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
本标准规定了空间热离于反应堆核动力装置的热工流体力学的设计基本耍求和设计准则，提山了 反应堆′…_二流体力学设计参数限值的确定原则。 本标准适月于仝间热离予反应堆核动力装苴热 〔流体力学设计。
Thermal Fluid Dynamics Design Criteria for Space Thermionic Reactor Nuclear Power Plant
- ICS
- CCS
- F69
- 发布
- 2013-05-01
- 实施
- 2013-05-01
This International Standard describes the requirements for thermocouples suitable for nuclear power plant (NPP) applications. Thermocouples are widely used in NPPs with other temperature measurement devices such as Resistance Temperature Detectors (RTDs). They are simple and robust and have some specific characteristics (range of measurement and maximum temperature) which make them uniquely suitable for some measurements. The requirements given in this standard for thermocouples include design, materials, manufacturing, testing, calibration, procurement, and inspection. The scope of this standard does not cover the design, material selection, and construction of the thermowell, the guide tube, the extension cable, and the temperature transmitter or bridge which may be associated with the thermocouple.
Nuclear power plants - Instrumentation important to safety - Thermocouples: Characteristics and test methods
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013-04
- 实施
- 2013-05-01
Ventilating components in nuclear facilities
- ICS
- 27.120.20;91.140.30
- CCS
- F69
- 发布
- 2013-04
- 实施
Design and Construction Code for mechanical equipments of innovative nuclear installations; English version CWA 16519:2012
- ICS
- 27.120.01
- CCS
- F69
- 发布
- 2013-04
- 实施
Nuclear power plants. Control rooms. Application of visual display units (VDUs)
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013-03-31
- 实施
- 2013-03-31
Nuclear power plants. Instrumentation and control important to safety. Electrical equipment condition monitoring methods. Elongation at break
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013-01-31
- 实施
- 2013-01-31
Rules for Inservice Inspection of Nuclear Power Plant Components
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013-01-01
- 实施
Rules for Construction of Nuclear Facility Components
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013-01-01
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Appendices
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013
- 实施
IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 2: Code for Concrete Containments
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 5: High Temperature Reactors
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection ND - Class 3 Components
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013
- 实施
Reliability, Availability, and Maintainability of Equipment and Systems in Power Plants
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
Comprehensive Evaluation of the NSQ-100 Nuclear Safety and Quality Management System Requirements
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
Comprehensive Comparison of International Quality Standards
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
ASME Code Development Roadmap for HDPE Pipe in Nuclear Service
- ICS
- 23.100.40;27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
ASME Boiler & Pressure Vessel Code - Section 3: Rules for Construction of Nuclear Facility Components - Division 1: Subsection NB - Class 1 Components
- ICS
- 27.120.10
- CCS
- F69
- 发布
- 2013
- 实施
Standard for Level 1 / Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications; Addenda
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2013
- 实施
Nuclear power plants. Control rooms. Computer based procedures
- ICS
- 27.120.20
- CCS
- F69
- 发布
- 2012-12-31
- 实施
- 2012-12-31
