Nuclear Engineering and Technology

  • 제51권2호
  • /
  • Pages.546-555
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  • 2019
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Research on the structure design of the LBE reactor coolant pump in the lead base heap

  • 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) ;
  • Wang, Xiuli (National Research Center of Pumps, Jiangsu University) ;
  • An, Ce (National Research Center of Pumps, Jiangsu University) ;
  • Chen, Jing (National Research Center of Pumps, Jiangsu University)
  • 투고 : 2018.03.31
  • 심사 : 2018.09.28
  • 발행 : 2019.04.25
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초록

Since the first nuclear reactor first critical, nuclear systems has gone through four generations of history, and the fourth generation nuclear system will be truly realized in the near future. The notions of SVBR and lead-bismuth eutectic alloy coolant put forward by Russia were well received by the international nuclear science community. Lead-bismuth eutectic alloy with the ability of the better neutron economy, the low melting point, the high boiling point, the chemical inertness to water and air and other features, which was considered the most promising coolant for the 4th generation nuclear reactors. This study mainly focuses on the structural design optimization of the 4th-generation reactor coolant pump, including analysis of external characteristics, inner flow, and transient characteristic. It was found that: the reactor coolant pump with a central symmetrical dual-outlet volute structure has better radial-direction balance, the pump without guide vane has better hydraulic performance, and the pump with guide vanes has worse torsional vibration and pressure pulsation. This study serves as experience accumulation and technical support for the development of the 4th generation nuclear energy system.

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참고문헌

  1. Hartmut U. Wider, Johan C. Klaus Dietze Jurgen Konys Heavy Metal Cooled Reactors: Pros and Cons.
  2. M. Kazuaki, Innovative Nuclear Energy Systems, The Institute of Applied Energy.Science and Culture Series: Nuclear Strategy And Peace Technology, 2007, pp. 22-25.
  3. US DOE Office of Nuclear Energy, The U.S. Generation IV Fast Reactor Strategy, DOE/NE-0130, 2006.
  4. YuG. Dragunov, V.S. Stepanov, et al., Project of svbr-75/100 reactor plant with improved safety for nucler sources of small and medium power, in: 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Gridsdubrovnik, 2004.
  5. M.Y. LIU, Study on Flow and Heat Transfer in Natural Circulation of Lead and Bismuth, North China Electric Power University, Beijing, 2013.
  6. W.L. Zhan, H.S. Xu, Advanced fission energy program-ADS transmutation system, Bull. Chin. Acad. Sci. 21 (Issue 3) (2012) 375-381.
  7. C. Rubbia, J. Rubio, S. Buono, et al., Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier, European Organization for Nuclear Research, 1995.
  8. J. Cao, Y.Q. Shi, P. Xia, X.B. Wu, ADS transmutation research based on venus 1#, Atomic Energy Sci. Technol. 46 (Issue 10) (2012) 1185-1188.
  9. Z. Chen, Y. Chen, Y.Q. Bai, et al., CLEAR Neutron Design Analysis of Accelerator - Driven Nuclear Waste. 5th Conference on Reactor Physics and Nuclear Materials, 2nd Workshop on Nuclear Energy Software Autonomy, Chongqing, 2011, p. 1.
  10. Y.Q. Bai, W.H. Wang, J.Q. Jiang, et al., Accelerator driven nuclear waste transmutation reactor CLEAR conceptual design, in: 5th Conference on Reactor Physics and Nuclear Materials, 2nd Workshop on Nuclear Energy Software Autonomy. Chongqing, 2011, p. 1.
  11. L. Brissonneau, F. Beauchamp, O. M, et al., Oxygen control systems and impurity purification in LBE: learning from DEMETRA project, J. Nucl. Mater. 415 (2011) 348-360. https://doi.org/10.1016/j.jnucmat.2011.04.040
  12. A. Bournia, Studies of Thermal Behavior under Loss of Pump Power Transient Conditions, Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh, 1958.
  13. O. Pavel, G. Ferdinand, Simulations and field tests of a reactor coolant pump emergency start-up by means of remote gas units, Trans. Energy Con. 7 (4) (1992) 691-697. https://doi.org/10.1109/60.182652
  14. H. Gao, F. Gao, X. Zhao, et al., Transient flow analysis in reactor coolant pump systems during flow coastdown period, Nucl. Eng. Des. 241 (2) (2011) 509-514. https://doi.org/10.1016/j.nucengdes.2010.09.033
  15. S.L. Huang, J.J. Fen, Q.Y. Chen, et al., AP1000 DNBR calculation and analysis of complete loss of flow accident, Nucl. Power Eng. 02 (2015) 33-36.
  16. X.J. Liu, Study on the Flow and Vibration Characteristics of Reactor Coolant Pump under Power Failure, Shanghai Jiao Tong University, 2008.
  17. P. Guo, J.P. Xiang, B. Lin, et al., Analysis of water loss test of AP 1000 nuclear power main pump, Pump Tech. (01) (2016) 33-35.
  18. Y. Long, R.S. Zhu, Q. Fu, et al., Numerical simulation of unsteady flow in reactor coolant pump with small flow, J. Drainage Irrigation Machinery Eng. (04) (2014) 290-295.
  19. P. Wang, S.Q. Yuan, X.L. Wang, et al., Numerical analysis of effect of eccentricity on radial force of reactor coolant pump, J. Drainage Irrigation Machinery Eng. (06) (2015) 461-466.
  20. Q. Fu, S.B. Xing, R.S. Zhu, et al., Effect of blade inlet position on flow characteristics of nuclear reactor coolant pump under gas-liquid two-phase condition, Nucl. Power Eng. (03) (2016) 87-93.
  21. R.S. Zhu, Z.L. Chen, X.L. Wang, et al., Numerical study on cavitation characteristics of CAP1400 nuclear main coolant pump, J. Drainage Irrigation Machinery Eng. (06) (2016) 490-495.
  22. X.L. Wang, Y.G. Lu, S.Q. Yuan, et al., Dynamic characteristics analysis of the reactor coolant pump variation based on fluid-structure coupling, J. Harbin Eng. Univ. (02) (2015) 213-217.
  23. W. Jiang, X.Y. Zhu, G.J. Li, et al., Influence of relative installation positions of guide vane and volute tongue on radial force in centrifugal pump, Trans. Chin. Soc. Agric. Mach. (02) (2016) 28-34.
  24. J.G. Mu, J.G. Liu, J.G. Liu, et al., Effects of different tongues on radial hydraulic force characteristics and internal flow field of a centrifugal pump, J. Vib. Shock (11) (2016) 116-122. https://doi.org/10.13465/j.cnki.jvs.2015.11.021
  25. S.Q. Yuan, J.S. Zhou, J.F. Zhang, et al., Numerical simulation on radial hydraulic forces for screw-type centrifugal pump with splitter blade, Trans. Chin. Soc. Agric. Mach. (09) (2012) 37-42.
  26. M.G. Yang, T. Shao, B. Gao, et al., Interior flow and unsteady performance of molten salt pump with splitter space guide vane, J. Drainage Irrigation Machinery Eng. (04) (2015) 306-310.

피인용 문헌

  1. The Influence and Optimization of Geometrical Parameters on Coast-Down Characteristics of Nuclear Reactor Coolant Pumps vol.7, pp.6, 2019, https://doi.org/10.3390/pr7060327
  2. Mathematical Modelling Forecast on the Idling Transient Characteristic of Reactor Coolant Pump vol.7, pp.7, 2019, https://doi.org/10.3390/pr7070452
  3. Study on pressure pulsation characteristics of reactor coolant pump during the idling transition process vol.25, pp.18, 2019, https://doi.org/10.1177/1077546319858856
  4. Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition vol.51, pp.7, 2019, https://doi.org/10.1016/j.net.2019.05.009
  5. Influence of Eccentricity on Hydrodynamic Characteristics of Nuclear Reactor Coolant Pump under Different Cavitation Conditions vol.8, pp.1, 2019, https://doi.org/10.3390/pr8010098
  6. Investigation of the effects of the impeller blades and vane blades on the CAP1400 nuclear coolant pump's performances with a united optimal design technology vol.126, 2019, https://doi.org/10.1016/j.pnucene.2020.103426
  7. Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant vol.53, pp.2, 2019, https://doi.org/10.1016/j.net.2020.07.008
  8. Comparative analysis of internal flow characteristics of LBE-cooled fast reactor main coolant pump with different structures under reverse rotation accident conditions vol.53, pp.7, 2019, https://doi.org/10.1016/j.net.2021.01.015