护规程Code for Operation and Maintenance of Nuclear Power PlantsASME OMa CODE Addenda-1999核电厂运行与维护规程：附录Code for Operation and Maintenance of Nuclear Power Plants; AddendaANSI/ASME OMb-S/G-2005核电厂运行、维护标准与指南Standards and Guides for Operation and Maintenance of Nuclear Power PlantsASME OMb-S/G Addenda-2002 核电厂运行和维护Operation and Maintenance of Nuclear Power PlantsASME OMb CODE Addenda-2000核电厂的运行和维护规程：附录Code for Operation and Maintenance of Nuclear Power Plants; AddendaASME PTC 32.2 Report-1978轻水反应堆核燃料性能测试方法Methods of Measuring the Performance of Nuclear Reactor Fuel in Light Water ReactorsANSI/ASME QME-1-2002核电厂放射性机械设备鉴定Qualification of Active Mechanical Equipment for Nuclear Power PlantsASME QME-1a Addenda-1998核电厂放射性机械设备鉴定：附录Qualification of Active Mechanical Equipment for Nuclear Power Plants; AddendaASME N45.2.1-1980核电厂流体系统和相关元件的净化处理Cleaning of Fluid Systems and Associated Components for Nuclear Power PlantsASME N45.2.2-1978核电厂零部件包装、运输、接收、储存与处理Packaging, Shipping, Receiving, Storage, and Handling of Items for Nuclear Power PlantsASME N45.2.3-1973核电厂建设阶段现场清理工作Housekeeping during the Construction Phase of Nuclear Power PlantsASME N45.2.3a Addenda-1978核电厂建设阶段现场清理工作：附录Housekeeping during the Construction Phase of Nuclear Power Plants; AddendaASME N45.2.5-1978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Supplementary Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, Soils, and Foundations during the Construction Phase of Nuclear Power PlantsASME N45.2.6-1978核电厂监察、验收与检测人员资质鉴定Qualifications of Inspection, Examination, and Testing Personnel for Nuclear Power PlantsASME N45.2.8-1975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Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power PlantsASME N45.2.8a Addenda-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Supplementary Quality Assurance Requirements for Installation, Inspection and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants; AddendaASME N45.2.9-1979核电厂质保记录的收集、存放与维护规定Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power PlantsASME N45.2.11-1974核电厂设计质保规定Quality Assurance Requirements for the Design of Nuclear Power PlantsASME N45.2.12-1977核电厂质保程序评审规定Requirements for Auditing of Quality Assurance Programs for Nuclear Power PlantsASME N45.2.13-1976核电厂零部件、劳务采购管理质保规定Quality assurance requirements for control of procurement of items and services for nuclear Power PlantsASME N45.2.15-1981核电厂部件升降、安装与运输Hoisting, Rigging, and Transporting of Items for Nuclear Power PlantsASME N45.2.20-1979核电厂地表下监察工作附加质保规定Supplementary Quality Assurance Requirements for Subsurface Investigations for Nuclear Power PlantsASME N45.2.23-1978核电厂质保计划监察人员资质鉴定Qualification of Quality Assurance Program Audit Personnel for Nuclear Power PlantsANSI/ASME N509-2002核电厂空气净化设备与部件Nuclear Power Plant Air Cleaning Units and ComponentsASME RA-S-2002核电厂设施风险概率评估Probalistic Risk Assessment for Nuclear Power Plant ApplicationsANSI/ANS 2.10-2003核电厂抗震仪器记录数据的处理与初始评价标准Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic InstrumentationANSI/ANS 2.23-2002核电厂