Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation

  • Li, Xiaoyu (School of Nuclear Science and Technology, University of South China) ;
  • Li, Chuhao (School of Nuclear Science and Technology, University of South China) ;
  • Hu, Yang (School of Nuclear Science and Technology, University of South China) ;
  • Yu, Yongqi (School of Nuclear Science and Technology, University of South China) ;
  • Zeng, Wenjie (School of Nuclear Science and Technology, University of South China) ;
  • Wu, Haibiao (School of Nuclear Science and Technology, University of South China)
  • Received : 2021.10.23
  • Accepted : 2022.01.02
  • Published : 2022.06.25
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Abstract

The coolant temperature feedback coefficient is an important parameter of reactor core power control system. To study the coolant temperature feedback coefficient influence on the core power control system of small PWR, the core power control system is built with the nonlinear model and fuzzy control theory. Then, the uncertainty quantification method of reactor core parameters is established based on the Latin hypercube sampling method and the Bootstrap method. Finally, under the conditions of reactivity step perturbation and coolant inlet temperature step perturbation, uncertainty analysis for two cases is carried out. The result shows that with fuzzy controller and fuzzy PID controller, the uncertainty of the coolant temperature feedback coefficient affects the core power control system, and the maximum uncertainties of core relative power, coolant temperature deviation, fuel temperature deviation and total reactivity are acceptable.

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Acknowledgement

The work is supported in part by the National Natural Science Foundation of China Youth Fund (12005096), and the Provincial Innovation and Entrepreneurship Training Program for Undergraduates (S202110555173).

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