反应堆控制

核反应堆控制材料&B4C的研究

Study of reactor control material-b_4c

反应堆控制棒材料Ag-In-Cd的热物理性能测量

Thermal Property Measurement of Reactor Control Material Rod Ag-In - Cd

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

反应堆控制棒在事故工况下的落棒时间分析

Computation of Reactor Control Rod Drop Time under Accident Conditions

反应堆控制棒驱动线故障分析

Fault Analysis for a Certain Reactor Control Rod Drive Line

介绍了反应堆控制棒的一种新型电磁驱动机构，其电磁铁线圈吸引位于密封筒内的衔铁，衔铁与驱动对象相连；

: The paper introduces a new electromagnet drive for reactor control rod .

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

金属铪是优异的核反应堆控制材料。

Hafnium metal is excellent nuclear reactor control material .

反应堆控制总工程师监督反应堆。

Chief engineer of reactor control supervises the reactor .

核反应堆控制棒水压驱动技术

Hydraulic control rod drive technology for nuclear reactors

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

反应堆控制棒导向管环形缝隙内漏流量的实验测定及其研究

Experimental Determination and Research of Leakage Flow in Annular Gaps of the Reactor Control Rod Guide Tubes

本工作在反应堆控制棒可移动线圈电磁驱动机构工程样机实验台架上，进行了电磁铁刚度实验。

This work concerns in the rigidity experiment of coil-moveable electromagnetic drive mechanism for reactor control rod .

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

用作反应堆控制材料，特种玻璃器皿着色。

Function : used in the manufacture of reactor of the domination materials ; color particular kind of glass ware .

当反应堆控制棒采用磁阻电动机驱动时，需要一个相序可逆的低频电源。

A magnetic reluctance motor is used for driving a reactor control rod , it needs a low-frequency power unit .

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 .

控制棒的落棒在反应堆控制中是一个十分重要的方面，尤其是落棒时间这个参数。

Control rod is a key safety control system for nuclear reactors , with the scram time parameters being crucial to reactor safety .

研究反应堆控制棒水力驱动装置在冲击作用下的流固耦合动力学问题。

The fluid-solid coupling dynamics of a hydraulic drive for a reactor control rod were analyzed to evaluate its response with impact load .

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 .

在清华大学核能与新能源技术研究院的反应堆控制棒可移动线圈电磁驱动机构实验台架上进行了反应堆控制棒可移动线圈电磁驱动机构极限承载能力实验。

The study of the maximal load capacity of the moveable coil electromagnetic drive for reactor control rod has been conducted at Institute of Nuclear and New Energy , Tsinghua University .

本文分析了反应堆控制棒驱动线几种典型故障发生的原因和机理，并提出了消除故障的改进措施。

In this paper , the causes of some typical faults of a certain reactor control rod drive line and their mechanism are analyzed , and the measures for troble removal are proposed .

在核物理研究、反应堆控制、加速器技术及空间探测、核辐射防护等领域，都需要精确了解辐射场内中子能谱分布。

It is necessary to know the accurate neutron spectrum in many fields , such as nuclear physics research , reactor techniques , accelerator operation , space exploration , radiological protection and so on .

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 .