27.120.20 核电站、安全 标准查询与下载



共找到 1815 条与 核电站、安全 相关的标准,共 121

1   Scope This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control cables using insulation resistance measurements in the detail necessary to produce accurate and reproducible results during simulated accident conditions. It includes the requirements for the measurement system and measurement procedure, and the reporting of the measurement results. NOTE Measurement of insulation resistance during simulated accident conditions with the aim of determining the lowest value during the accident in order to assess cable performance involves special requirements given in this document. Methods for measurement under stable (non-accident) conditions are available in other international standards, e.g. IEC 62631‑3‑3. The different parts of the IEC/IEEE 62582 series 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 qualification of equipment important to safety is found in IEC/IEEE 60780-323.

Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods - Insulation resistance

ICS
27.120.20
CCS
发布
2021-07-31
实施
2021-07-31

Nuclear power plants - Electrical power system - General requirements (IEC 63046:2020)

ICS
27.120.20
CCS
发布
2021-07-30
实施
2021-07-30

Nuclear power plants – Electrical power systems – Electrical power systems analysis

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27.120.20
CCS
发布
2021-07-22
实施
2021-07-22

Nuclear power plants – Instrumentation and control important to safety – Electrical equipment condition monitoring methods – Part 6: Insulation resistance

ICS
27.120.20
CCS
发布
2021-07-22
实施
2021-07-22

Nuclear power plants – Instrumentation, control and electrical power systems important to safety – Categorization of functions and classification of systems

ICS
27.120.20
CCS
发布
2021-07-22
实施
2021-07-22

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

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27.120.20
CCS
发布
2021-07-22
实施
2021-07-22

IEC TR 63084:2017(E) provides an assessment framework and activities for efficient and transparent qualification of I&C platforms for use in nuclear applications important to safety, according to nuclear standards and state of the art. The assessment aims at a pre-qualification of I&C platforms outside the framework of a specific plant design. Qualification is assumed to be pre-requisite for allowing the particular I&C platform to be used for implementation of the safety classified I&C system. It is to enable parties implementing particular plant specific I&C systems to concentrate on application functions, while for basic system functions to rely on platform qualification. Basic means of equipment qualification, as prescribed by the IEC/IEEE 60780-323, are through analysis, type testing and documented operational experience. Other documents applicable for qualification for nuclear use include IEC 61513, IEC 60880, IEC 62138, IEC 62566, IEC 62671 and IEC 61226.

Nuclear power plants - Instrumentation and control important to safety - Platform qualification for systems important to safety

ICS
27.120.20
CCS
发布
2021-07-01
实施

ISO 21613:2015 describes a method for determining chlorine and fluorine in mixed (U,Pu)O2 powders and sintered pellets. It is applicable for the analysis of samples containing 5 µg.g−1 to 50 µg.g−1 of chlorine and 2 µg.g−1 to 50 µg.g−1of fluorine. For UO2 powder and sintered pellets, refer to ISO 22875.

(U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine

ICS
27.120.20
CCS
发布
2021-07-01
实施

IEC TR 63123:2017(E) gives guidance for the application in the IAEA / IEC framework of IEC 63147:2017/IEEE 497 corresponding to the adoption without modification of IEEE 497:2016.

Nuclear power plants - Instrumentation, control and electrical power systems - Guidance for the application of IEC 63147:2017/IEEE Std 497™ -2016 in the IAEA / IEC framework

ICS
27.120.20
CCS
发布
2021-07-01
实施

IEC 62954:2019 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). 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 synergies between the traditional operational means and emergency means.

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

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27.120.20
CCS
发布
2021-07-01
实施

IEC 62887:2018 lays down specific requirements for nuclear applications of pressure transmitters including design, materials, manufacturing, testing, calibration and inspection. This document is applicable to general aspects of design, manufacturing and test methods for pressure transmitters used in instrumentation systems important to safety in all nuclear power plants (PWR, BWR, FBR, etc.). The consequences of nuclear conditions for pressure transmitters lead to onerous requirements regarding qualification.

Nuclear power plants - Instrumentation systems important to safety - Pressure transmitters: Characteristics and test methods

ICS
27.120.20
CCS
发布
2021-07-01
实施

IEC 63147:2017(E) contains the functional and design criteria for accident monitoring instrumentation for new plant designs and nuclear power generating stations desiring to perform design modifications. The purpose of this standard is to establish selection, design, performance, qualification, and display criteria for accident monitoring instrumentation for anticipated operational occurrences, design basis events, and severe accidents. This standard applies to accident monitoring instrumentation intended for use during the following operations: - As required for planned operator action related to accident mitigation, - For assessing plant conditions, safety system performance, and making decisions related to plant response to abnormal events, - For achieving and maintaining safe shutdown following an accident This standard does not apply to the following: - Accident monitoring instrumentation that is intended solely for historical recording or solely for maintenance purposes - Other instrumentation that may be available during accident conditions. This standard is an adoption of IEEE 497-2016 by IEC. When applied in an IAEA / IEC environment this standard is to be used in conjunction with IEC TR 63123.

Criteria for accident monitoring instrumentation for nuclear power generating stations

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27.120.20
CCS
发布
2021-07-01
实施

IEC 62855:2016 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. This standard is intended to be used: - for verification of the design of new nuclear power plants; - for demonstrating the adequacy and impact of major modifications of electrical power systems in operating nuclear power plants; - and where there is a requirement to assess and establish operating limits and constraints for existing plants.

Nuclear power plants - Electrical power systems - Electrical power systems analysis

ICS
27.120.20
CCS
发布
2021-07-01
实施

IEC 62988:2018 establishes requirements relevant to the selection and use of wireless devices in instrumentation and control (I&C) systems important to safety used in nuclear power plants (NPPs). Those I&C systems may fully consist of wireless devices. This document applies to the I&C of new NPPs and to backfit of I&C in existing NPPs. Every wireless device or wireless system that is important to safety is in the scope of this document. Both fixed and mobile devices and all data types (voice, process data, etc.) are included within the scope if they provide a safety classified function. This document restricts the use of wireless devices to systems supporting category C functions according to IEC 61226, excluding explicitly their use for categories A and B. Non-safety devices and systems may use this document as guidelines, for example to ensure that important to safety devices are not disturbed.

Nuclear power plants - Instrumentation and control systems important to safety - Selection and use of wireless devices

ICS
27.120.20
CCS
发布
2021-07-01
实施

IEC 62859:2016 provides a framework to manage the interactions between safety and cybersecurity for nuclear power plant (NPP) systems, taking into account current IEC standards addressing these issues and the specifics of nuclear I&C programmable digital systems. This standard establishes requirements and guidance to: - integrate cybersecurity provisions in nuclear I&C architectures and systems, which are fundamentally tailored for safety; - avoid potential conflicts between safety and cybersecurity provisions; - aid the identification and the leveraging of the potential synergies between safety and cybersecurity.

Nuclear power plants - Instrumentation and control systems - Requirements for coordinating safety and cybersecurity

ICS
27.120.20
CCS
发布
2021-07-01
实施

This standard specifically focuses on the issue of requirements for coordinating safety and cybersecurity provisions for I&C programmable digital systems and architectures. It defines both generic principles and guidance for practical situations to integrate cybersecurity require

Nuclear power plants - Instrumentation and control systems - Requirements for coordinating safety and cybersecurity (IEC 62859:2016 + A1:2019); German version EN IEC 62859:2020

ICS
27.120.20
CCS
发布
2021-07-00
实施
2021-07-01

Nuclear facilities - Equipment important to safety - Seismic qualification (IEC/IEEE 60980-344:2020)

ICS
27.120.20
CCS
发布
2021-06-30
实施
2021-06-30

Nuclear power plants--Instrumentation and control systems--Requirements for coordinating safety and cybersecurity (IEC 62859:2016+A1:2019)

ICS
27.120.20
CCS
发布
2021-06-14
实施
2021-06-14

Nuclear energy - Accelerators used in industrial and research fields: installations

ICS
27.120.20
CCS
发布
2021-06-12
实施
2021-06-12

本文件是T/CNEA 102《压水堆承压部件 焊接》的第4部分。本文件共计11章,其中,1-3章为规范性条款,4-11章为压水堆承压部件 焊接 第4部分:产品焊接主要内容。主要内容包括:通用要求、焊接材料、焊接评定、焊接准备、焊接、热处理、检验和产品焊接见证件。

PWR pressure boundary components—Welding— Part4:Production welds

ICS
27.120.20
CCS
D441
发布
2021-06-04
实施
2022-03-15



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