Experimental Study on Cold State Performance of Control Rod Hydraulic Drive System

被引：0
|
作者：
Qin B. [1 ]
Yang L. [1 ]
Bo H. [1 ]
机构：
[1] Institute of Nuclear and New Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing
来源：
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2022年 / 56卷 / 03期
关键词：
Cold state performance experiment; Control rod hydraulic drive mechanism; Control rod hydraulic drive system; Nuclear heating reactor; Scram performance;
D O I：
10.7538/yzk.2021.youxian.0091
中图分类号：
TL [原子能技术];
学科分类号：
0827 ;
摘要：
Control rod hydraulic drive system (CRHDS), which is invented by Institute of Nuclear and New Energy Technology, Tsinghua University for the nuclear heating reactor NHR200, is a new type of internal control rod drive technology. CRHDS is composed of control rod hydraulic drive mechanism (CRHDM), integrated valve, control rod and hydraulic buffer, etc. The cold state performance of CRHDS is the basis to determine control rod stepping time and system driving pressure. The composition and working principle of CRHDS were analyzed in the paper. The full scale CRHDS performance experiments, which include the minimum rod drop pressure test of hydraulic cylinder, step motion test of lifting cylinder and the scram performance test, were carried out under room temperature. Based on the experimental results, the changing laws of the key characteristic parameters of CRHDS were analyzed. The research results show that, the minimum rod drop pressure is the minimum driving pressure for CRHDM to work normally, and it corresponds to the starting point of the peak wave process on the time history curve of cylinder pressure. The inflection points of the pressure curves in the step-up and step-down processes of the control rod correspond to the end points of the step motion respectively. With the increase of the driving pressure, the inflection pressure of the hydraulic cylinder increases gradually, the step-up time and the time of the turning point decrease during the step-up process. The experimental results lay the basis for the design, optimization and engineering application of the CRHDS. © 2022, Editorial Board of Atomic Energy Science and Technology. All right reserved.
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页码：504 / 511
页数：7
相关论文
共 17 条
  • [1] (2007)
  • [2] CHI Zongbo, WU Yuanqiang, CHEN Yunxia, Et al., Study and design of hydraulic driving system of control rod, Nuclear Power Engineering, 20, 1, pp. 58-62, (1999)
  • [3] ATAOLLAH R, ALIREZA A., Control rod drop hydrodynamic analysis for a pressurized water reactor, Progress in Nuclear Energy, 88, pp. 191-197, (2016)
  • [4] ISHIDA T, IMAYOSHI S, YORITSUNE T, Et al., Development of in-vessel type control rod drive mechanism for marine reactor, Journal of Nuclear Science and Technology, 38, 7, pp. 557-570, (2003)
  • [5] QIN Benke, JIANG Junfei, BO Hanliang, Study on the decelerating mechanism of the new control rod hydraulic decelerator for the CRHDS based on numerical simulation and experiment, Annals of Nuclear Energy, 120, pp. 814-827, (2018)
  • [6] BO Hanliang, ZHENG Wenxiang, WANG Dazhong, Et al., Hydraulic control rod drive technology for nuclear reactors, Journal of Tsinghua University: Science and Technology, 45, 3, pp. 424-427, (2005)
  • [7] (2005)
  • [8] QIN Benke, BO Hanliang, ZHENG Wenxiang, Et al., Pressure transients in hydraulic cylinder step-up motion of control rod hydraulic drivemechanism, Journal of Tsinghua University: Science and Technology, 48, 12, pp. 2118-2121, (2008)
  • [9] QIN Benke, BO Hanliang, ZHENG Wenxiang, Study on step-down dynamic process of hydraulic cylinder for control rod hydraulic drive mechanism, Atomic Energy Science and Technology, 43, 4, pp. 345-349, (2009)
  • [10] JIANG Junfei, QIN Benke, BO Hanliang, Experimental and numerical analysis of the flow field in the integrated valve for the control rod hydraulic drive system, International Conference on Nuclear Engineering, (2018)
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