可移动线圈电磁驱动机构是一种新型的反应堆控制棒驱动机构。
Electromagnetic movable coil control rod drive mechanism is a new type drive mechanism.
本文介绍了稳态控制棒驱动机构的结构特点、设计参数和试验情况。
The structure characteristics, the parameter of design and the test results of CRDM are presented.
水力步进缸系统是以流体动压为动力的反应堆新型控制棒驱动装置。
A hydraulic step cylinder system (HSCS) used as a new kind of nuclear control rod driving system is driven by dynamic pressure.
脉冲控制棒驱动机构具有全行程脉冲时间短、结构简单、维修方便的特点。
The feature are: the pulse time of whole journey is short, the configuration is simple, the maintain is convenient.
本文简要介绍秦山核电厂控制棒驱动线的设计依据、设计要求以及试验研究。
This paper simply presents the bases of design, design requirement and experimental investigation of Qinshan nuclear power plant's control rod drive li-ne.
理想的一般混凝土，人行道及道路拆迁，再加上地面控制棒驱动和地下室防水。
Ideal for general concrete, sidewalk and road demolition, plus ground-rod driving and basement waterproofing.
为验证长寿命控制棒驱动机构能否满足设计要求，进行行驱动机构热态寿命考验。
The hot life test has been done to testify whether the longeval Control Rod Drive Mechanism can meet the requirements of the design indexes.
他们使得很多的安全系统,失效，他们不得不启动应急操作，我记得，使用控制棒驱动系统,来将核心冷却。
They essentially disabled many of the safety systems and they had to jury rig, and as I remember using the cooling from the control rod drive systems to cool the core.
控制棒水力驱动系统是核供热堆的关键系统之一，其运行失效将直接导致供热堆的非计划停堆。
The hydraulic system of control rod drives is one of the key systems in a nuclear heating reactor. The unplanned outage will be directly caused by the system failure.
为了解释控制棒可动线圈电磁驱动机构加入永磁后电磁力增强的机理，对机构的电磁机理及分布进行了研究。
The electromagnetic field distribution was studied to explain the increased electromagnetic force after installing permanent magnets in a movable magnetic coils control rod drive mechanism.
应用计算流体力学程序CFX5对水力驱动控制棒步进缸内部的三维流场进行了计算和分析。
The three dimensional flow field of the step cylinder in Hydraulic Control Rod Driving System (HCRDS) is calculated and analyzed with the computational fluid (dynamics) program CFX5 in detail.
针对控制棒水压驱动机构单个水压缸的步进性能，通过实验获得了水压缸步进的动态过程。
The dynamic stepping motion of a hydraulic cylinder for the control rod hydraulic drive mechanism (CRHDM) was tested experimentally.
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.
通过数值计算，分析了上置式水力驱动控制棒的落棒时间。
The time of dropping rod was analysed by numerical simulation.
控制棒水力驱动系统是核供热堆的关键系统之一 ，其运行失效将直接导致供热堆的非计划停堆。
The flow resistance of the integrated valve is one of the key parameters for the design of the control rod hydraulic drive system(CRHDS).
通过对计算结果进行分析，得出不同温度、流量下水力驱动控制棒系统不出现异常提棒现象的临界加速度。
The critical acceleration for the control rod not to move up or down abnormally was determined using them.
控制棒水力驱动系统是核供热堆的关键系统之一 ，其运行失效将直接导致供热堆的非计划停堆。
The control rod drive mechanism(CRDM) is one of the key equipment related to reactor normal operation, safety and reliability.
对水力驱动控制棒步进缸的静态保持特性进行了理论分析。
Theoretical analysis on the steady state property of step cylinder of the hydraulic control rod drive system for the 200 MW nuclear heating reactor have been carried out.
对水力驱动控制棒步进缸的静态保持特性进行了理论分析。
Theoretical analysis on the steady state property of step cylinder of the hydraulic control rod drive system for the 200 MW nuclear heating reactor have been carried out.
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