27.120.20 核电站、安全 标准查询与下载

KS A ISO 16117-2022 核临界安全 估计假定临界事故的裂变数量

Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident

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 62241-2022 核电厂 主控室 报警功能及呈现

Nuclear power plants－Main control room－Alarm functions and presentation

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 61888-2022 核电厂 安全重要仪表 跳闸设定点的确定和维护

Nuclear power plants－Instrumentation important to safety－Determination and maintenance of trip setpoints

KS C IEC 61226-2022 核电厂 安全重要仪表和控制 仪表和控制功能的分类

Nuclear power plants－Instrumentation and control important to safety－Classification of instrumentation and control functions

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 A ISO 17873-2022 核设施 核反应堆以外的核设施通风系统设计和运行标准

Nuclear facilities－Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

KS C IEC 61771-2022 核电厂 主控室 设计验证和确认

Nuclear power plants－Main control-room－Verification and validation of design

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 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 C IEC 62465-2022 核电厂 安全重要仪表和控制 电气布线系统老化管理

Nuclear power plants－Instrumentation and control important to safety－Management of ageing of electrical cabling systems

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 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 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 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

T/CNEA 012-2021 核电厂爆破阀定期检查和在役试验

本文件共计8章，其中，1-3章为规范性条款，4-8章为核电厂爆破阀定期检查和在役试验主要内容。主要内容包括：总体要求、检查维护、解体检查、药筒驱动装置输出试验和电气控制回路试验。

The periodic inspect and in-service test of squib valve in nuclear power plant