The Neutron Fluence Rate Measurement and Control Simulation of Adaptive Algorithm Simulates the Algorithm in Nuclear Power Plant

This project intends to use the step reaction data of nuclear power generation unit to establish its adaptive parameter model. Then the predictive control algorithm based on energy density equivalence relation is studied. The neutron flow rate variation in the power range of nuclear instruments in nuclear power plants is a key protection parameter of nuclear power plants, and its reasonable correction can not only ensure that it can continue to play its role in the case of rebound, drop rod and other failures, but also prevent the shutdown caused by pressure dumping at the beginning and end of the life cycle, thereby reducing <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">t</sup>he economy of nuclear power plants. In this paper, the correction factor of neutron energy rate is simulated by means of simulation and analysis. The algorithm does not need to strictly model the specific modeling mode of the system, and has low real-time performance, good tracking performance and robustness, and can effectively eliminate unmeasurable disturbance. The method is proved to be feasible by computer simulation.