F69 核反应堆与核电厂核岛设备 标准查询与下载
共找到 1177 条与 核反应堆与核电厂核岛设备 相关的标准，共 79 页
"Object This International Standard establishes requirements for the whole life cycle of operating procedures that the designer wishes to computerise. It also provides guidance for making decisions about which types of procedures are to be computerised and to what extent. Once computerised@ procedures are designated as ""Computer Based Procedures"" (CBP). Enhancing safety@ easing operation and increasing NPP availability have always been greatly valued aims which@ during NPP operation@ rely to a large extent on the operating staff and on operating procedures. Digital technology is currently contributing by providing efficient help to do this at the automation level. In addition@ the use of computer technology to provide formats of operating procedures to the plant operators1@ on-line and in real time@ is increasing and becoming current practice. This can be done both for normal operating situations and also as advisory formats for use in abnormal situations. When properly implemented and kept up-to-date@ such operating procedures can provide enhanced support for greater safety and operator effectiveness compared to paper based procedures. Their preparation demands great care and close interaction with operators and plant designers@ and will also need close co-operation with IC designers. CBP have many common points with paper based procedures. This standard focuses only on what is specific to CBP."
Nuclear power plants - Control rooms - Computer based procedures
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-09
- 实施
- 2016-10-07
Interpretations to OM CODE Code for Operation and Maintenance of Nuclear Power Plants (Includes Interpretations Dated September 1, 1995 thru April 18, 2012)
- ICS
- CCS
- F69
- 发布
- 2012-04-18
- 实施
Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. Indenter modulus
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-31
- 实施
- 2012-01-31
Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. Oxidation induction techniques
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-31
- 实施
- 2012-01-31
Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. General
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-31
- 实施
- 2012-01-31
本标准规定了安全壳人员闸门的设计、试验等方面的技术要求，适用于国内压水堆核电厂安全壳人员气闸门的设计，并可供设计其他堆型安全壳人员气闸门参考。
Design requirements of personnel airlock for containment in pressurized water reactor nuclear power plants
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂安全壳氢气控制系统的主要功能，系统范围和主要设备，设计准则等，以确保该系统能够安全可靠地执行其预定的功能。 本标准适用于压水堆核电厂安全壳氢气控制系统的设计，不包括对该系统设备的具体设计要求，亦不包括该系统的运行、维修和试验要求，除非与系统设计直接有关。
Design criteria for containment hydrogen control system of pressurized water reactor nuclear power plants
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂安全壳通风系统及设备的设计准则和基本要求，以及实体布置设计要求。 本标准适用于压水堆核电厂为一次安全壳结构内服务的、由设备、风管及控制装置组成的、依赖能动部件实现用于排热、供暖、空气净化及全面通风的通风系统。 本标准不适用于安全壳环形空间通风系统、安全壳过滤排放系统、安全壳氢气控制系统、安全壳内换料通道吹吸通风系统、不采用空气冷却的控制棒驱动机构冷却系统、冰冷凝器隔间环境控制系统。
Containment ventilation system of pressurized water reactor nuclear power plant
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂安全壳外影响安全功能的HVAC系统及设备的设计准则和基本要求，而且包含了实体布置设计要求。 本标准适用于压水堆核电厂为安全壳外服务的、由设备、风道及控制装置组成的、依赖能动部件实现供暖、冷却、通风、烟气和热量控制、释放控制的HVAC系统。 本标准不适用于反应堆厂房安全壳环形空间通风系统。
Design criteria for HVAC systems located outside containment of PWR nuclear power plant
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了对压水堆核电厂混凝土安全壳及相关系统设计的基本要求，包括安全壳的设计基准、功能设计要求、严重亊故设计考虑及试验和检查要求等。 本标准适用于各类压水堆核电厂混凝土安全壳功能的设计。
Concrete containment functional design requirements for PWR nuclear power plant
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了核电厂安全级阀门驱动装置及驱动装置部件的鉴定程序及鉴定方法，以证明其达到了预定的安全功能。 本标准适用于核电厂安全级阀门驱动装置及驱动装置部件的鉴定。
Qualification of safety-related valve actuators for nuclear power plants
- ICS
- 120.27.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂安全级柴油发电机组中发电机的鉴定过程、方法和验收准则的基本要求。 本标准适用于内燃机拖动，额定电压为（6～10.5) kV的无刷式自励三相同步发电机，不适用于对发电机励磁调节控制部分、拖动发电机的内燃机部分的鉴定。
Qualification procedure for safety-class diesel-generator applied as standby power supplies for nuclear power plants
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂安全级余热排出泵电机的鉴定过程、方法和验收准则的基本要求。 本标准适用于安装在压水堆核电厂安全壳内，在正常运行工况下、事故工况下和（或）事故工况后以及在地震载荷下能够执行其安全功能的余热排出泵电机。该电机为额定电压（6～10)kV级的鼠笼型三相异步电动机。 本标准不适用于对电机需定期更换部件及润滑油脂的鉴定。
Qualification procedure for safety class residual heat removal motor applied in nuclear power plants
- ICS
- 27.120.69
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂反应堆系统设计中堆芯燃料组件的设计准则。 本部分适用于镐合金作包装管、UO芯块和（或）UO-GdO芯块或涂ZrB的UO芯块作燃料的压水堆核电厂燃料组件的设计，采用其他包壳和燃料材料的燃料组件设计亦可参考执行。
PWR nuclear power plants reactor system design.Core.Part3:Fuel assembly
- ICS
- 27.120.30
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本部分规定了压水堆核电厂反应堆系统设计中堆芯燃料相关组件的设计准则。 本部分适用于压水堆核电厂束棒型燃料相关组件的设计，其他类型反应堆燃料相关组件的设计可参照执行。
PWR nuclear power plants reactor system design.Core.Part4:Core components
- ICS
- 27.120.30
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了核电厂安全级气动调节阀鉴定所采用的通用试验项目、试验条件、试验方法和验收准则。对特定功能的阀门，可根据技术规格书要求进行补充试验。调节阀使用的附件，如电磁阀、定位器等需要按相应标准进行并通过鉴定，不在本标准规定的范围内。 本标准适用于安装在压水堆核电厂内，经受了正常工况、异常工况和核电厂设计基准事件后，要求保持性能的调节阀。 本标准也可供其他类型核电厂的调节阀鉴定时参考使用。
Qualification procedure for safety-related pneumatic control valve of pressurized water reactor nuclear power plants
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
本标准规定了压水堆核电厂反应堆堆芯仪表系统安装、检查与试验要求，主要包括堆芯仪表系统安装计划、安装与试验相关文件准备、安装与试验人员资格、安装前检查、安装过程检查及安装后的试验要求等，确保反应堆堆芯仪表系统安装与试验满足系统规定的功能和性能要求。 本标准适用于压水堆核电站堆芯仪表系统设备的安装和试验。 对于设备安装期间的下述方面的活动本标准不提出特定要求： a）焊接部件的焊接、无损检查、理化试验； b)仪表管线的吹扫； c）转动设备的对中和调整； d)设备支撑结构完整性验证； e)设备投入运行后的定期试验和维护； f)设备制造完工后的接收检查和试验。
Installation and test requirement of in-core instrumentation system in pressured water reator nuclear power plant
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-06
- 实施
- 2012-04-06
The Roadmap has been developed as a guide to the R&D and Code development tasks that could be considered in developing rules for High Temperature Gas Cooled Reactors (HTGR). The primary focus of the Roadmap is on the development of a complete set of rules for the design and operating conditions that are being proposed for the Next Generation Nuclear Plant (NGNP) demonstration unit.
Roadmap to Develop ASME Code Rules for the Construction of High Temperature Gas Cooled Reactors (HTGRS) (STP-NU-045-1 - 2012)
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01-01
- 实施
Code Cases to OM CODE Code for Operation and Maintenance of Nuclear Power Plants
- ICS
- CCS
- F69
- 发布
- 2012-01-01
- 实施
Nuclear power plants - Instrumentation and control important to safety - Development of HDL-programmed integrated circuits for systems performing category A functions
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-01
- 实施
