27.120.20 核电站、安全 标准查询与下载

LST EN IEC/IEEE 62582-6:2021 核电站 安全重要的仪表和控制 电气设备状态监测方法 第6部分：绝缘电阻（IEC/IEEE 62582-6:2019）

Nuclear power plants - Instrumentation and control important to safety - Electrical equipment condition monitoring methods - Part 6: Insulation resistance (IEC/IEEE 62582-6:2019)

KS A ISO 6258-2021 核电厂 抗震设计

Nuclear power plants－Design against seismic hazards

KS C IEC 61468-2021 核电站 堆内仪器 自供电中子探测器的特性和测试方法

Nuclear power plants－In-core instrumentation－Characteristics and test methods of self-powered neutron detectors

KS C IEC 61250-2021 核反应堆 对安全至关重要的仪表和控制系统 冷却剂系统泄漏检测

Nuclear reactors－Instrumentation and control systems important for safety－Detection of leakage in coolant systems

KS C IEC 62645-2021 核电厂 仪表和控制系统 计算机系统安全程序的要求

Nuclear power plants — Instrumentation and control systems — Requirements for security programmes for computer-based systems

BS EN IEC 60987:2021 核电站. 仪表和控制的重要安全性. 硬件要求

Nuclear power plants. Instrumentation and control important to safety. Hardware design requirements for computer-based systems

DS/EN IEC 60987:2021 核电厂“安全重要的仪表和控制”硬件要求

Nuclear power plants – Instrumentation and control important to safety – Hardware requirements

EN IEC 60987:2021 核电厂 安全重要的仪表和控制 硬件要求

IEC 60987:2021 provides requirements and recommendations for the hardware aspects of I&C systems whatever the technology and applies for all safety classes in a graded manner (as defined by IEC 61513). The requirements defined within this document guide, in particular, the selection of pre-existing components, hardware aspects of system detailed design and implementation and equipment manufacturing. This third edition cancels and replaces the second edition published in 2007. This edition includes the following significant technical changes with respect to the previous edition: a) Title modified; b) Take account of the fact that hardware requirements apply to all I&C technologies, including conventional hardwired equipment, programmable digital equipment or by using a combination of both types of equipment; c) Align the standard with the new revisions of IAEA documents SSR-2/1, which include as far as possible an adaptation of the definitions; d) Replace, as far as possible, the requirements associated with standards published since the edition 2.1, especially IEC 61513, IEC 60880, IEC 62138, IEC 62566 and IEC 62566‑2; e) Review the existing requirements and update the terminology and definitions; f) Extend the scope of the standard to all hardware (computerized and non-computerized) and to all safety classes 1, 2 and 3; g) Complete, update the IEC and IAEA references and vocabulary; h) Check possible impact of other IAEA requirements and recommendations considering extension of the scope of SC 45A; i) Highlight the use of IEC 62566 and IEC 62566-2 for HPD development; j) Introduce specific activities for pre-existing items (selection, acceptability and/or mitigation); k) Introduce clearer requirements for electronic module-level design, manufacturing and control; l) Complete reliability assessment methods; m) Introduce requirements when using automated tests or control activities; n) Complete description of manufacturing control activities (control process, assessment of manufactured equipment, preservation of products); o) Define and ensure the inclusion of a graded approach for dealing with the 3 different classes of equipment and related requirements.

Nuclear power plants - Instrumentation and control important to safety - Hardware requirements

BS IEC 63186:2021 核电站 对安全至关重要的仪表和控制系统 地震跳闸系统标准

Nuclear power plants. Instrumentation and control systems important to safety. Criteria for seismic trip system

OVE EN IEC 62003:2021 核电站 仪表、控制和电力系统 电磁兼容性测试要求（德文版）

Nuclear power plants - Instrumentation, control and electrical power systems - Requirements for electromagnetic compatibility testing (german version)

SN EN ISO 16647:2021 核设施 核工地和退役核装置封闭系统的设计和运行标准（ISO 16647:2018）

Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning (ISO 16647:2018)

BS EN IEC 62954:2021 核电厂 控制室 应急响应设施要求

1   Scope This document presents the requirements for the on-site emergency response facilities (referred to hereinafter as the “ ERF ”) which are to be used in case of incidents or accidents occurring on the associated Nuclear Power Plant (NPP). The ERF consists of the Emergency Response Centre ( ERC ), the Technical Support Centre ( TSC ) and the Operational Support Centre ( OSC ), as shown in Figure 1. It establishes requirements for the ERF features and ERF I&C equipment to: • coordinate on-site operational efforts with respect to safety and radioprotection; • optimize the design in terms of environment control, lighting, power supplies and access control of the ERF ; • enhance the identification and resolution of potential conflicts between the traditional operational means and emergency means (MCR/SCR and ERF , operating staff and emergency teams, operational procedures and emergency procedures); • aid the identification and the enhancement of the potential syn...

Nuclear power plants. Control rooms. Requirements for emergency response facilities

BS EN IEC 62855:2021 核电厂 电力系统 电力系统分析

1   Scope IEC 62855 provides the electrotechnical engineering guidelines for analysis of AC and DC electrical power systems in nuclear power plants (NPPs) in order to demonstrate that the power sources and the distribution systems have the capability for safe operation and shut down of the NPP, bringing it to a controlled state after an anticipated operational occurrence or accident conditions and finally reaching a safe state. The analytical studies discussed in this document provide assurance that the design bases are satisfied to meet their functional requirements under the conditions produced by the applicable design basis events. The studies provide assurance that the electrical power system is capable of supporting safety functions during all required plant conditions. Analytical studies validate the robustness and adequacy of design margins and demonstrate the capability of electrical power systems to support plant operation for normal, abnormal, degraded and accident conditions. NOTE The safety functions are described in IAEA Specific Safety Requirements SSR-2/1 related to the design of the nuclear power plants.. The analyses are used to verify that the electrical power system can withstand minor disturbances and that the consequences of major disturbances or failures do not degrade the capability of the electrical power systems to support safe shutdown of the plant and maintain the plant in shutdown condition. The analyses are performed with one or more of ...

Nuclear power plants. Electrical power systems. Electrical power systems analysis

IEC 63186:2021 核电厂.对安全重要的仪表和控制系统.地震跳闸系统的标准

Nuclear power plants - Instrumentation and control systems important to safety - Criteria for seismic trip system

DS/EN ISO 16647:2021 核设施 核工地和退役核设施的封闭系统设计和运行标准（ISO 16647:2018）

Nuclear facilities – Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning (ISO 16647:2018)

CSA N292.8-2021 放射性废物和辐照燃料的表征

Characterization of radioactive waste and irradiated fuel

OVE EN IEC 62859:2021 核电站 仪表和控制系统 协调安全和网络安全的要求（（IEC 62859:2016）EN IEC 62859:2020）（德文版）

Nuclear power plants - Instrumentation and control systems - Requirements for coordinating safety and cybersecurity ((IEC 62859:2016) EN IEC 62859:2020) (german version)

DIN 25478:2021 计算机代码在临界安全评估中的应用

The document is to be applied for the application of computer codes for the handling of fissile material. It describes the structure of computer codes for the assessment of criticality safety.

Application of computer codes for the assessment of criticality safety

DIN 25471:2021 在轻水反应堆核电站燃料池中处理和储存核燃料元件时考虑燃料元件燃耗的临界安全

This document specifies requirements which guarantee an observation of criticality safety in handling and storage of nuclear fuel elements in fuel storage pools of nuclear power stations with lightwater reactors when during planning, setting up or during operation of correspondin

Criticality safety taking into account the burnup of fuel elements when handling and storing nuclear fuel elements in fuel pools of nuclear power plants with lightwater reactors

EN ISO 16647:2021 核设施.核工地和退役核设施限制系统的设计和操作标准

Nuclear facilities - Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning (ISO 16647:2018)