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Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method

  • Lekang Chen (School of Nuclear Science and Technology, University of South China) ;
  • Chuqi Chen (School of Nuclear Science and Technology, University of South China) ;
  • Linna Wang (School of Nuclear Science and Technology, University of South China) ;
  • Wenjie Zeng (School of Nuclear Science and Technology, University of South China) ;
  • Zhifeng Li (Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University)
  • Received : 2022.11.11
  • Accepted : 2023.03.27
  • Published : 2023.07.25

Abstract

To study the influence of parameter uncertainty in small pressurized water reactor (SPWR) once-through steam generator (OTSG), the nonlinear mathematical model of the SPWR is firstly established. Including the reactor core model, the OTSG model and the pressurizer model. Secondly, a control strategy that both the reactor core coolant average temperature and the secondary-side outlet pressure of the OTSG are constant is adopted. Then, the uncertainty quantification method is established based on Latin hypercube sampling and statistical method. On this basis, the quantitative platform for parameter uncertainty of the OTSG is developed. Finally, taking the uncertainty in primary-side flowrate of the OTSG as an example, the platform application work is carried out under the variable load in SPWR and step disturbance of secondary-side flowrate of the OTSG. The results show that the maximum uncertainty in the critical output parameters is acceptable for SPWR.

Keywords

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 (S202210555135), and the science and technology innovation Program of Hunan Province (2020RC4053).

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