27.120.20 核电站、安全 标准查询与下载

T/CNS 85-2022 反应堆压力容器辐照监督材料拉伸试验方法

本文件描述了反应堆压力容器材料拉伸试验方法、定义、符号、试样及其尺寸测量、试验设备、试验要求、性能测定、测定结果数值修约和试验报告等内容。

Tensile test method of irradition surveillance for reactor pressure vessel materials

T/CNS 86-2022 核电厂凝汽器钛管涡流检测技术导则

本文件描述了核电厂凝汽器钛管实施内穿过式涡流检测的方法。

Technical guide for eddy current testing in titanium tube of nuclear power plant condenser

T/CNS 57-2022 高温气冷堆核动力厂石墨粉尘去污导则

本文件规定了高温气冷堆核动力厂石墨粉尘去污方法、去污试剂使用、去污实施等方面的技术要求。

Guidelines for graphite dust decontamination in high temperature gas cooled reactor nuclear power plants

T/CNS 58-2022 高温气冷堆核动力厂蒸汽发生器二回路侧停（备）用腐蚀防护导则

本文件规定了高温气冷堆蒸汽发生器二回路侧停（备）用腐蚀防护方法选择的原则和技术要求。

Guidelines for steam generator secondary side corrosion protection during shutdown (standby) in high temperature gas cooled reactor nuclear power plants

T/CNS 61-2022 高温气冷堆核动力厂堆功率阶跃和线性变化动态响应试验导则

本文件规定了高温气冷堆核动力厂在调试阶段的功率阶跃和线性变化动态响应试验的试验目的、先决条件、试验方法、验收准则、注意事项、试验数据和报告等的要求。

Guidelines for reactor power step and linear change dynamic response tests in high temperature gas cooled reactor nuclear power plants

T/CNS 65-2022 高温气冷堆核动力厂输出热功率控制系统闭环试验导则

本文件规定了高温气冷堆核动力厂在调试阶段进行的输出热功率控制系统闭环试验的试验目的、先决条件、试验方法、注意事项、试验数据和报告等的要求。

Guidelines for output thermal power control system closed-loop test in high temperature gas cooled reactor nuclear power plants

T/CNS 73-2022 高温气冷堆核动力厂蒸汽发生器传热管堵管导则

本文件规定了高温气冷堆核动力厂蒸汽发生器传热管堵管工艺和堵头的要求、评定试验、堵管准备、堵管设备要求、堵管操作人员要求、堵管实施及记录和报告等的技术要求。

Guide for tubes plugging of steam generator in high temperature gas cooled reactor

T/CNS 63-2022 高温气冷堆核动力厂核功率控制系统闭环试验导则

本文件规定了高温气冷堆核动力厂在调试阶段的核功率系统闭环试验的试验目的、试验条件、试验方法、注意事项、试验数据和报告等的要求。

Guidelines for nuclear power control system closed-loop test in high temperature gas cooled reactor nuclear power plants

T/CNS 69-2022 高温气冷堆核动力厂蒸汽温度控制系统 闭环试验导则

本文件规定了高温气冷堆核动力厂在调试阶段的蒸汽温度控制系统闭环试验的试验目的、先决条件、试验方法、注意事项、试验数据和报告等的要求。

Guidelines for steam temperature control system closed-loop test in high temperature gas cooled reactor nuclear power plants

T/CNS 87-2022 压水堆核电厂未堆熔的设计扩展工况清单分析导则

本文件规定了压水堆核电厂未堆熔的设计扩展工况清单分析方法和技术要求。

Guide for determination for design extension conditions without obvious core damage of pressurized water reactor nuclear power plants

T/CNS 60-2022 高温气冷堆核动力厂反应堆首次装料及初始临界试验

本文件描述了高温气冷堆核动力厂在调试试验阶段反应堆首次装料及初始临界试验的专门预防措施、先决条件、初始条件、试验步骤及验收准则等。

Reactor first loading and initial criticality test in high temperature gas cooled reactor nuclear power plants

T/CNS 62-2022 高温气冷堆核动力厂氦气流量控制系统闭环试验导则

本文件规定了高温气冷堆核电厂在调试阶段的氦气流量闭环控制回路试验的试验目的、先决条件、试验步骤、注意事项、试验数据和报告等的要求。

Guidelines for helium flow closed-loop control circuit test in high temperature gas cooled reactor nuclear power plants

BS ISO 20041-1:2022 核设施气体流出物和气体排放中的氚和碳 14 活度 氚和碳 14 采样

1   Scope 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 ISO 2889:2021, Annex H. 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 - Sampling of tritium and carbon-14

BS IEC 60910:2022 核电厂 仪表对安全很重要 安全壳监测 以便及早发现轻水反应堆偏离正常运行的情况

Nuclear power plants. Instrumentation important to safety. Containment monitoring for early detection of developing deviations from normal operation in light water reactors

BS IEC/IEEE 62582-2:2022 核电厂 仪表和控制对安全很重要 电气设备状态监测方法 压痕测量

1   Scope This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control systems using the indenter measurement technique in the detail necessary to produce accurate and reproducible measurements. It includes the requirements for the selection of samples, the measurement system and measurement conditions, and the reporting of the measurement results. The different parts of IEC/IEEE 62582 are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582‑1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in the qualification of equipment important to safety is found in IEC/IEEE 60780‑323. This document is intended for application to non-energised equipment.

Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. Indenter measurements

IEC 60951-1:2022 RLV 核设施.对安全重要的仪表系统.事故和事故后条件的辐射监测.第1部分:一般要求

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

IEC 60951-1:2022 核设施.对安全重要的仪表系统.事故和事故后条件的辐射监测.第1部分:一般要求

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

IEC 62397:2022 核电厂.对安全重要的仪表和控制.电阻温度检测器

Nuclear power plants - Instrumentation and control important to safety - Resistance temperature detectors

IEC 62705:2022 RLV 核设施.对安全重要的仪表和控制.辐射监测系统（RMS）:特性和生命周期

Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle

IEC 62705:2022 核设施.对安全重要的仪表和控制.辐射监测系统（RMS）:特性和生命周期

Nuclear facilities - Instrumentation and control important to safety - Radiation monitoring systems (RMS): Characteristics and lifecycle