27.120.20 核电站、安全 标准查询与下载

T/CNSCPA 009-2023*:2023 压水堆核电厂蒸汽发生器进口传热管安全检验文件审查指南

本文件综合考虑了当前主要堆型压水堆核电站的特点，明确了压水堆核电厂蒸汽发生器进口传热管安全检验申报文件的审查要求；作为审查者的审查依据，明晰审查边界、统一审查深度，提高审查工作质量；同时，指导设备采购单位合理规划设备采购过程中的质量管理活动，保证进口核安全设备的质量，提高工作效率和质量。

Review guidelines for safety inspection application documents of import heat exchange tubes for steam generator of pressurized water reactor nuclear power plants

T/CNSCPA 006-2023 进口核安全 1、2、3 级安全阀安全检验文件审查指南

为明确安全检验文件审查规范，明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性，督促进口核安全设备采购单位合理合法规划其设备的质量管理活动，保证进口核安全设备的质量，制定本标准。

Review guidelines for safety inspection application documents of import nuclear safety class 1, 2 and 3 Safety Valve

T/CNSCPA 011-2023 进口核安全1、2、3级截止阀 安全检验文件审查指南

为明确安全检验文件审查规范，明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性，督促进口核安全设备采购单位合理合法规划其设备的质量管理活动，保证进口核安全设备的质量，制定本标准。

Review guidelines for safety inspection application documents of import nuclear safety class 1, 2 and 3 Globe Valve

T/CNSCPA 007-2023 进口核安全 1、2、3 级截止阀安全检验文件审查指南

为明确安全检验文件审查规范，明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性，督促进口核安全设备采购单位合理合法规划其设备的质量管理活动，保证进口核安全设备的质量，制定本标准。

Review guidelines for safety inspection application documents of import nuclear safety class 1, 2 and 3 Globe Valve

T/CNSCPA 009-2023 压水堆核电厂蒸汽发生器进口传热管安全检验文件审查指南

本文件综合考虑了当前主要堆型压水堆核电站的特点，明确了压水堆核电厂蒸汽发生器进口传热管安全检验申报文件的审查要求；作为审查者的审查依据，明晰审查边界、统一审查深度，提高审查工作质量；同时，指导设备采购单位合理规划设备采购过程中的质量管理活动，保证进口核安全设备的质量，提高工作效率和质量。

Review guidelines for safety inspection application documents of import heat exchange tubes for steam generator of pressurized water reactor nuclear power plants

T/CNSCPA 010-2023 进口核安全1、2、3级安全阀 安全检验文件审查指南

为明确安全检验文件审查规范，明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性，督促进口核安全设备采购单位合理合法规划其设备的质量管理活动，保证进口核安全设备的质量，制定本标准。

Review guidelines for safety inspection application documents of imported nuclear safety class 1, 2 and 3 Safety Valve

T/CNSCPA 012-2023 进口核安全2、3级仪表阀安全检验文件审查指南

本审查文件通过确立明确的安全检验文件审查规范，让审查者在审查进口核安全2、3级仪表阀的安全检验文件时有据可依，从而明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性。同时，让进口核安全设备采购单位合理合法规划其设备的质量管理活动，从而保证进口核安全设备的质量，提高采购效率，特制定本标准。

Review guidelines for safety inspection application documents of import nuclear safety class2 and 3 instrumentation valves

T/CNSCPA 008-2023 进口核安全 2、3 级仪表阀安全检验文件审查指南

本审查文件通过确立明确的安全检验文件审查规范，让审查者在审查进口核安全2、3级仪表阀的安全检验文件时有据可依，从而明晰审查边界、统一审查深度，提高审查工作质量的可靠性和稳定性。同时，让进口核安全设备采购单位合理合法规划其设备的质量管理活动，从而保证进口核安全设备的质量，提高采购效率，制定本标准。

Review guidelines for safety inspection application documents of import nuclear safety class2 and 3 instrumentation valves

ASTM E3104-17(2023) 减少放射性污染扩散的可剥离和可去除涂层的标准规范

1.1 This specification is intended to provide a basis for identification of strippable/removable materials used to immobilize radioactive contamination, minimize worker exposure, and facilitate subsequent decontamination or to protect uncontaminated areas against the spread of radioactive contamination. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Strippable and Removable Coatings to Mitigate Spread of Radioactive Contamination

ASTM E1035-18(2023) 核反应堆容器支撑结构中子暴露量测定的标准实施规程

1.1 This practice covers procedures for monitoring the neutron radiation exposures experienced by ferritic materials in nuclear reactor vessel support structures located in the vicinity of the active core. This practice includes guidelines for: 1.1.1 Selecting appropriate dosimetric sensor sets and their proper installation in reactor cavities. 1.1.2 Making appropriate neutronics calculations to predict neutron radiation exposures. 1.2 The values stated in SI units are to be regarded as standard; units that are not SI can be found in Terminology E170 and are to be regarded as standard. Any values in parentheses are for information only. 1.3 This practice is applicable to all pressurized water reactors whose vessel supports will experience a lifetime neutron fluence (E > 1 MeV) that exceeds 1 × 1017 neutrons/ cm2 or exceeds 3.0 × 10−4 dpa (1).2 (See Terminology E170.) 1.4 Exposure of vessel support structures by gamma radiation is not included in the scope of this practice, but see the brief discussion of this issue in 3.2. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. (For example, (2).) 1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures

ASTM E3105-17(2023) 用于减少放射性污染扩散的永久涂层的标准规范

1.1 This specification is intended to provide a basis for identification of non-removable permanent coatings and fixatives as a long-term measure used to immobilize radioactive contamination, minimize worker exposure, and to protect uncontaminated areas against the spread of radioactive contamination. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

Standard Specification for Permanent Coatings Used to Mitigate Spread of Radioactive Contamination

IEC TR 63468:2023 核设施.仪表和控制以及电力系统.人工智能应用

Nuclear facilities - Instrumentation and control, and electrical power systems - Artificial Intelligence applications

ISO/CD 3579 反应堆技术-核电站-结构模块安装

Reactor technology — Nuclear Power Plants —Installation of Structural modules

ISO/FDIS 7753 核临界安全 运行临界事故报警系统的使用

Nuclear criticality safety — Use of criticality accident alarm systems for operations

ISO/CD 4917-5 核电厂抗震设计 第5部分：地震仪器

Design of Nuclear Power Plants against Seismic Events — Part 5: Seismic Instrumentation

ISO/DIS 4917-3 核电站抗震设计 第3部分：土木结构

Design of Nuclear Power Plants against Seismic Events — Part 3: Civil Structures

ISO/DIS 4917-6 核电厂抗震设计 第6部分：震后措施

Design of Nuclear Power Plants against Seismic Events — Part 6: Post-Seismic Measures

ISO/DIS 4917-4 核电厂抗震设计 第4部分：部件

Design of Nuclear Power Plants against Seismic Events — Part 4: Components

ISO/DIS 4917-1 核电厂抗震设计 第1部分：原理

Design of Nuclear Power Plants against Seismic Events — Part 1: Principles

23/30472818 DC BS IEC 63435 核电站 控制室 运营支持系统

BS IEC 63435. Nuclear power plants. Control rooms. Operatoring support system