F82 堆用核仪器 标准查询与下载

EJ/T 626-1992 核电厂电气、仪表和控制设备的安装、检查和试验要求

本标准规定了核电厂施工期间对电气、仪表和控制设备及系统的安装、检查和试验的要求。 本标准适用于核电厂电气、仪表和控制设备，也适用于核电厂的改进和运行期间的工作，但它们在性质和程序上要与施工期间的工作相当。 本标准也适用于其他核设施，包括研究堆、乏燃料贮存、废料贮存、燃料加工、钚处理和燃料装配等设施。

Requirements for installation, inspection and testing of nuclear power plant electrical, instrumentation and control equipment

EJ/T 649-1992 核电厂电线系统设计及安装准则

本标准规定了核电厂导线和电缆系统的设计及安装准则。 本标准适用于核电厂也适用于非核电厂。对于核电厂安全级电路系统的导线和电缆系统的设计及安装在EJ 534中规定。

Design and installation guidelines for nuclear power plant wiring system

EJ/T 638-1992 核电厂控制室综合体的设计准则

本标准规定了核电厂控制室综合体的设计准则。 本标准适用于核电厂控制室综合体的设计，使控制室设计者正确执行GB/T 13630中规定的有关要求，保证控制室的设计满足核安全法规HAF 0200《核电厂设计安全规定》中的要求。 本标准不适用于特设的或通常无人监视的控制室，例如，为放射性废物处理或应急停堆控制而设置的控制室。

Design criteria for control room complexes in nuclear power plants

EJ/T 637-1992 核电厂安全有关通信系统

Nuclear power plant safety-related communication system

EJ/T 632-1992 反应性仪特性和测试方法

Reactivity instrument characteristics and test methods

EJ/T 534-1991 核电厂安全级电路电缆系统的设计和安装

本标准规定了核电厂安全级电路电缆系统的设计和安装要求。 本标准适用于核电厂安全级电路电缆系统的设计和安装，也适用于可能影响安全系统功能的相关电路或其他非安全级电路电缆系统的设计和安装。

Design and installation of safety level circuit and cable system in nuclear power plant

EJ/T 597-1991 磁浮子液位计

Magnetic float level gauge

EJ/T 609-1991 核电厂保护系统电气插件型式检验准则

Criterion for type inspection of electrical plug-in for nuclear power plant protection system

EJ/T 571-1991 核电厂保卫系统电气设备准则

Guidelines for electrical equipment of nuclear power plant protection system

EJ/T 574-1991 核电厂安全级控制仪表盘（屏）和机架的设计与鉴定

Design and appraisal of safety level control instrument panels (screens) and racks of nuclear power plants

EJ/T 572-1991 核电厂安全系统设备设计鉴定

本标准规定了核电厂安全系统设备设计鉴定的基本原则。 本标准适用于核电厂安全系统设备的设计鉴定。 本标准不适用于设备安装与设备验收后进行的常规产品试验及预运行试验。

Nuclear power plant safety system equipment design appraisal

EJ/T 529-1990 用于核电厂安全重要系统数字计算机

本标准规定了对数字计算机系统硬件的特殊要求（包括对冗余、独立性和结构等方面要求）、至于对计算机软件的具求以及对硬件和软件共同领域内的要求则可按照GB 12172《核电厂安全系统计算机软件》及GB 12727《核电厂安全系统电气物项质量鉴定》中规定的要求，特别是后者第4.2条通用于核电厂安全重要系统可编程数字计算机。 本标准适用于核电厂安全重要系统中的计算机系统。

Digital computer for systems important to safety in nuclear power plants

IEEE 498-1990 核装置用测量与试验设备的校准和控制要求

Requirements for the calibration and control of measuring and test equipment used in nuclear facilities

EJ/T 313-1988 压水堆核电厂系统部件安全等级的划分

Classification of Safety Levels of System Components in PWR Nuclear Power Plants

IEC 60552:1977/AMD1:1984 计算机辅助测量与控制 多机箱系统组织 分支总线和A1型计算机辅助测量与控制机箱控制器规范 修改1

In sub-clause 4.2.3, Command accepted (BX), item b) is deleted and the following aub-clauses are added: 4.2.4 Response "command accepted" BX to a graded-L request BG and 4.2.5 Command accepted X or BX disabling (additional information). Sub-clauses 4.6.1

CAMAC - Organization of multi-crate systems. Specifications of the Branch-highway and CAMAC crate controller Type A1

BS 5552:1978 动力反应堆中子注量率(通量)测量用堆芯测量仪的实用规程

Applies to in-core (on-line) neutron detectors and instrumentation designed for safety, information or control purposes , the major emphasis being on the general design aspect of on-line systems

Code of practice for in-core instrumentation for neutron fluence rate (flux) measurements in power reactors

IEC 60552:1977 计算机辅助测量与控制 多机箱系统组织 分支总线和A1型计算机辅助测量与控制机箱控制器规范

This standard defines the signals, timing and logical organization of the connections from crate controllers and branch drivers to the branch-highway through a defined 132-way connector. Appendix A defines those features of a crate controller that affect

CAMAC - Organization of multi-crate systems. Specifications of the Branch-highway and CAMAC crate controller Type A1

IEC 60568:1977 动力反应堆内中子注量率(通量)测量用堆芯仪表

Incore instrumentation for the measurement of fluence in power reactors

IEC 60231G:1977 核反应堆仪表一般原则 补充7:液态金属冷却快中子反应堆

The purpose of this supplement is to lay down standard requirements pertaining to the general principles of instrumentation of liquid-metal cooled fast reactors, in addition to those given in the IEC Publications 231 and 231A. This supplement applies onl

General principles of nuclear reactor instrumentation. Seventh supplement: Liquid-metal cooled fast reactor

IEC 60231F:1977 核反应堆仪表一般原则 补充6:蒸汽生成、直接循环、重水慢反应堆

The purpose of this supplement is to lay down standard requirements pertaining to steam generating heavy-water moderated reactors which operate in the direct cycle mode. These requirements are in additon to those given in the IEC Publications 231 and 231

General principles of nuclear reactor instrumentation. Sixth supplement: Heavy-water-moderated reactor with steam generating direct-cycle turbine