核电厂.主控制室设计.IEC 60964-1989的应用回顾 -
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
- NF M60-805-2-2003 - 中外标准 - NFBASE- 2003/1 - 现行
- NF M60-805-1-2003 - 中外标准 - NFBASE- 2003/1 - 现行
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
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
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.
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
126.96.36.199 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
188.8.131.52 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.
184.108.40.206 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.
220.127.116.11 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.
18.104.22.168 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
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
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)
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
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