美国核电标准(ASME).docx

美国核电标准(ASME) 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 11-2001ASME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 instrumentsANSI/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 StationsANSI/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 StationsANSI/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 PlantsANSI/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 ActionsANSI/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 StationsANSI/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 PlantsANSI/ANS 6.6.1-1987LWR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 StationsANSI/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 ExaminationANSI/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 StationsANSI/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 PlantsANSI/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 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 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 SystemsANSI/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 StationsANSI/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 StationsANSI/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 ofANSI/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 SystemsANSI/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 StationsANSI/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 ofANSI/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 StationsANSI/ASME OM-1990核电站的运行和维护Operation and Maintenance of Nuclear Power PlantsANSI/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 SationsANSI/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 PeripheriesANSI/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 1EANSI/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 StationsANSI/ASME N509-2002核电厂空气净化设备和部件Nuclear Power Plant Air Cleaning Units and ComponentsANSI/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 StationsANSI/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 PlantsANSI/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 StationsANSI/IEEE 765-2002核电站的优先选用电源Preferred Power Supply for Nuclear Power Generating StationsANSI/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 InstrumentationANSI/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 StationsANSI/IEEE 323-2003核电站1E级设备的质量鉴定Qualifying Class 1E Equipment for Nuclear Power Generating StationsANSI/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 StationsANSI/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 PlantsANSI/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 PlantsANSI/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 PlantsANSI/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 forANSI/ASME OMCode-2004核电厂的维护和操作标准Code for Operation and Maintenance of Nuclear Power PlantsANSI/ASME OMaCode-2005核电厂的操作和维修规范Code for Operation and Maintenance of Nuclear Power PlantsANSI/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 StationsANSI/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 StationsANSI/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 StationsANSI/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 StationsANSI/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 StationsANSI/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 FacilitiesANSI/ANS 18.1-1999核电站.源术语规范Nuclear Power Plants - Source Term SpecificationANSI/ANS 2.23-2002与地震相关的核电厂反应Nuclear Plant Response to an EarthquakeANSI/ANS 6.1.2-1999核电站核辐射防护计算用的中子和射线截面Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power PlantsANSI/ASME OMbCode-2006核电站的操作和维护规程Code for Operation and Maintenance of Nuclear Power PlantsASTM 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 PlantsASTM 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 PlantsASTM 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 VesselsASTM D 4082-1995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 PlantsASTM 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) ConditionsASTM 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 PlantASTM 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 PlantHD 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 3ASME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 IdentificationANSI/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 ElementsASTM 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 CycleASTM 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 FacilityASTM 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 CycleASTM 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 MaterialsASTM 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 DisposalASTM E 692-2000用高分辨率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 AnalysisASTM 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 FuelASTM 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 FacilitiesASTM 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 MaterialsASTM 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