27.120.20 核电站、安全 标准查询与下载

ASME ANS RA-S-1.4-2021 非轻水堆核电站概率风险评估标准

Probabilistic Risk Assessment Standard for Advanced Non- Light Water Reactor Nuclear Power Plants

IEC TR 63335:2021 核电厂.仪表和控制系统 控制室和电力系统.小型模块化反应堆的特殊特性和标准要求

Nuclear power plants - Instrumentation and control systems, control rooms and electrical power systems - Specific features of small modular reactors and needs regarding standards

ASTM E1892-15(2021) 准备退役核设施特征化计划的标准指南

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 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. 1.3 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 Preparing Characterization Plans for Decommissioning Nuclear Facilities

IEC 60987:2021 核电站. 仪表和控制的重要安全性. 硬件要求

I&C systems important to safety may be implemented using conventional hardwired equipment, programmable digital equipment or by using a combination of both types of equipment. This document provides requirements and recommendations for the hardware aspects of I&C systems whatever

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

OVE EN IEC 63046:2021 核电站 电力系统 一般要求（英文版）

Nuclear power plants - Electrical power system - General requirements (english version)

ASTM D5163-16(2021) 核电厂涂装服务一级涂装系统条件评估方案标准指南

1.1 This standard covers procedures for establishing a monitoring program for condition assessment of Coating Service Level (CSL) I coating systems in operating nuclear power plants. Monitoring is an ongoing process of evaluating the condition and performance of the in-service coating systems. 1.2 It is the intent of this standard to provide a recommended basis for establishing a coatings condition assessment program, not to mandate a singular basis for all programs. Variations or simplifications of the program described in this standard may be appropriate for each operating nuclear power plant depending on their licensing commitments. 1.3 This requirements of ASME Section XI, In-Service Inspection Subsections IWE and IWL are beyond the scope of this standard. 1.4 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. 1.5 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 Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants

ASTM E1281-15(2021) 核设施退役计划标准指南

1.1 This guide applies to decommissioning plans for any nuclear facility whose operation was (is) governed by Nuclear Regulatory Commission (NRC), Agreement State license, under Department of Energy (DOE) orders, or whose operation was overseen by another federal, state, or local agency. 1.2 The guide applies to the preparation and content of the decommissioning plan document itself. 1.3 The detailed description and development of implementation plans identified in Section 4 is outside the scope of this guide. NOTE 1—Nuclear facilities operated by the U.S. DOE are not licensed by the U.S. NRC, nor are other nuclear facilities which may come under the control of the U.S. Department of Defense or individual agreement states. The references in this guide to licensee, U.S. NRC Regulatory guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD, or agreement state nuclear facilities. This distinction should not alter the content of decommissioning plans for nuclear facilities. 1.4 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. 1.5 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 Nuclear Facility Decommissioning Plans

NB 10597-2021 核电厂海工构筑物混凝土结构防腐蚀技术规范

Technical specifications for anti-corrosion of concrete structures in offshore structures of nuclear power plants

CSA N290.7-2021 核设施的网络安全

Cyber security for nuclear facilities

GOST R 59390-2021 核电厂工艺过程的自动控制系统 术语和定义

Automated control systems of technological processes for nuclear power plants. Terms and definitions

GOST R IEC 61839-2021 核电站的控制室 设计时的功能分析与分配

Control rooms of nuclear power plants. Functional analysis and assignment when designing

GOST R IEC 61225-2021 核电站 仪表与控制安全性重要事项 电源规格

Nuclear power plants. Instrumentation, control and electrical power systems. Requirements for static uninterruptible DC and AC power supply systems

GOST R IEC 61888-2021 核电站的跳闸设定点 规定条件下的选型与维护

Trip setpoints for nuclear power plants. Selection and maintenance under specified conditions

GOST R 59410-2021 核电站控制和安全系统的电气设备和驱动装置的综合体 实际采出量的核算及剩余资源量的估计

Complex of electrical equipment and drives of control and safety systems of nuclear power plants. Accounting for actually worked out and estimation of residual resource

GOST R IEC 62241-2021 核电站主控室信号系统 功能要求

Signaling systems for main control room of nuclear power plants. Functional requirements

T/CNS 23-2020 高温气冷堆核动力厂工况分类

本文件规定了球床模块式高温气冷堆（以下简称高温气冷堆）核动力厂运行及事故工况的分类方法。

Categorization of plant states of high temperature gas cooled reactor nuclear power plant

T/CERS 0010-2020 核电厂金属废物部件激光去污规范

本文件规定了核电厂金属废物部件激光去污实施的技术要求、去污设施、去污实施要求、去污效果评估、安全要求等方面的技术要求。 本文件适用于核电厂金属废物部件激光去污实施工作。其它行业的激光去污实施亦可参照本标准执行。

Specification for laser decontamination of metal waste components in nuclear power plants

BS EN IEC 62566-2:2020 核电厂 对安全很重要的仪表和控制系统 HDL 编程集成电路的开发 用于执行 B 类或 C 类功能的系统的 HDL 编程集成电路

1   Scope This part of IEC 62566 provides requirements for achieving highly reliable HDL -Programmed Devices ( HPDs ), for use in I&C systems of nuclear power plants performing functions of safety category B or C as defined by IEC 61226. The programming of HPDs relies on Hardware Description Languages ( HDL ) and related software tools. They are typically based on blank Field Programmable Gate Arrays ( FPGAs ) or similar micro-electronic technologies such as Programmable Logic Devices ( PLD ), Complex Programmable Logic Devices (CPLDs), etc. General purpose integrated circuits such as microprocessors are not HPDs . Annex B.8 provides descriptions of a number of different types of integrated circuits. This document provides requirements on: a) a dedicated HPD life-cycle addressing each phase of the development of HPDs , including specification of requirements, design, implementation, integration and validation, as well as verification activities associated with each phase, b) planning and complementary activities such as modification and production, c...

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

T/CERS 0009-2020 核电厂冷源安全分级预警规范 水母灾害

本文件规定了针对沿海核电企业冷源安全的水母灾害预警等级和阈值。 本文件适用于我国沿海核电企业水母灾害应急管理工作中的水母灾害预警等级划分。

Specification for classified early warning of cold source safety in nuclear power plants—Jellyfish disasters

T/CNEA 005-2020 核电工程项目后评价导则

本标准共计14章，其中，1-4章为规范性条款，5-12章为针对核电工程项目的主要评价内容，13-14章为结论和建议。主要评价内容包括：项目前期准备阶段的决策程序和过程、工程勘察、初步设计；项目建设实施阶段的开工条件、施工图设计、组织管理、采购和合同管理、工程监理、四大控制、调试；项目生产运营阶段的生产准备、验收、生产运营管理和指标、运行、维修、设备管理；针对核安全与环境、投资分析与财务、信息文档管理、社会效益、可持续性的专项评价。

Guidelines of post-evaluation for nuclear power plant project