Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Research on aging-related degradation of control rod drive system based on dynamic object-oriented Bayesian network and hidden Markov model

  • Kang Zhu (Institute of Nuclear Science and Technology, Naval University of Engineering) ;
  • Xinwen Zhao (Institute of Nuclear Science and Technology, Naval University of Engineering) ;
  • Liming Zhang (Institute of Nuclear Science and Technology, Naval University of Engineering) ;
  • Hang Yu (Institute of Nuclear Science and Technology, Naval University of Engineering)
  • Received : 2022.02.03
  • Accepted : 2022.06.19
  • Published : 2022.11.25
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Abstract

The control rod drive system is critical to the reactor's reliable operation. The performance of its control system and mechanical system will gradually deteriorate because of operational and environmental stresses, thus increasing the reactor's operational risk. Currently there are few researches on the aging-related degradation of the entire control rod drive system. Because it is difficult to quantify the effect of various environmental stresses and establish an accurate physical model when multiple mechanisms superimposed in the degradation process. Therefore, this paper investigates the aging-related degradation of a control rod drive system by integrating Dynamic Object-Oriented Bayesian Network and Hidden Markov Model. Uncertainties in the degradation of the control system and mechanical system are addressed by using fuzzy theory and the Hidden Markov Model respectively. A system which consists of eight control rod drive mechanisms divided into two groups is used to demonstrate the method. The aging-related degradation of the control rod drive system is analyzed by the Bayesian inference algorithm based on the accelerated life test data, and the impact of different operating schemes on the system performance is also investigated. Meanwhile, the components or units that have major impact on the system's performance are identified at different operational phases. Finally, several essential safety measures are suggested to mitigate the risk caused by the system degradation.

Keywords

Acknowledgement

The authors thankfully acknowledge the financial support provided by the key laboratory of nuclear reactor system design open fund (HT-KFKT-02-2017101). Meanwhile the authors would like to thank the associate editor and anonymous reviewers for their constructive suggestions and comments on the previous version of this paper.

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