| 编号 | 中文名称 | 英文名称 |
| ASME QME-1a Addenda-1998 | 核电厂用放射性机械设备的合格证书.附录 | (Qualification of active mechanical equipment used in nuclear power plants; Addenda) |
| ASME BPVC Section 11-2001 | ASME锅炉和压力容器规程.第11节:核电厂元部件在使用中进行检查的规则 | (ASME Boiler & Pressure Vessel Code - Section 11: Rules for Inservice Inspection of Nuclear Power Plant Components) |
| ASME OMa-S/G Addenda-2001 | 核电厂运行和维护的标准及导则.附录 | (Standards and guides for operation and maintenance of nuclear power plants; Addenda) |
| ASME N45.2.2-1978 | 核电站零部件的包装,航运,接收,储存和处理 | (Packaging, shipping, receiving, storage, and handling of items for nuclear power plants) |
| ASME OMb-S/G Addenda-2002 | 核电厂运行和维护 | (Operation and maintenance of nuclear power plants) |
| ASME N45.2.11-1974 | 核电厂设计的质量保证要求 | (Quality assurance requirements for the design of nuclear power plants) |
| ASME OMa CODE Addenda-1999 | 核电厂的运行和维护规程.附录 | (Code for operation and maintenance of nuclear power plants; Addenda) |
| ASME N45.2.12-1977 | 核电厂评审质量保证计划的要求 | (Requirements for auditing of quality assurance programs for nuclear power plants) |
| ASME OM CODE-1998 | 核电厂的运行和维护规程 | (Code for operation and maintenance of nuclear power plants) |
| ASME N45.2.15-1981 | 核电厂零部件的升降,安装和运输 | (Hoisting, rigging, and transporting of items for nuclear power plants) |
| ASME 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; Addenda) |
| ASME N45.2.8-1975 | 核电厂建筑阶段机械设备和系统的安装,检验和测试用附加质量保证要求 | (Supplementary quality assurance requirements for installation, inspection and testing of mechanical equipment and systems for the construction phase of nuclear power plants) |
| ASME N45.2.5-1978 | 核电厂建筑阶段结构混凝土,结构钢,土质和地基的安装,检验以及测试用附加质量保证要求 | (Supplementary quality assurance requirements for installation, inspection, and testing of structural concrete, structural steel, soils, and foundations during the construction phase of nuclear power p) |
| ASME N45.2.20-1979 | 核电厂地表以下勘测的附加质量保证要求 | (Supplementary quality assurance requirements for subsurface investigations for nuclear power plants) |
| ASME N45.2.3a Addenda-1978 | 核电站建筑阶段的房屋维护.附录 | (Housekeeping during the construction phase of nuclear power plants; Addenda) |
| ASME RA-S-2002 | 核电厂设施的概率风险评估 | (Probalistic risk assessment for nuclear power plant applications) |
| ASME N45.2.6-1978 | 核电厂的检验,验收和测试人员的资格鉴定 | (Qualifications of inspection, examination, and testing personnel for nuclear power plants) |
| ASME N45.2.8a Addenda-1981 | 核电厂建筑阶段机械设备和系统的安装,检验和测试用附加质量保证要求.附录 | (Supplementary quality assurance requirements for installation, inspection and testing of mechanical equipment and systems for the construction phase of nuclear power plants; Addenda) |
| ASME N45.2.23-1978 | 核电厂质量保证计划审查人员的资格鉴定 | (Qualification of quality assurance program audit personnel for nuclear power plants) |
| ASME OM Interpretations 1990-1 | 说明:核电厂操作和维护规程 | (Interpretations: Code for operation and maintenance of nuclear power plants) |
| ASME N45.2.9-1979 | 核电厂质量保证记录收集,存放和维护的要求 | (Requirements for collection, storage, and maintenance of quality assurance records for nuclear power plants) |
| ASME N45.2.3-1973 | 核电站建筑阶段的房屋维护 | (Housekeeping during the construction phase of nuclear power plants) |
| ASME 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 componends for nuclear power plants) |
| ASME N45.2.13-1976 | 核电厂控制采购零部件及劳务的质量保证要求 | (Quality assurance requirements for control of procurement of items and services for nuclear power plants) |
| ASME OM Interpretations August | 说明:核电厂操作及维护规范 | (Interpretations: Code for operation and maintenance of nuclear power plants) |
| ASME OM Interpretations Decemb | 说明:核电厂操作及维护规范 | (Interpretations: Code for operation and maintenance of nuclear power plants) |
| HD 475 S1-1986 | 核电子仪器用圆片尺寸 | Dimensions of planchets used in nuclear electronic instruments |
| ANSI/IEEE 387-1995 | 作为核电站备用电源的柴油发电机装置的标准准则 | Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations |
| ANSI/IEEE 650-1991 | 核电站用1E级静态电池充电器和转换器的鉴定 | Qualifications of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations |
| ANSI/ANS 3.4-1996 | 核电站持证上岗人员的健康认证与监测 | Medical Certification and Monitoring of Personnel Requiring Operating Licenses for Nuclear Power Plants |
| ANSI/ANS 58.8-1994 | 核电站.有关安全操作人员行为的时间响应设计准则 | Nuclear Power Plants - Time Response Design Criteria for Safety Related Operator Actions |
| ANSI/IEEE 1290-1996 | 核电站电动控制阀门电机的应用、保护、控制和试验指南 | Guide for MOV (Motor-Operated Valve) Motor Application, Protection, Control, and Testing in Nuclear Power Generating Stations |
| ANSI/ANS 3.1-1993 | 核电厂人员选择,资格和培训 | Selection, Qualification, and Training of Personnel for Nuclear Power Plants |
| ANSI/ANS 6.6.1-1987 | LWR核电站直接的和散射的伽马辐射的计算和测量 | Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants, |
| ANSI/IEEE 649-1992 | 核电站用合格的1E级电动机控制台 | Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations |
| ANSI/ANS 3.5-1998 | 操作者训练和检验用核电厂模拟装置 | Nuclear Power Plant Simulators for Use in Operator Training and Examination |
| ANSI/IEEE 1082-1997 | 核电站采纳人类行为可靠性分析的指南 | Guide for Incorporating Human Action Reliability Analysis for Nuclear Power Generating Stations |
| ANSI/ISA S67.10-1994 | 核电站中使用的取样管线管系和管道标准 | Sample-Line Piping and Tubing Standard for Use in Nuclear Power Plants |
| ANSI/IEEE 352-1994 | 核电站安全系统可靠性分析一般原则指南 | Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
| ANSI/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 of |
| ANSI/IEEE 338-1987 | 核电站安全系统周期监督检测的准则 | Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems |
| ANSI/IEEE 317-1983 | 核电站安全壳结构的电气贯穿组件 | Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations |
| ANSI/IEEE 638-1992 | 核电站用IE级变压器的合格鉴定 | Standard for Qualification of Class 1E Transformers for Nuclear Power Generating Stations |
| ANSI/IEEE 628-2001 | 核电站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 of |
| ANSI/IEEE 379-2000 | 核电站安全系统中单一故障标准的应用 | Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems |
| ANSI/IEEE C37.105-1987 | 核电站用的1E防护继电器和附件的合格鉴定标准 | Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations |
| ANSI/IEEE C37.82-1987 | 应用于核电站的1E级装置用开关装置组件的合格鉴定 | Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations, Qualification of |
| ANSI/IEEE 933-1999 | 核电站可靠性工作计划的定义指南 | Guide for the Definition of Reliability Program Plans for Nuclear Power Generating Stations |
| ANSI/ASME OM-1990 | 核电站的运行和维护 | Operation and Maintenance of Nuclear Power Plants |
| ANSI/IEEE 1205-2000 | 核电站用1E级设备老化影响的评定、监测和减轻 | Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in Nuclear Power Generating Sations |
| ANSI/IEEE 845-1999 | 核电站、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 Peripheries |
| ANSI/IEEE 308-2001 | 核电站1E级电力系统的标准 | Power Systems for Nuclear Power Generating Stations, Criteria for Class 1E |
| ANSI/IEEE 420-2001 | 核电站用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 Stations |
| ANSI/ASME N509-2002 | 核电厂空气净化设备和部件 | Nuclear Power Plant Air Cleaning Units and Components |
| ANSI/IEEE 741-2002 | 核电站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 Stations |
| ANSI/ASME QME-1-2002 | 核电站用放射性机械设备的合格鉴定 | Qualification of Active Mechanical Equipment for Nuclear Power Plants |
| ANSI/IEEE 497-2002 | 核电站用事故监测仪标准判据 | Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
| ANSI/IEEE 765-2002 | 核电站的优先选用电源 | Preferred Power Supply for Nuclear Power Generating Stations |
| ANSI/ANS 2.10-2003 | 核电站地震测量仪记录数据的处理和初始评价标准 | Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation |
| ANSI/IEEE 7-4.3.2-2003 | 核电站安全系统中数字计算机标准 | Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
| ANSI/IEEE 323-2003 | 核电站1E级设备的质量鉴定 | Qualifying Class 1E Equipment for Nuclear Power Generating Stations |
| ANSI/IEEE 383-2003 | 核电站1E级电缆质量鉴定和现场拼接标准 | Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations |
| ANSI/ASME OM-S/Ga-2004 | 核电站的运行和维护的标准和指南 | Standards and Guides for Operation and Maintenance of Nuclear Power Plants |
| ANSI/ASME OM-S/G-2003 | 核电站的运行和维护的标准和指南 | Standards and Guides for Operation and Maintenance of Nuclear Power Plants |
| ANSI/ASME OMb-S/G-2005 | 核电厂操作和维护的标准和指南 | Standards and Guides for Operation and Maintenance of Nuclear Power Plants |
| ANSI/IEEE 577-2004 | 核电站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 for |
| ANSI/ASME OMCode-2004 | 核电厂的维护和操作标准 | Code for Operation and Maintenance of Nuclear Power Plants |
| ANSI/ASME OMaCode-2005 | 核电厂的操作和维修规范 | Code for Operation and Maintenance of Nuclear Power Plants |
| ANSI/IEEE 572-2004 | 核电站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 Stations |
| ANSI/IEEE 334-1999 | 核电站1E级电动机连续负载质量鉴定 | Qualifying Continuous Duty Class 1E Motors for Nuclear Power Generating Stations |
| ANSI/IEEE 344-2004 | 核电站1E级设备防震鉴定的推荐实施规范 | Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations |
| ANSI/IEEE 690-2004 | 核电站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 Stations |
| ANSI/IEEE 1289-2004 | 核电站用基于计算机的监测和控制显示器的设计中的人因工程的应用指南 | Guide for the Application of Human Factors Engineering in the Design of Computer-Based Monitoring and Control Displays for Nuclear Power Generating Stations |
| ANSI/IEEE 1023-2004 | 核电站和其他核装置的系统、设备和装置的人因工程应用的推荐实施规程 | Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities |
| ANSI/ANS 18.1-1999 | 核电站.源术语规范 | Nuclear Power Plants - Source Term Specification |
| ANSI/ANS 2.23-2002 | 与地震相关的核电厂反应 | Nuclear Plant Response to an Earthquake |
| ANSI/ANS 6.1.2-1999 | 核电站核辐射防护计算用的中子和γ射线截面 | Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants |
| ANSI/ASME OMbCode-2006 | 核电站的操作和维护规程 | Code for Operation and Maintenance of Nuclear Power Plants |
| ASTM D 5139-1990 | 核电厂用涂层定量检查用的样品制备标准规范 | Standard Specification for Sample Preparation for Qualification Testing of Coatings to be Used in Nuclear Power Plants |
| ASTM D 3912-1995 | 轻水核电站用涂层耐化学性的标准试验方法 | Standard Test Method for Chemical Resistance of Coatings Used in Light-Water Nuclear Power Plants |
| ASTM E 2215-2002 | 评价轻水核电反应堆监视舱的标准实施规程 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
| ASTM D 4082-1995 | Υ射线对轻水核电站用涂层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 Plants |
| ASTM D 3911-2003 | 设计基本事故(DBA)的模拟条件下评价轻水核电站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) Conditions |
| ASTM D 5163a-2005 | 核电厂运行时使用的I级涂层性能监测程序制定的标准指南 | Standard Guide for Establishing Procedures to Monitor the Performance of Service Level I Coatings in an Operating Nuclear Power Plant |
| ASTM D 7167-2005 | 运行的核电厂中与安全有关的覆层设备III级里衬系统性能监测程序确定用标准指南 | Standard Guide for Establishing Procedures to Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant |
| HD 370 S2-1987 | 基于NIM标准(电子核仪器用)的模块插座装置和标准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) |
| ASME BPVC Section 3 Division 3 | ASME锅炉和压力容器规程.第3节:核设施元部件制造规则.第3分册.消耗核燃料和高等级放射性废物用外壳系统和运 | (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 Rad) |
| ASME PTC 32.2 Report-1978 | 轻水反应堆中核燃料性能测试方法 | (Methods of measuring the performance of nuclear reactor fuel in light water reactors) |
| ANSI/ANS 57.8-1995 | 核燃料组件的标识 | Nuclear Fuel Assembly Identification |
| ANSI/ANS 15.2-1999 | 片状铝铀核燃料元件的质量控制 | Quality Control for Plate-Type Uranium-Aluminum Fuel Elements |
| ASTM C 1011-1983 | 核燃料生产中用无电极电导仪器的选择指南或规范 | Selection or Specification of Electrodeless Conductivity Instruments for the Nuclear Fuel Cycle |
| ASTM C 1010-1983 | 核燃料再加工设备的验收、检测和操作前试验 | Acceptance, Checkout and Pre-Operational Testing of a Nuclear Fuels Reprocessing Facility |
| ASTM C 986-1989 | 核燃料周期的培训计划的制定及发展 | Developing Training Programs in the Nuclear Fuel Cycle |
| ASTM C 1128-1995 | 核燃料循环材料分析用操作参考材料制备的标准指南 | Standard Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle Materials |
| ASTM C 1431-1999 | 维护容器清理用铝基废核燃料腐蚀检验的标准导则 | Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal |
| ASTM E 692-2000 | 用高分辨率γ射线光谱分析法对照射过的核燃料中的铯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 Analysis |
| ASTM C 1454-2000 | 通过对燃烧核燃料的金属铀的自燃分析进行自燃/易燃性试验的标准指南 | Standard Guide for Pyrophoricity/Combustibility Testing in Support of Pyrophoricity Analyses of Metallic Uranium Spent Nuclear Fuel |
| ASTM C 1062-2000 | 核燃料溶解装置的设计、制造和安装标准指南 | Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities |
| ASTM B 353-2002 | 核设施(核燃料包壳除外)用锻制的锆及锆合金无缝与焊接管标准规范 | Standard Specification for Wrought Zirconium and Zirconium Alloy Seamless and Welded Tubes for Nuclear Service (Except Nuclear Fuel Cladding) |
| ASTM C 1297-2003 | 核燃料循环材料分析用实验室分析法的鉴定标准指南 | Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials |
| ASTM C 1156-2003 | 用于分析核燃料循环材料的测量方法用校准方法的确定的标准指南 | Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials |
| HD 462 S1-1987 | 正常操作和事故条件下轻水核反应堆的液流处理监控设备 | Process stream radiation monitoring equipment in light water nuclear reactors for normal operating and incident conditions |
| ANSI/ASTM C781-2002 | 高温气冷核反应堆石墨及硼酸化石墨元部件试验惯例 | Practice for Testing Graphite and Boronated Graphite Components for High-temperature Gas-cooled Nuclear Reactors |
| ANSI/ANS 56.8-2002 | 核反应堆.安全壳系统泄漏测试要求 | Nuclear Reactors - Containment System Leakage Testing Requirements |
| ANSI/ANS 19.3.4-2002 | 核反应堆热能沉积率的测定 | Determination of Thermal Energy Deposition Rates in Nuclear Reactors |
| ANSI/ANS 19.3-2005 | 核反应堆中子反应速率分布和反应性的测定 | Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors, Determination of |
| ASTM E 185-2002 | 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 Vessels |
| ASTM D 5962-1996 | 评定核反应堆的 I 级区域内连续不合格涂层(油漆)标准指南 | Standard Guide for Maintaining Unqualified Coatings (Paints) Within Level I Areas of a Nuclear Power Facility |
| ASTM E 1035-2002 | 核反应堆容器支承结构的中子辐照量测定标准实施规程 | Standard Practice for Determining NeutronExposures for Nuclear Reactor Vessel Support Structures |
| ASTM B 811-2002 | 核反应堆燃料包壳用锻制锆合金无缝管的标准规范 | Standard Specification for Wrought Zirconium Alloy Seamless Tubes for Nuclear Reactor Fuel Cladding |
| ASTM E 509-2003 | 轻水冷却核反应堆容器在运转中逐渐冷却的标准指南 | Standard Guide for In-Service Annealing of Light-Water Cooled Nuclear Reactor Vessels |
| ASTM C 781-2002 | 高温气冷核反应堆用石墨及硼酸化石墨元部件试验的标准实施规程 | Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors |
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2008-05-17, 10:33
美国核电标准(ASME)
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