电力工业标准-电力网-万方数据知识服务平台

1 核电厂.主控制室设计.IEC 60964-1989的应用回顾 - 摘要

Is a technical report presenting information concerning the use of IEC 60964 and feedback from designers, safety authorities and vendors. Includes recommendations to improve IEC 60964 (1989). To be used in conjunction with IEC 60964 which is the main IEC
IEC/TR 62247-2003 - 中外标准 - IEC- 2003/1 - 现行
关键词：电气工程安全反应堆装置检验控制间核电厂核电站核反应堆 checks nuclear power plants electrical engineering control rooms reactor instrumentation safety nuclear-electric power stations nuclear reactors Elektrotechnik Kernkraftwerk Kernreaktor Kontrolle Reaktorinstrumentierung Sicherheit Warte

2 核能.环境中放射性的测量.水.第2部分:感应耦合等离子体原子发射光谱法测量水中铀的浓度 - 摘要
NF M60-805-2-2003 - 中外标准 - NFBASE- 2003/1 - 现行

3 核能.环境中放射性的测量.水.第1部分:荧光测定法测量水中铀的浓度 - 摘要
NF M60-805-1-2003 - 中外标准 - NFBASE- 2003/1 - 现行

4 核电站1E级设备的考核 - 摘要

Describes the basic requirements for qualifying Class 1E equipment and interfaces that are to be used in nuclear power generating stations. The principles, methods and procedures described are intended to be used for qualifying equipment, maintaining and extending qualification, and updating qualification, as required, if the equipment is modified.
IEEE 323-2003 - 中外标准 - IEEE- 2003/1 - 现行
关键词：界面设备电气工程安全工程合格定义核反应堆核电站仪器装置安全规则 Definition Definitions Electrical engineering Equipment Instrumentation Interfaces Nuclear reactors Nuclear-electric power stations Qualifications Safety engineering Safety regulations

5 核电厂.有关安全的仪器仪表.事故保护定值器的测定和维护 - 摘要

Defines the requirements for assuring that automatic setpoints for nuclear safety system instrumentation are established and maintained within specified limits in nuclear power plants and nuclear reactor facilities.
BS IEC 61888-2003 - 中外标准 - BSBASE- 2003/1 - 现行
关键词：核反应堆反应堆安全核电厂核电站定义电气工程反应堆装置反应釜安全安全工程 Definition Definitions Electrical engineering Nuclear power plants Nuclear reactors Nuclear-electric power stations Reactor instrumentation Reactor safety Reactor vessels Safety Safety engineering

6 热室用物料搬运设备的标准指南 - 摘要

1.1 Intent:
1.1.1 This guide covers materials handling equipment used in hot cells (shielded cells) for the processing and handling of nuclear and radioactive materials. The intent of this guide is to aid in the selection and design of materials handling equipment for hot cells in order to minimize equipment failures and maximize the equipment utility.
1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, installation, maintenance, repair, replacement, and decontamination and decommissioning of materials handling equipment capable of meeting the stringent demands of operating, dependably and safely, in a hot cell environment where operator visibility is limited due to the radiation exposure hazards.
1.1.3 This guide may apply to materials handling equipment in other radioactive remotely operated facilities such as suited entry repair areas and canyons, but does not apply to materials handling equipment used in commercial power reactors.
1.1.4 This guide covers mechanical master-slave manipulators and electro-mechanical manipulators, but does not cover electro-hydraulic manipulators.
1.2 Applicability:
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, e.g., without shielded viewing windows, periscopes, or a video monitoring system.
1.3 User Caveats:
1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance.
1.3.1.1 The guidance set forth in this standard relating to design of equipment is intended only to alert designers and engineers to those features, conditions, and procedures that have been found necessary or highly desirable to the design, selection, operation and maintenance of reliable materials handling equipment for the subject service conditions.
1.3.1.2 The guidance set forth results from discoveries of conditions, practices, features, or lack of features that were found to be sources of operational or maintenance problems, or causes of failure.
1.3.2 This standard does not supersede federal and/or state regulations, or codes applicable to equipment under any conditions.
1.3.3 This standard does not cover design features of the hot cell, e.g., windows, drains, and shield plugs. This standard does not cover pneumatic or hydraulic systems. Refer to Guides C 1533, C 1217, and ANS Design Guides for Radioactive Material Handling Facilities Equipment for information and references to design features of the hot cell and other hot cell equipment.
1.3.4 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 and health practices, and determine the applicability of regulatory limitations prior to use.
ASTM C1554-2003 - 中外标准 - ASTM- 2003/1 - 现行
关键词：物料搬运设备装卸设备热室物料装卸 crane design equipment hot cells manipulator materials handling nuclear materials remote handling

7 核电站用1E级电缆质量鉴定和现场拼接 - 摘要

Provides general requirements, direction and methods for qualifying Class 1E electric cables, field splices, factory splices and factory rework for service in nuclear power generating stations
IEEE 383-2003 - 中外标准 - IEEE- 2003/1 - 废止
关键词：电缆连接件试验合格试验电气工程电缆定义发电站安全规则核电站反应堆安全 Cable junctions Definition Definitions Electric cables Electrical engineering Nuclear-electric power stations Power generating installation Qualification tests Reactor safety Safety regulations Testing

8 涂料.核设施涂层.第3部分:涂覆作业、计划和程序 - 摘要

The document lays down general principles for planning and procedure of coating work for nuclear facilities, with the aim to ensure the correct processing of coating materials tested according to DIN 55991-1 and fulfilling the requirements given in DIN 55991-1. The document applies to coating work for mineral surfaces bound with cement and for metallic surfaces for the control area of nuclear facilities.#,,#
DIN 55991-3-2003 - 中外标准 - DINBASE- 2003/1 - 废止
关键词：覆层材料质量保证监督(认可) 覆层核技术核装置计划人员材料试验可控区材料合格试验设计涂料 design controlled area coatings nuclear technology materials materials testing coating materials planning nuclear installations personnel quality assurance qualifications paints testing surveillance (approval)

9 附录K.低上平台夏比冲击能级反应堆容器的评估 - 摘要

Boiler and Pressure Vessels.Appendix K Assessment of Reactor Vessels with Low Upper Shelf Charpy Impact Energy Levels
ASME SEC XI D1 NMA APP K-2003 - 中外标准 - ASME- 2003/1 - 废止

10 附录H.基于故障评估表对管路中的缺陷进行评估的程序 - 摘要

Boiler and Pressure Vessels.Appendix H Evaluation Procedures for Flaws in Piping Based on Use of a Failure Assessment Diagram
ASME SEC XI D1 NMA APP H-2003 - 中外标准 - ASME- 2003/1 - 废止

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