QIN Benke

Senior Research Scientist of Nuclear Science and Engineering
Division  of Reactor Equipment

qinbk@tsinghua.edu.cn
(+86 10) 89796058-807

Education background

PhD, Tsinghua University, Nuclear Science and Engineering, 2006
B.S., Xi’an Jiaotong University, Energy and Power Engineering, 2000

Experience

12/2010-present, Senior Research Scientist, Division of Reactor Equipment, INET
03/2006-12/2010, Research Scientist, Division of Reactor Equipment, INET

Social service

Journal Reviewer

Atomic Energy Science and Technology
Nuclear Science and Engineering
Progress in Nuclear Energy
Nuclear Engineering and Design

Areas of Research Interests/ Research Projects

Qin’s research interests are in the areas of reactor equipment and reactor thermo-hydraulics, etc..
Reactor Thermo-hydraulics
Research on fluid and structure interaction (FSI), transient flow, vibration reduction and acoustics of equipment, and scaling analysis of large scale thermo-hydraulics test bench
Reactor Equipment
Research on control rod hydraulic driving technology, fluid machinery, control rod position measurement technology, etc..？

Research Status

2011.1-2019.12, Ministry of Science and Technology
Research on performance and verification   of control rod hydraulic drive system
Control rod hydraulic drive system(CRHDS) is developed as a new type of built-in control rod drive technology, which can be directly applied to the integrated nuclear reactor. The design of the CRHDS doesn’t penetrate the pressure vessel, shortens the control rod drive line, and eliminates the uncontrolled rod ejection accident. The CRHDS is driven by hydrostatic pressure and can position the control rod more accurately. This research is aimed to obtain and optimize the working mechanism, key design and operation parameters of the CRHDS, and carry out the engineering verification test of the control rod hydraulic drive line.

2011.1-2016.12, National Energy Administration
Key technology research and key equipment verification of NHR200-Ⅱ nuclear heating reactor- Engineering   verification test of hydraulic control rod drive system
Control rod hydraulic drive system(CRHDS) is the major reactivity control equipment of the nuclear heating reactor NHR200-Ⅱ. It performs the reactor startup, shutdown and different power operation functions through moving up and down, scram and holding position of control rods in the reactor core. This research includes the performance test, engineering verification test and mechanism analysis of CRHDS, which lays the foundation for the engineering application of CRHDS in NHR200-Ⅱ.

2019-2021, Tsinghua University Laboratory Innovation Fund
Research on comprehensive performance measurement technology of hydraulic cylinder for control rod drive line
Research on the key measurement and test technology of hydraulic loop, which includes 1) Research on kinetic resistance measurement technology of the hydraulic cylinder; 2) Research on high precision dynamic low flow rate measurement technology; 3) Research on measurement and analysis technology of vibration and noise of hydraulic cylinder and hydraulic circuit.

2008.1-2010.9 Project of CAP1400 demonstration power plant, Ministry of Science and Technology
Overall performance test and   verification of passive core cooling system for CAP1400 nuclear reactor
This research is aimed to finish the scaling analysis of overall performance test bench for CAP1400 passive core cooling system though Hierarchical Two-Tiered Scaling method, determine the overall scaling design ratios of the test rig, carry out the equipment scaling analysis of the reactor core, ACC, IRWST, CMT and long term pit circulation etc., and lay the foundation for the design and construction of the test rig.

Academic Achievement

Publications

Benke Qin, Jiang Junfei, Hanliang Bo. Study on the buffering characteristics of the new control rod hydraulic damper for the control rod hydraulic drive system. Proceedings of the 2019 27th International Conference on Nuclear Engineering, May 19-24, 2019. Tsukuba, Ibaraki, Japan.
Benke Qin, Leishi Li, Hanliang Bo. Decelerating performance and parameter analysis of the control rod hydraulic deceleration device for control rod hydraulic drive system. Journal of nuclear engineering and radiation science, 2019, 5(3), 031702-1-031702-10.
Guang Hu, Benke Qin, Hanliang Bo. Built-in capacitance sensor for control rod position measurement in NHR-200 with PEEK material. Annals of Nuclear Energy, 2019, 124:372-384.  
Hu Guang, Qin Benke, Liu Qianfeng, Bo Hanliang. Control rod position measurement by two-electrode capacitance sensor in nuclear heating reactor[J]. Journal of Nuclear Science and Technology, 2019, 56(1):32-40. 
Benke Qin, Leishi Li, Hanliang Bo. 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, 2018, 120: 814–827. 
Jiang Junfei, Benke Qin, Hanliang Bo. Experimental and numerical analysis of the flow field in the integrated valve for the control rod hydraulic drive system. Proceedings of the 2018 26th International Conference on Nuclear Engineering, July 22-26, 2018, London, England.
Guang Hu, Benke Qin, Hanliang Bo. Control rod position measurement with helix-electrode capacitance sensor in nuclear heating reactor. Annals of Nuclear Energy, 2018, 120: 788–797.
Sun Xinming, Qin Benke, Bo Hanliang. Transient flow analysis of the single cylinder for the control rod hydraulic driving system[J]. Annals of Nuclear Energy, 2017, 101:151-158. SCI
Liu Qianfeng, Qin Benke, Li Y, et al. Sensitivity analysis of the parameters of the hydraulic cylinder in pressure transients stepping motion for the control rod hydraulic drive system based on Model II[J]. Journal of Nuclear Science & Technology, 2017, 54(3):1-13.
Sun Xinming, Qin Benke, Bo Hanliang. Transient flow analysis of integrated valve opening process[J]. Nuclear Engineering & Design, 2017, 313:296-305.
Benke Qin, Leishi Li, Hanliang Bo. Experimental study on scram performance of hydraulic deceleration device for control rod hydraulic drive system[J]. Atomic Energy Science and Technology, 2017, 51(11):2054-2061.
Leishi Li, Benke Qin, Hanliang Bo. 3D Numerical analysis of hydraulic deceleration device flow channel of control rod hydraulic drive system[J]. Atomic Energy Science and Technology, 2017, 51(10): 1791-1799.
Benke Qin, Leishi Li, Hanliang Bo. Numerical and experimental analysis of the control rod hydraulic deceleration device for the control rod hydraulic drive system, Proceedings of 2017 25th International Conference on Nuclear Engineering. July 2-6, 2017, Shanghai, China.
Benke Qin, Xingxing Xu, Hanliang Bo, Wei Song. Study on decelerating performance of hydraulic driving control rod[J]. Atomic Energy Science and Technology, 2015, 49(05): 825-831.

Last updated: 2020-10-07