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Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition

  • Wang, Xiuli (National Research Center of Pumps, Jiangsu University) ;
  • Lu, Yonggang (National Research Center of Pumps, Jiangsu University) ;
  • Zhu, Rongsheng (National Research Center of Pumps, Jiangsu University) ;
  • Fu, Qiang (National Research Center of Pumps, Jiangsu University) ;
  • Yu, Haoqian (National Research Center of Pumps, Jiangsu University) ;
  • Chen, Yiming (National Research Center of Pumps, Jiangsu University)
  • Received : 2018.10.01
  • Accepted : 2019.05.12
  • Published : 2019.10.25

Abstract

The AP1000 reactor coolant pump is a vertical shielded-mixed flow pump, is the most important coolant power supply and energy exchange equipment in nuclear reactor primary circuit system, whose steadystate and transient performance affect the safety of the whole nuclear island. Moreover, safety demonstration of reactor coolant pump is the most important step to judge whether it can be practiced, among which software simulation is the first step of theoretical verification. This paper mainly introduces the fluid-solid coupling simulation method applied to reactor coolant pump, studying the feasibility of simulation results based on workbench fluid-solid coupling technology. The study found that: for the unsteady calculations of the pure liquid media, the average head of the reactor coolant pump with bidirectional fluid-solid coupling decreases to a certain extent. And the coupling result is closer to the real experimental value. The large stress and deformation of rotor under different flow conditions are mainly distributed on impeller and idler, and the stress concentration mainly occurs at the junction of front cover plate and blade outlet. Among the factors that affect the dynamic stress change of rotor, the pressure load takes a dominant position.

Keywords

Acknowledgement

Supported by : National Youth Natural Science Foundation of China, Natural Science Foundation of Jiangsu Province of China

References

  1. Jingren Guo, Mengjia Yang, Comparison and analysis on the differences between AP1000 and EPR engineered safety system [J], China. Nucl. Power 2 (2) (2009) 166-171.
  2. Xiaoqin Xiang, Research on Simulation of Advanced PWR Using RELAP5-HD code[D], Harbin Engineering University, 2014.
  3. Jiqiang Jing, Hongwei Zhai, On the history of word nuclear development and the road for China nuclear development, Northeast Electric Power Technol. 29 (2) (2008) 48-52. https://doi.org/10.3969/j.issn.1004-7913.2008.02.016
  4. Ye Zhang, Numerical Analysis of Fluid Structure Interaction and Comments to Rotor Stator Interaction in AP1000 Reactor Coolant Pump [D], Dalian University of Technology, 2012.
  5. Stephan M. Senn, Martin Seiler, Ottmar Schaefer, Blade excitation in pulse-charged mixed-flow turbocharger turbines [J], J. Turbomach.Transac. ASME. 133 (2) (2011), 021012. https://doi.org/10.1115/1.4001186
  6. Rice Tim, David Bell, Gurnam Singh, Identification of the stability margin between safe operation and the onset of blade flutter, J. Turbomach.Transac. ASME. 13 (1) (2009), 011009 (1-10).
  7. Zhongning Zhou, Yimin Li, Yongxia Gu, et al., Dynamic characteristic analysis of blade based on fluid-structure coupling [J], J. China Inst. Min. Technol. 38 (03) (2009) 401-405.
  8. Wenliang Lv, Numerical Analysis of Fluid-Structure Interaction on Rotor Blade of Counter-rotating Turbine [D], Nanjing University of Aeronautics and Astronautics, Nanjing, 2010.
  9. Ruiqin Zhang, Jiansheng Weng, Blade flutter analysis based on fluid solid coupling, Comput. Simul. 28 (3) (2010) 48-51. https://doi.org/10.3969/j.issn.1006-9348.2011.03.012
  10. Songling Wang, Zhe Sun, Zhengren Wu, Lei Zhang, Strength investigation of the centrifugal fan impeller based on fluid-structure coupling [J], J. North China Electr. Power Univ. (Soc. Sci.) 38 (4) (2011) 108-111.
  11. Xiangyang Chen, Danqing Yuan, Minguan Yang, et al., Blade stress of the reactor coolant pump of 300 MWe nuclear power plant in China based on fluid-solid coupling method [J], J. Mech. Eng. 46 (04) (2010) 111-115. https://doi.org/10.3901/JME.2010.04.111
  12. Yonggang Lu, Rongsheng Zhu, Xiuli Wang, et al., Study on the complete rotational characteristic of coolant pump in the gas-liquid two-phase operating condition, Ann. Nucl. Energy 123 (2019) 180-189. https://doi.org/10.1016/j.anucene.2018.09.030
  13. Yonggang Lu, Rongsheng Zhu, Xiuli Wang, et al., Study on gas-liquid two-phase all-characteristics of CAP1400 nuclear reactor coolant pump, Nucl. Eng. Des. 319 (2017) 140-148. https://doi.org/10.1016/j.nucengdes.2017.05.001
  14. Yonggang Lu, Rongsheng Zhu, Qiang Fu, et al., Research on the structure design of the LBE reactor coolant pump in the lead base heap, Nucl. Eng. Technol. 51 (2) (2019) 546-555. https://doi.org/10.1016/j.net.2018.09.023
  15. Wei Wang, Yayun Wang, Tao Tang, Lin Yin, Xiaofang Wang, Numerical simulation and test of cavitation performance of CAP1400 reactor coolant model pump [J], J. Drainage. Irrig. Mach. Eng. 37 (02) (2019) 100-105.
  16. Yun Jia, Xiangsong Liu, Yushuang Gao, 1000MW nuclear main pump impeller profile detection method, J. Drainage. Irrig. Mach. Eng. 36 (12) (2018) 1216-1221.
  17. Weifeng Qiu, Rongsheng Zhu, Xiuli Wang, Weiyuan Zhong, E. Cai, Analysis of the influence of impeller geometric parameters on the inert characteristics of nuclear main pump [J/OL], J. Drainage. Irrig. Mach. Eng. 1-6 (2019). -05-05], http://kns.cnki.net/kcms/detail/32.1814.TH.20180918.1552.010.html.
  18. Minguan Yang, Yuting Li, Gaobo, Dan Ni, Yongchao Zhang, The influence of different blade shapes on the energy distribution at the impeller outlet of mixed flow nuclear main pump [J], J. Drainage. Irrig. Mach. Eng. 36 (07) (2018) 560-566.
  19. F.R. Menter, M. Kunts, R. Langtry, Ten years of industrial experience with the SST turbulence model, Turbulence, Heat and Mass Transfer 4 (2003).
  20. F.R. Menter, Zonal Two-Equation K-${\omega}$ Turbulence Model for Aerodynamic flows[J], AIAA PaPer, 1993, pp. 1993-2006.
  21. Fujun Wang, Computational Fluid Dynamics Analysis [M], Tsinghua University Press, Beijing, 2004.
  22. Xingfan Guan, Modern Pump Technical Manual [M], China Astronautic Publishing House, Beijing, 1995.

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