DOI QR코드

DOI QR Code

Operation optimization of auxiliary electric boiler system in HTR-PM nuclear power plant

  • Du, Xingxuan (School of Management, Xi'an University of Architecture and Technology) ;
  • Ma, Xiaolong (Xi'an Thermal Power Research Institute Co. Ltd) ;
  • Liu, Junfeng (Xi'an Thermal Power Research Institute Co. Ltd) ;
  • Wu, Shifa (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University) ;
  • Wang, Pengfei (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University)
  • Received : 2022.01.10
  • Accepted : 2022.02.16
  • Published : 2022.08.25

Abstract

Electric boilers (EBs) are the backup steam source for the auxiliary steam system of high-temperature gas-cooled reactor nuclear power plants. When the plant is in normal operations, the EB is always in hot standby status. However, the current hot standby operation strategy has problems of slow response, high power consumption, and long operation time. To solve these problems, this study focuses on the optimization of hot standby operations for the EB system. First, mathematical models of an electrode immersion EB and its accompanying deaerator were established. Then, a control simulation platform of the EB system was developed in MATLAB/Simulink implementing the established mathematical models and corresponding control systems. Finally, two optimization strategies for the EB hot standby operation were proposed, followed by dynamic simulations of the EB system transient from hot standby to normal operations. The results indicate that the proposed optimization strategies can significantly speed up the transient response of the EB system from hot standby to normal operations and reduce the power consumption in hot standby operations, improving the dynamic performance and economy of the system.

Keywords

Acknowledgement

This research is funded by the Xi'an Thermal Power Research Institute Co., Ltd.

References

  1. H. Reutler, G.H. Lohnert, The modular high-temperature reactor, Nucl. Technol. 62 (1) (1983) 22-30. https://doi.org/10.13182/NT83-A33228
  2. H. Reutler, G. Lohnert, Advantages of going modular in HTRs, Nucl. Eng. Des. 78 (2) (1984) 129-136. https://doi.org/10.1016/0029-5493(84)90298-X
  3. H. Frewer, W. Keller, R. Pruschek, The modular high-temperature reactor, Nucl. Sci. Eng. 90 (4) (1985) 411-426. https://doi.org/10.13182/NSE85-4
  4. J.E. Kelly, Generation IV International Forum: a decade of progress through international cooperation, Prog. Nucl. Energy 77 (2014) 240-246. https://doi.org/10.1016/j.pnucene.2014.02.010
  5. D.Z. Wang, D.X. Zhong, Y.K. Yu, Present status of research and development for HTR in China, Energy 16 (1) (1991) 159-167. https://doi.org/10.1016/0360-5442(91)90097-6
  6. Z. Zhang, Z.X. Wu, D.Z. Wang, Y.H. Xu, Y.L. Sun, F. Li, Y.J. Dong, Current status and technical description of Chinese 2×250MWth HTR-PM demonstration plant, Nucl. Eng. Des. 239 (7) (2009) 1212-1219. https://doi.org/10.1016/j.nucengdes.2009.02.023
  7. A.C. Kadak, The status of the US high-temperature gas reactors, Eng. Times 2 (1) (2016) 119-123.
  8. S. Ueta, J. Aihara, K. Sawa, A. Yasuda, M. Honda, N. Furihata, Development of high temperature gas-cooled reactor (HTGR) fuel in Japan, Prog. Nucl. Energy 53 (7) (2011) 788-793. https://doi.org/10.1016/j.pnucene.2011.05.005
  9. Z.Y. Zhang, Z.X. Wu, Y.L. Sun, F. Li, Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM, Nucl. Eng. Des. 236 (5) (2006) 485-490. https://doi.org/10.1016/j.nucengdes.2005.11.024
  10. P.Y. Zhang, Q.Q. Guo, S. Pang, Y.L. Sun, Y. Chen, Experimental research on vertical mechanical performance of embedded through-penetrating steel-concrete composite joint in high-temperature gas-cooled reactor pebble-bed module, Nucl. Eng. Technol. (2022).
  11. W.J. Zeng, Q.F. Jiang, S.M. Du, T.Y. Hui, S. Li, Design of the flexible switching controller for small PWR core power control with the multi-model, Nucl. Eng. Technol. 53 (2021) 851-859. https://doi.org/10.1016/j.net.2020.07.037
  12. L. Wang, X.Y. Wei, F.Y. Zhao, X.G. Fu, Modification and analysis of load follow control without boron adjustment for CPR1000, Ann. Nucl. Energy 70 (2014) 317-328. https://doi.org/10.1016/j.anucene.2013.12.001
  13. M.R. Li, W.Z. Chen, J.L. Hao, W.T. Li, Experimental and numerical investigations on effect of reverse flow on transient from forced circulation to natural circulation, Nucl. Eng. Technol. 52 (2020) 1955-1962. https://doi.org/10.1016/j.net.2020.02.019
  14. P. Singh, L.K. Singh, Instrumentation and control systems design for nuclear power plant: an interview study with industry practitioners, Nucl. Eng. Technol. 53 (2021) 3694-3703. https://doi.org/10.1016/j.net.2021.05.025
  15. J.W. H, J.Q. Yuan, Disturbance observer-based robust backstepping load-following control for MHTGRs with actuator saturation and disturbances, Nucl. Eng. Technol. 53 (2021) 3685-3693. https://doi.org/10.1016/j.net.2021.05.019
  16. Z. Dong, Nonlinear adaptive power-level control for modular high temperature gas-cooled reactors, IEEE Trans. Nucl. Sci. 60 (2) (2013) 1332-1345. https://doi.org/10.1109/TNS.2013.2252023
  17. D. Jiang, Z. Dong, Dynamic matrix control for thermal power of multi-modular high temperature gas-cooled reactor plants, Energy (198) (2020) 117386.
  18. S.M. Baek, H.C. No, I.Y. Park, A non-equilibrium three-region model for transient analysis of pressurized water reactor pressurizer, Nucl. Technol. 74 (1986) 213-221.
  19. J.F. Wilson, R.J. Grenda, J.F. Patterson, The velocity of rising steam in a bubble two-phase mixture, Trans. Am. Nucl. Soc. 5 (1962) 151.
  20. A. Bejan, A.D. Kraus, Heat Transfer Handbook, John Wiley & Sons, 2003.
  21. Mathworks Inc, Control System Toolbox Documentation, 2016.