This work concerns in the rigidity experiment of coil-moveable electromagnetic drive mechanism for reactor control rod.
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。
The cruciform control rod controlling is the main method to control reactivity in the nuclear heating reactor (NHR).
核供热反应堆的过剩反应性主要靠十字形控制棒来控制。
Control rod is a key safety control system for nuclear reactors, with the scram time parameters being crucial to reactor safety.
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。
The steady counting rates of neutron in reactor are measured by a conventional instrument(the start-up devices)to calibrate reactivity worth of a control rod.
利用常规仪器（堆控制室中的启动装置）测得反应堆中稳定的中子计数率来刻度控制棒的反应性当量。
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.
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 response amplitude also relates to the impact direction. When the reactor moved down rapidly, the response displacement of the control rod is larger.
冲击响应幅值还与冲击方向有关，当冲击位移向下时，控制棒的响应位移相对比较大。
The control rod drive mechanism(CRDM) is one of the key equipment related to reactor normal operation, safety and reliability.
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。
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.
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。
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