F69 核反应堆与核电厂核岛设备 标准查询与下载

NB/T 20422-2017 压水堆核电厂非能动氢气复合器的鉴定

本标准规定了压水堆核电厂非能动氢气复合器的鉴定试验原则、鉴定试验项目、鉴定试验方法和鉴定文件的要求。 本标准适用于压水堆核电厂非能动氢气复合器的鉴定，其他堆型的非能动氢气复合器的鉴定可参照执行。

Qualification of passive autocatalytic hydrogen recombiner for pressurized water reactor NPP

NB/T 20408-2017 核电厂物项包装、运输、装卸、接收、贮存和维护要求

Packaging, transportation, handling, receiving, storage and maintenance requirements for nuclear power plant items

NB/T 20407-2017 压水堆核电厂堆内构件设计制造规范

Specifications for design and manufacturing of internal components of pressurized water reactor nuclear power plants

NB/T 20009.30-2017 压水堆核电厂用焊接材料 第30部分：安全1级设备埋弧焊用低合金钢焊丝和焊剂

Welding consumables for pressurized water reactor nuclear power plants Part 30: Low alloy steel wire and flux for submerged arc welding of safety level 1 equipment

ASME NQA-1-2017 核设施应用的质量保证要求

Quality Assurance Requirements for Nuclear Facility Applications

BS IEC 62646:2016 核电站.控制室.基于计算机的规程

Nuclear power plants. Control rooms. Computer-based procedures

BS EN 60965:2016 核电厂 控制室 用于反应堆停堆的辅助控制室 无需进入主控制室

Nuclear power plants. Control rooms. Supplementary control room for reactor shutdown without access to the main control room

DIN 25449:2016 核设施用钢筋和预应力混凝土元部件.安全概念、作用、设计和施工

Reinforced and prestressed concrete components in nuclear facilities - Safety concept, actions, design and construction

NB/T 20393-2016 压水堆核电厂稳压器电加热器技术条件

本标准规定了压水堆核电厂稳压器电加热器的设计、制造、检验、试验、验收和包装运输等要求。 本标准适用于参照法国RCC系列规范建造的压水堆核电厂稳压器电加热器，其它压水堆核电厂稳压器电加热器可参照使用。

Specification of pressurizer electric heater for pressurized water reactor nuclear power plants

NB/T 20394-2016 核电厂安全级控制盘、屏和机架的设计与鉴定

本标准规定了核电厂安全级控制盘、屏和机架的设计和鉴定基本要求。 本标准适用于核电厂安全缀控制盘、屏和机架的设计与鉴定，其他核反应堆也可参照使用。 本标准不适用于安装在安全级控制盘、屏和机架上的单个部件、插件和外部敷设的电缆的设计与鉴定，但要考虑它们可能对安全级控制盘、屏和机架的设计与鉴定的影响。

Design and qualification of class 1E control boards, panels and racks in nuclear power plants

ANSI/ANS 2.23-2016 核电站对地震的反应

Nuclear Power Plant Response to an Earthquake

GOST R IEC 62342-2016 核电厂. 具有安全重要性的仪表和控制系统. 老化管理

Nuclear power plants. Instrumentation and control systems important to safety. Management of ageing

PNST 120-2016 核电厂. 控制室. 基于计算机的程序

Nuclear power plants. Control rooms. Computer based procedures

PNST 118-2016 核电厂. 具有安全重要性的仪表和控制. 系统执行A类功能的硬件描述语言程控集成电路的研发

Nuclear power plants. Instrumentation and control important to safety. Development of HDL-programmed integrated circuits for systems performing category A functions

PNST 119-2016 核电厂. 具有安全重要性的仪表和控制. 功能有限的工业数字设备的选择和使用

Nuclear power plants. Instrumentation and control important to safety. Selection and use of industrial digital devices of limited functionality

ASME NQA-1-2015 核设施应用的质量保证要求

This Standard provides requirements and guidelines for the establishment and execution of quality assurance programs during siting, design, construction, operation and decommissioning of nuclear facilities. This Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient utilization of nuclear energy, and management and processing of radioactive materials. The Standard focuses on the achievement of results, emphasizes the role of the individual and line management in the achievement of quality, and fosters the application of these requirements in a manner consistent with the relative importance of the item or activity.

Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)

ASME OM-2015 核电站的运行和维护（包括截至 2013年2月的解释）

Establishes the requirements for preservice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor power plants. It identifies the components subject to test or examination, responsibilities, methods, intervals, parameters to be measured and evaluated, criteria for evaluating the results, corrective action, personnel qualification, and record keeping. These requirements apply to: (a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident; (b) pressure relief devices that protect systems or portions of systems that perform one or more of these three functions; and (c) dynamic restraints (snubbers) used in systems that perform one or more of these three functions.

Operation and Maintenance of Nuclear Power Plants (Includes Interpretations through February 2013)

BS IEC/IEEE 62582-5:2015 核电站. 安全重要仪表和控制. 电气设备状态监测方法. 光时域反射计

Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. Optical time domain reflectometry

NB/T 20350-2015 非能动核电厂设计和建造阶段质量保证分级和管理要求

本标准规定了非能动核电厂设计与建造阶段构筑物、系统和部件（以下简称“物项”）、领域（包括设计、采购、制造、施工领域）及相关活动的质量保证分级原则，及每个领域的相关活动各质量保证级别的管理要求。 本标准适用于非能动核电厂设计与建造阶段物项的质量保证分级，以及在设计、采购、制造、施工领域相关活动的质量保证分级管理。与零件、材料相关活动的管理可参考使用，其他类型的核电厂设计和建造阶段质量保证分级也可参考使用。

Quality assurance classification and management requirements for advanced passive nuclear power plant in design and construction phase

NB/T 20367-2015 核电厂核级石墨密封垫片鉴定规程

本标准规定了用试验法进行核电厂核级石墨密封垫片鉴定的试验程序和文件编制等方面的要求。 本标准适用于核电厂核级工艺系统管道法兰和设备法兰用石墨密封垫片(以下简称垫片)的鉴定，垫片典型结构型式见图1。

Qualification procedure for safety classified graphite gasket of nuclear power plants