27.120.20 核电站、安全 标准查询与下载

KS C IEC 60951-1-2022 核电厂 安全重要仪表 事故和事故后条件的辐射监测 第1部分：一般要求

Nuclear power plants－Instrumentation important to safety－ Radiation monitoring for accident and post-accident conditions－ Part 1：General requirements

KS C IEC 60772-2022 核电站安全壳结构中的电气贯穿组件

Electrical penetration assemblies in containment structures for nuclear power generating stations

KS C IEC 60671-2022 核电厂 安全重要仪表和控制系统 监视测试

Nuclear power plants－Instrumentation and control systems important to safety－Surveillance testing

KS A ISO 6527-2022 核电厂 可靠性数据交换 一般准则

Nuclear power plants－Reliability data exchange－General guidelines

KS C IEC 60768-2022 核电厂 安全重要仪表 正常和事故条件下连续在线或在线监测工艺流中放射性的设备

Nuclear power plants－Instrumentation important to safety－Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions

KS A ISO 7385-2022 核电厂 确保可靠性收集数据质量的指南

Nuclear power plants－Guidelines to ensure quality of collected data on reliability

KS C IEC 62003-2022 核电厂 安全重要仪表和控制 电磁兼容性测试要求

Nuclear power plants－Instrumentation and control important to safety－Requirements for electromagnetic compatibility testing

KS C IEC 60964-2022 核电站 控制室 设计

Nuclear power plants－Control rooms－Design

KS C IEC 60988-2022 核电厂 安全重要仪表 用于检测松动部件的声学监测系统：特性、设计标准和操作程序

Nuclear power plants－Instrumentation important to safety－ Acoustic monitoring systems for detection of loose parts: characteristics, design criteria and operational procedures

KS C IEC 60951-3-2022 核电厂 安全重要仪表 事故和事故后条件的辐射监测 第3部分：连续高范围区域伽玛监测设备

Nuclear power plants－Instrumentation important to safety－Radiation monitoring for accident and post-accident conditions－Part 3：Equipment for continuous high range area gamma monitoring

KS C IEC 60965-2022 核电厂 控制室 无法进入主控制室的反应堆停堆的补充控制点

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

KS C IEC 60515-2022 核电站 安全重要仪表 辐射探测器 特性和试验方法

Nuclear power plants－Instrumentation important to safety－ Radiation detectors－Characteristics and test methods

ISO 20041-1:2022 核设施气体流出物和气体排放物中的氚和碳-14活性.第1部分:氚和碳-14的取样

This document presents the methods and provisions for sampling tritium and carbon-14 in the gaseous effluents generated by nuclear facilities during operation and decommissioning. Specifically included are sample withdrawal location, extraction, transport flow measurement, and collection for later analysis. This document doesn’t address to real time measurements of tritium activity and carbon-14 activity in the effluent air of stacks and ducts. Information about real time measurements can be found in Sample processing, analysis and calculations of tritium and carbon-14 emissions will be addressed in future parts of ISO 20041.

Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 1: Sampling of tritium and carbon-14

ASTM E482-22 反应堆容器监测用中子传输方法的应用标准指南

1.1 Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E944 and Practice E853 define appropriate computational procedures. 1.2 Methodology—Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1) validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and in the pressure vessel. 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 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance

T/CECPA 001-2022 核安全级风机民用核安全机械设备许可证申请标准化审查

为规范民用核安全机械设备许可证取证申请工作的开展，进一步明确许可证申请单位应具备的条件以及审评人员应关注的审评要点，根据《中华人民共和国核安全法》、《民用核安全设备监督管理条例》以及《民用核安全设备设计制造安装和无损检验监督管理规定》等，制定本文件。

Standard review of civil nuclear safety machinery and equipment license application nuclear safety-related fan

T/CNEA 017-2021 核电厂防异物管理指南

本文件共计6章，其中，1-3章为规范性条款，4-6章为核电厂防异物管理指南主要内容。主要内容包括：防异物管理总体要求、防异物管理和防异物通用工具。

Guidelines for foreign material exclusion management in nuclear power plant

T/CNEA 015-2021 核电厂三维数字化设计要求 布置设计

本文件共计7章，其中，1-3章为规范性条款，4-7章为核电厂三维数字化设计要求 布置设计主要内容。主要内容包括：三维数字化设计总体技术要求、三维模型内容和精确度、三维设计过程要求和三维模型发布。

General technical requirements for 3D digital design of nuclear power plant—layout design

T/CNEA 016-2021 核电站生产业务数据标准制定技术要求

本文件共计5章，其中，1-3章为规范性条款，4-5章为核电站生产业务数据标准制定技术要求主要内容。主要内容包括：原则与方法和核电站生产数据实体及数据实体属性表填写模板。

Technical requirement for establishment of production business data standard for nuclear power plant

T/CNEA 018-2021 核电厂核应急演习监控与评估

本文件共计6章，其中，1-3章为规范性条款，4-6章为核电厂核应急演习监控与评估主要内容。主要内容包括：演习监控、演习评估和其他要求。

Monitoring and evaluation for nuclear emergency exercise of nuclear power plant

T/CNEA 013-2021 核电厂电动阀和气动阀在役试验

本文件共计5章，其中，1-3章为规范性条款，4-5章为核电厂电动阀和气动阀在役试验主要内容。主要内容包括：在役试验和记录。

Motor-operated valve and air-operated valve in-service test in nuclear power plant