共找到 1815 条与 核电站、安全 相关的标准,共 121 页
Nuclear power plants. Instrumentation systems important to safety. In-core instrumentation: Characteristics and test methods of self-powered neutron detectors
本文件是T/CNEA 104《压水堆承压部件 设备设计制造》的第1部分。本文件共计7章,其中,1-3章为规范性条款,4-7章为压水堆承压部件 设备设计制造 第1部分:反应堆压力容器主要内容。主要内容包括:通用要求、材料、设计和制造、检验和验收。
PWR pressure boundary components—Equipments design and fabrication— Part 1:Reactor pressure vessel
本文件是T/CNEA 104《压水堆承压部件 设备设计制造》的第5部分。本文件共计7章,其中,1-3章为规范性条款,4-7章为压水堆承压部件 设备设计制造 第5部分:堆内构件主要内容。主要内容包括:总则、材料、设计和制造、检验和验收。
PWR pressure boundary components—Equipments design and fabrication— Part 5:Reactor internals
本文件是T/CNEA 104《压水堆承压部件 设备设计制造》的第4部分。本文件共计7章,其中,1-3章为规范性条款,4-7章为压水堆承压部件 设备设计制造 第4部分:控制棒驱动机构主要内容。主要内容包括:通用要求、材料、设计和制造、检验和验收。
PWR pressure boundary components—Equipments design and fabrication— Part 4:Control rod drive mechamism
Technical requirements for grounding and shielding of instrumentation and control equipment in pressurized water reactor nuclear power plants
Nuclear power plants - Instrumentation systems important to safety - In-core instrumentation: Characteristics and test methods of self-powered neutron detectors
本文件共计11章,其中,1-3章为规范性条款,4-11章为压水堆核电厂一回路冷却剂加锌指南主要内容。主要内容包括:总则、加锌影响评估、数据采集、加锌装置、锌化学品要求和安全防护、加锌执行、加锌注意事项和加锌效果评估等。
Guidelines for zinc addition in primary coolant of PWR
Nuclear facilities - Instrumentation important to safety - Spent fuel pool instrumentation
Nuclear facilities - Instrumentation important to safety - Spent fuel pool instrumentation
Nuclear power plants - Electrical power systems - Electrical power systems analysis (IEC 45A/1094/FDIS) (english version)
Nuclear power plants - Control rooms - Requirements for emergency response facilities (english version)
本标准规定了滨海核电站冷源取水区致灾物的监视、预报与处置等流程,提出了监视、预报与处置等阶段的工作方法。
Guide for Monitoring, forecasting and disposal of disaster-causing substance in cold source water intake areas of coastal nuclear power stations
Ice plug isolation of piping in nuclear power plant
核电抗震能力走访是核电厂抗震裕度评估(SMA)工和地震概率安全评估(SPSA)工作及现有核实施安全评估中最重要的组成部分之一。 为规范核电厂抗震裕度评估(SMA)及地震概率安全评估(SPSA)中的构筑物、系统和部件的抗震能力走访工作,本标准充分借鉴了美国通用实施程序(GIP)中给出的走访方法以及美国电力研究院(EPRI)发布的评定核电厂抗震裕度的方法,并结合国内多个核电厂的走访实践经验,制定本标准。
Seismic Capacity Walkdown Criteria for Nuclear Power Plant
This standard establishes requirements and provides guidance for the development and management of effective computer-based (CB) I&C systems security programmes at NPPs. Inherent to these requirements and guidance is the criterion that the power plant´s security programme complie
Nuclear power plants - Instrumentation, control and electrical power systems - Cybersecurity requirements (IEC 62645:2019); German version EN IEC 62645:2020
This preliminary standard applies to reinforced and prestressed concrete containment for nuclear power plants. This containment is the structural part of the confinement from the nuclear power plant. The safety function to be fulled by the confinement consists in ensuring that in
Reinforced and prestressed concrete containment for nuclear power plants
Nuclear power plants - Instrumentation and control systems important to safety - Development of HDL-programmed integrated circuits - Part 2: HDL-programmed integrated circuits for systems performing category B or C functions (IEC 62566-2:2020)
Nuclear facilities – Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning
Nuclear power plants. Instrumentation and control systems, control rooms and electrical power systems. Specific features of small modular reactors and needs regarding standards
Probabilistic Risk Assessment Standard for Advanced Non- Light Water Reactor Nuclear Power Plants
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