反应堆控制系统

反应堆控制系统在线试验台在预防性维修中的应用

Application of On-line Tester in Preventive Maintenance of Reactor Control System

核电站仿真技术在反应堆控制系统调试中的应用

Implementation of Nuclear Power Plant Simulation in Start-up Commissioning of Reactor Control System

研究了HTR－10堆芯的动态仿真，为反应堆控制系统的分析和设计服务。

The dynamic simulation of HTR 10 core is studied .

深圳大学中子源核反应堆控制系统

Control System of Miniature Neutron Source Nuclear Reactor in Shenzhen University

反应堆控制系统可靠性动态分析

Dynamic Analysis for Reactor Control System Reliability

数字化反应堆控制系统研究

Research on Digital Control System Reactor

岭澳二期反应堆控制系统数字化技术应用及其工程适应性研究

Application of Digital Technology and Its Engineering Adaptation in Reactor Control System in Ling ' Ao Phase II NPP

它的建成为我国自主设计建造大型商用核电站反应堆控制系统积累了宝贵的工程经验。

It provides valuable experiences for the indigenous design and manufacture of the reactor control system for large commercial NPPs .

对导致反应堆控制系统故障的事故序列进行了识别，计算了该系统顶事件的概率。

The event sequences leading to the reactor control system failure are identified and the top event probability of this system is calculated .

在先进压水堆预研项目中，中国核动力研究设计院研制出了数字化反应堆控制系统原理样机。该产品样机研成后经运行试验表明设计是成功的。

The Prototype Digital Control System for Advanced Reactor is produced by NPIC . A performance test of the advanced development shows the design is successful .

仿真计算结果表明，模型的假设合理，并为反应堆控制系统设计的验证提供了有效的输入数据。

The simulation results show that the assumptions of model are reasonable . This dynamic model can provide valid input data for the design verification of the reactor control .

为提高大亚湾核电站反应堆控制系统预防性维修水平，在线试验台被设计用来对控制通道进行测试。

In order to improve the level of preventive maintenance in Daya Bay Nuclear Power Station , the On-line Tester is designed to test the channels of reactor control system .

研究了基于解析冗余的容错控制&控制率重构方法，分析了控制系统中传感器出现故障时其输出信息重构的问题，并针对核反应堆控制系统进行了仿真试验。

Control strategy reconstruction , a method of fault tolerant control based on the analytical redundancy is studied . This paper analyzes the problem of reconstruction of a failure sensor ′ s output in the control system .

半实物仿真系统是一个半实物的反应堆闭环控制系统。

Modeling and simulat-ing system is a simulated close-loop control system .

反应堆功率控制系统的建模及闭环验证闭式循环系统闭路制

Modeling of Reactor Power Control System and Closed Loop Verification

数字化反应堆仪表控制系统的可靠性设计

Measures to enhance the reliability of digital reactor instrumentation and control system

核反应堆功率控制系统的数字化实现

A Digitalized Power Control System for Nuclear Reactor

压水型核反应堆功率控制系统的优化设计

Optimal design of power control system of PRW

数字化反应堆功率控制系统

Digital Reactor Power Control System

反应堆安全控制系统

Reactor safety control system

反应堆手动控制系统

Reactor manual control system

反应堆装置控制系统

Reactor plant control system

将核仪器测量参数进行数字化处理是反应堆控制保护系统计算机化的前提，也是保护系统“冗余和多样性原则”在核测仪器中的应用。

Digitizing the measuring data from nuclear instruments is precondition of reactor control and protection system which would be computerizing , and it is also an application of redundancy and variety of reactor protection system in nuclear measuring instruments . At last the working state is described .

反应堆最优功率控制系统的设计

The optimal design of power regulating system of reactor

反应堆保护控制棒系统

Reactor protection control rod system

反应堆再循环量控制系统

Reactor recirculation flow control system

反应堆仪表和控制系统（I&C）的数字化发展方向成为趋势，反应堆堆外核测量系统的数字化势在必行。

For the digitization development direction of reactor instrument and control system become a tendency , the digital nuclear measurement of exterior reactor is imperative under the situation .

驱动ADS次临界反应堆的稳态外源控制系统

Steady external neutron source system of driven sub - critical reactor for ADS

核电机组反应堆平均温度控制仿真系统图形化建模中温平板型SOFC电堆的模拟与控制

Graphical modeling for simulation of average temperature control systems for nuclear units ' reactors

反应堆水力驱动控制棒系统安全分析

The safety analysis of hydraulic control rod drive system for nuclear reactor