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.
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.
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.
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).
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.
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.
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.
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.
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