标准号 |
中文名称 |
英文名称 |
| ANSI/AMCA 520-2004 |
试验促动器的实验室方法 |
|
| ANSI/AMCA 610-1995 |
空气流动速率测量站的试验方法 |
Methods of Testing Airflow Measurement Stations for Rating |
| ANSI/AMCA 99-0068-2003 |
AMCA词汇:产品定义 |
(The AMCA Vocabulary: Product Definitions ) |
| ANSI/AMCA 99-2404-2003 |
离心式风扇用传动设备 |
(Drive Arrangements for Centrifugal Fans ) |
| ANSI/AMCA 99-2406-2003 |
离心式风扇的转向和排量标识 |
(Designation for Rotation and Discharge of Centrifugal Fans ) |
| ANSI/AMCA 99-2410-2003 |
管状离心式风机用传动设备 |
(Drive Arrangements for Tubular Centrifugal Fans ) |
| ANSI/AMCA 99-2412-2003 |
离心式风扇用叶轮直径和插座区 |
(Impeller Diameters and Outlet Areas for Centrifugal Fans ) |
| ANSI/AMCA 99-2413-2003 |
工业离心式风扇的叶轮直径和出口面积 |
(Impeller Diameters and Outlet Areas for Industrial Centrifugal Fans ) |
| ANSI/AMCA 99-2414-2003 |
管状离心式风机用叶轮直径和排气口面积 |
(Impeller Diameters and Outlet Areas for Tubular Centrifugal Fans ) |
| ANSI/AMCA 99-3001-2003 |
轴流风机的尺寸 |
(Dimensions for Axial Fans ) |
| ANSI/AMCA 99-3404-2003 |
有或无出口渐扩段和进气箱的轴流风机传动设备 |
(Drive Arrangements for Axial Fans With or Without Evase and Inlet Box ) |
| ANSI/ANS 10.2-1988 |
科研用计算机程序促进的推荐设计规程 |
Portability of Scientific Computer Programs, Recommended Programming Practices to Facilitate the |
| ANSI/ANS 10.3-1995 |
数字计算机程序文件编制导则 |
Documentation of Computer Software |
| ANSI/ANS 10.4-1987 |
核工业科研和工程用计算机程序验证和校验导则 |
Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, Guidelines for |
| ANSI/ANS 14.1-1975 |
快速脉冲反应堆的运行 |
Fast Pulse Reactors, Operation of |
| ANSI/ANS 14.1-2004 |
快速脉冲反应堆的运行 |
|
| ANSI/ANS 15.1-1990 |
研究反应堆的技术开发规范 |
Research Reactors, Development of Technical Specifications for |
| ANSI/ANS 15.10-1994 |
研究反应堆的停运 |
Decommissioning of Research Reactors |
| ANSI/ANS 15.11-1993 |
研究反应堆设施辐射的防护 |
Radiation Protection at Research Reactor Facilities |
| ANSI/ANS 15.12-1977 |
研究反应堆控制系统污水处理的设计目标及监控 |
Effluents, Design Objectives for and Monitoring of Systems Controlling Research Reactor |
| ANSI/ANS 15.15-1978 |
研究反应堆的反应堆安全系统准则 |
Safety Systems of Research Reactors, Criteria for the Reactor |
| ANSI/ANS 15.16-1982 |
研究反应堆的应急方案 |
Emergency Planning for Research Reactors |
| ANSI/ANS 15.17-1981 |
研究反应堆的消防措施标准 |
Fire Protection Program Criteria for Research Reactors |
| ANSI/ANS 15.19-1991 |
研究反应堆设施用特种核材料的船运和接收 |
Shipment and Receipt of Special Nuclear Material (SNM) by Research Reactor Facilities |
| ANSI/ANS 15.21-1996 |
研究反应堆安全分析报告格式和内容 |
Format and Content for Safety Analysis Reports for Research Reactors |
| ANSI/ANS 15.4-1988 |
研究用反应堆的人员选择和培训 |
Selection and Training of Personnel for Research Reactors |
| ANSI/ANS 15.7-1977 |
研究反应堆现场评定 |
Site Evaluation, Research Reactor |
| ANSI/ANS 15.8-1976 |
研究反应堆, 保险程序要求(ANSI N402-1976的重新设计和重申) |
Quality assurance program requirements for research reactors |
| ANSI/ANS 16.1-2003 |
用短期试验法对固化低放射性废物浸出性的测量 |
(Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure ) |
| ANSI/ANS 19.1-2002 |
反应堆设计计算用核数据集 |
(Nuclear Data Sets for Reactor Design Calculations ) |
| ANSI/ANS 19.11-1997 |
水慢化动力堆反应性的慢化剂温度系数计算和测量 |
Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors |
| ANSI/ANS 19.3-1983 |
中子反应速率分布与核反应堆反应性的测定 |
Neutron Reaction Rate Distributions and Reactivity of Nuclear Reactors, Determination of |
| 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 19.4-1976 |
核分析鉴定用参考动力反应堆物理测量的数据获得及文献工作指南 |
Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification, Guide for |
| ANSI/ANS 19.5-1995 |
标准反应堆的物理测量要求 |
Physics Measurements, Requirements for Reference Reactor |
| ANSI/ANS 19.6.1-1997 |
压水反应堆重新装料起动物理试验 |
Reload Startup Physics Tests for Pressurized Water Reactors |
| ANSI/ANS 2.10-2003 |
核电站地震测量仪表所示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/ANS 2.12-1978 |
核动力反应堆现场内在的与外部人为危险综合考虑导则 |
Natural and External Man-Made Hazards at Power Reactor Sites, Guidelines for Combining |
| ANSI/ANS 2.25-1982 |
需获准建立热电厂的大地生态考查 |
Surveys of Terrestrial Ecology Needed to License Thermal Power Plants |
| ANSI/ANS 2.8-1992 |
核反应堆场所的溢流设计基础的测定 |
Determining Design Basis Flooding at Power Reactor Sites |
| 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 3.2-1994 |
核电厂操作期的质量保证和行政控制 |
Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants |
| ANSI/ANS 3.4-1996 |
核电厂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 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/ANS 3.7.1-1995 |
核电厂辐射事故现场医疗护理用的设备 |
Emergencies, Facilities and Medical Care for On-Site Nuclear Power Plant Radiological |
| ANSI/ANS 3.8.1-1995 |
核电厂应急功能及组织机构标准 |
Nuclear Power Plants - Criteria for Emergency Response Functions and Organizations |
| ANSI/ANS 3.8.2-1995 |
核电厂应急设施的功能和物理特征准则 |
Criteria for Functional and Physical Characteristics of Emergency Response Facilities |
| ANSI/ANS 3.8.3-1995 |
核电厂应急方案与实施程序准则 |
Nuclear Power Plants - Criteria for Emergency Response Plans and Implementing Procedures |
| ANSI/ANS 3.8.4-1995 |
核电厂应急能力的维护准则 |
Nuclear Power Plants - Criteria for Maintaining Emergency Response Capability |
| ANSI/ANS 3.8.5-1992 |
紧急辐射场的监测、采样和分析准则 |
Criteria for Emergency Radiological Field Monitoring, Sampling, and Analysis |
| ANSI/ANS 3.8.6-1995 |
核电厂应急进行场外辐射评估的准则 |
Criteria for Conduct of Offsite Radiological Assessment for Emergency Response for Nuclear Power Plants |
| ANSI/ANS 3.8.7-1998 |
应急准备演习和训练的计划、开发、指导和评价标准 |
Criteria for Planning, Development, Conduct, and Evaluation of Drills and Exercises for Emergency Preparedness |
| ANSI/ANS 40.35-1991 |
低能级放射性废物的体积压缩 |
Volume Reduction of Low Level Radioactive Waste |
| ANSI/ANS 40.37-1993 |
轻便的低能级放射性废物处理装置 |
Mobile Radioactive Waste Processing Systems |
| ANSI/ANS 5.1-2005 |
轻水反应堆衰变热功率 |
|
| ANSI/ANS 5.10-1998 |
非活性核设施气载释放率 |
Airborne Release Fractions at Non-Reactor Nuclear Facilities |
| ANSI/ANS 51.10-1991 |
加压水冷反应堆的供水系统 |
Auxiliary Feedwater System for Pressurized Water Reactors |
| ANSI/ANS 55.1-1992 |
轻水冷却反应堆中固体放射性废物的处理系统 |
Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants |
| ANSI/ANS 55.4-1993 |
轻水反应堆厂气态放射性废物处理系统 |
Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants |
| ANSI/ANS 55.6-1993 |
轻水冷却反应堆中液体放射性废物的处理系统 |
Liquid Radioactive Waste Processing Systems for Light Water Reactor Plants |
| ANSI/ANS 56.8-1994 |
核反应堆安全壳系统泄漏测试要求 |
Nuclear Reactors - Containment System Leakage Testing Requirements |
| 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 57.1-1992 |
轻水反应堆燃料处理系统的设计要求 |
Design Requirements for Light Water Reactor Fuel Handling Systems |
| ANSI/ANS 57.10-1996 |
轻水反应堆废燃料的压力设计准则 |
Design Criteria for Consolidation of LWR Spent Fuel |
| ANSI/ANS 57.5-1996 |
轻水反应堆燃料组件的机械设计和评估 |
Light Water Reactors Fuel Assembly Mechanical Design and Evaluation |
| ANSI/ANS 57.7-1988 |
独立的废燃料贮存设备的设计准则 |
Design Criteria for an Independent Spent Fuel Storage Installation (Water Pool Type) |
| ANSI/ANS 57.8-1995 |
核燃料组件的标识 |
Nuclear Fuel Assembly Identification |
| ANSI/ANS 57.9-1992 |
独立的废燃料贮藏设备的设计准则 |
Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type) |
| ANSI/ANS 58.11-1995 |
轻水反应堆冷却准则 |
Cooldown Criteria for Light Water Reactors |
| ANSI/ANS 58.14-1993 |
轻水反应堆安全与压力综合分类准则 |
Safety and Pressure Integrity Classification Criteria for Light Water Reactors |
| ANSI/ANS 58.2-1988 |
轻水反应堆核电站设定管子断裂影响的防护设计基础 |
Design Basis for Protection of Light Water Nuclear Power Plants against Effects of Postulated Pipe Rupture |
| ANSI/ANS 58.21-2003 |
外部事件PRA方法 |
(External Events PRA Methodology ) |
| ANSI/ANS 58.3-1992 |
核安全有关的系统的件的物理防护 |
Physical Protection for Nuclear Safety-Related Systems and Components |
| ANSI/ANS 58.6-1996 |
轻水反应堆实施远距离关闭的准则 |
Remote Shutdown for Light Water Reactors, Criteria for |
| ANSI/ANS 58.8-1994 |
关于操作安全的时间响应设计准则 |
Nuclear Power Plants - Time Response Design Criteria for Safety Related Operator Actions |
| ANSI/ANS 58.9-2002 |
轻水反应堆有关安全的液体系统的单一故障准则应用 |
(Application of the Single Failure Criterion for Light Water Reactor Safety-Related Fluid Systems ) |
| ANSI/ANS 59.1-1986 |
与核安全有关的轻水反应堆水冷却系统 |
Cooling Water Systems for Light Water Reactors, Nuclear Safety Related |
| ANSI/ANS 59.2-1985 |
主安全外壳的采暖、通风和空调系统的安全准则 |
Nuclear Power Plants - HVAC Systems Located Outside Primary Containment, Safety Criteria for |
| ANSI/ANS 59.3-1992 |
控制空气系统的核安全准则 |
Nuclear Safety Criteria for Control Air Systems |
| ANSI/ANS 59.51-1997 |
应急柴油发动机用的燃油系统 |
Fuel-Oil Systems for Emergency Diesel Generators |
| ANSI/ANS 59.52-1998 |
备用柴油发电机的安全用润滑油系统 |
Lubricating Oil Systems for Safety Related Emergency Diesel Generators |
| ANSI/ANS 6.1.1-1991 |
中子及ｒ射线能量与剂量因素的关系 |
Neutron and Gamma-Ray Fluence-to-Dose Factors |
| ANSI/ANS 6.3.1-1987 |
轻水反应堆(LWR)中辐射屏蔽的测试过程 |
Program for Testing Radiation Shields in Lightwater Reactors |
| ANSI/ANS 6.4-1997 |
核动力厂的混凝土辐射屏蔽.核分析导则和导则设计 |
Concrete Radiation Shielding for Nuclear Power Plants, Guidelines on the Nuclear Analysis and Design of |
| ANSI/ANS 6.4.2-1985 |
辐射屏蔽材料的规范 |
Radiation Shielding Materials, Specification for |
| ANSI/ANS 6.4.3-1991 |
工程材料中γ射线衰变系数和结构因素 |
Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials |
| ANSI/ANS 6.6.1-1987 |
LWR核电站直接和散射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/ANS 8.1-1983 |
反应堆外部可裂变材料的操作中核临界安全 |
Operations with Fissionable Materials Outside Reactors, Nuclear Criticality Safety in |
| ANSI/ANS 8.10-1983 |
操作中使用屏蔽和限制的核临界安全控制标准 |
Nuclear Criticality Safety Controls in Operations with Shielding and Confinement, Criteria for |
| ANSI/ANS 8.12-1987 |
反应堆外部钚铀混合燃料核临界控制和安全 |
Plutonium-Uranium Fuel Mixtures Outside Reactors, Nuclear Criticality Control and Safety of |
| ANSI/ANS 8.14-2004 |
反应堆外部核设施中可溶性中子吸收剂的使用 |
|
| ANSI/ANS 8.15-1981 |
专用锕系素的核临界控制 |
Nuclear Criticality Control of Special Actinide Elements |
| ANSI/ANS 8.17-1984 |
反应堆外部的轻水反应堆燃料的搬运、贮藏和运输准则 |
Handling, Storage, and Transportation of LWR Fuel Outside Reactors, Criteria for |
| ANSI/ANS 8.19-1996 |
核临界安全性管理规程 |
Nuclear Criticality Safety - Administrative Practices |
| ANSI/ANS 8.20-1991 |
核临界安全培训 |
Nuclear Criticality Safety Training |
| ANSI/ANS 8.21-1995 |
混合的中子吸收在核设施外围反应堆的使用 |
Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors |
| ANSI/ANS 8.22-1997 |
限制和控制慢化剂基础上的核临界安全 |
Nuclear Criticality Safety Based on Limiting and Controlling Moderators |
| ANSI/ANS 8.23-1997 |
核临界事故应急设计和反应 |
Nuclear Criticality Accident Emergency Planning and Response |
| ANSI/ANS 8.3-1997 |
核临界事故报警系统 |
Criticality Accident Alarm System |
| ANSI/ANS 8.5-1996 |
易裂变材料溶液中用硼硅玻璃拉希环作中子吸收剂 |
Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material |
| ANSI/ANS 8.6-1983 |
次临界中子增殖现场测量的安全 |
Safety in Conducting Subcritical Neutron-Multiplication Measurements in situ |
| ANSI/ANS/HPSSC 6.8.1-1981 |
轻水核反应堆辐射监测系统,定位和设计标准 |
Radiation Monitoring Systems for Light Water Nuclear Reactors, Location and Design Criteria for Area |
| ANSI/API 10A-2001 |
良好粘接用水泥和材料规范(第23版) |
Specification for Cements and Materials for Well Cementing (Twenty Third Edition) |
| ANSI/API 10B-3-2004 |
深水固井水泥成分检测的推荐实施规程 |
|
| ANSI/API 10D-2001 |
弓形弹簧铸塑中心化子的规范(第6版) |
Specification for Bow-Spring Casing Centralizers (Sixth Edition) |
| ANSI/API 10F-2001 |
水泥灌浆浮标设备性能试验的推荐实施规程 |
Recommended Practice for Performance Testing of Cementing Float Equipment |
| ANSI/API 1104-1999 |
管道和相关设施的焊接 |
Welding of Pipelines and Related Facilities |
| ANSI/API 1107-1992 |
管道保养焊接规程 |
Pipeline Maintenance Welding Practices |
| ANSI/API 1160-2001 |
危险液体管道的管理系统完整性 |
Managing System Integrity for Hazardous Liquid Pipeline |
| ANSI/API 1163-2005 |
在线检查系统合格标准(第1版) |
|
| ANSI/API 13M-2004 |
完井液体粘性测量的推荐规程 |
|
| ANSI/API 14A-2005 |
井下安全阀设备的规范 |
|
| ANSI/API 2000-1992 |
通风大气式低压贮罐 |
Venting Atmospheric and Low-Pressure Storage Tanks (Nonrefrigerated and Refrigerated) |
| ANSI/API 2015-2001 |
石油贮罐的安全入口和清洗 |
Safe Entry and Cleaning of Petroleum Storage Tanks |
| ANSI/API 2510-1996 |
船上及输油管总站、天然气加工厂、炼油厂、石油化工厂及油罐区的液化石油气装置的设计及制造 |
Design and Construction of LPG Installations |
| ANSI/API 2530 Part 1-1991 |
天然气流体测量.同心,方边,有孔测量仪.第1部分:通用方程式和不确定性指南 |
Natural Gas Fluids Measurement - Concentric, Square-Edged Orifice Meters, Part 1 - General Equations and Uncertainty Guidelines |
| ANSI/API 2530 Part 2-1991 |
天然气流体测量.同心,方边,有孔测量仪.第2部分:安装要求和规范 |
Natural Gas Fluids Measurement - Concentric, Square-Edged Orifice Meters, Part 2 - Specification and Installation Requirements |
| ANSI/API 2530 Part 3-1991 |
石油测量标准手册.第14章:天然气流体测量.第3节:同心,方边,有孔测量仪.第3部分:天然气应用 |
Manual of Petroleum Measurement Standards, Chapter 14 - Natural Gas Fluids Measurement, Section 3 - Concentric, Square-Edged Orifice Meters, Part 3 - Natural Gas Applications |
| ANSI/API 2610-1994 |
油库和贮罐设备的设计、建造、操作、维护和检查 |
Design, Construction, Operation, Maintenance and Inspection of Terminal and Tank Facilities |
| ANSI/API 520-1992 |
炼油厂中减压设备的定尺寸、选择和安装.第1部分:定尺寸和选择 |
Sizing, Selection, and Installation of Pressure-Relieving Devices in Refineries - Part I, Sizing and Selection |
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