Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident

Highlights: • The core transfer function is used to set up core model. • The core power control system with a BP neural network PID controller is designed. • The way to perform the uncertainty quantitative analysis is established by the Chebyshev inequality and relative standard deviation calculation. To study the influence of the reactivity feedback coefficient uncertainty on reactor core power control system, taking a lead-cooled fast reactor as the object, the core power control system with a BP neural network PID controller is designed. Drawing the input samples with Latin hypercube sampling method, the uncertainty quantitative analysis consists of the Chebyshev inequality and relative standard deviation calculation. Based on the method in this paper, the dynamic simulation of reactor core is performed. The results show that the uncertainties of the system output control performance parameters are less than 1% when introducing 50pcm and 100 pcm step reactivity. The uncertainty of the system output parameters changes and returns to zero with the action of the controller.