Off-line debugging simulation device of steam-driven feedwater pump in nuclear power plant

Abstract

The invention discloses an off-line debugging simulation device for a steam-driven feed pump of a nuclear power plant. The off-line debugging simulation device comprises a power supply management module and a simulation module. The simulation module generates a rotating speed given value of the steam-driven feed pump of the nuclear power plant according to pre-stored information and converts and transmits the rotating speed given value to a remote rotating speed given value interface of a rotating speed control system. The simulation module obtains a driving command of the steam-driven feed pump of the nuclear power plant through an actuator, generates a rotating speed detection signal of the steam-driven feed pump of the nuclear power plant according to the driving command, the real-timerotating speed given value and a mathematical model of the steam-driven feed pump of the nuclear power plant and converts and transmits the rotating speed detection signal to a rotating speed detection interface of the rotating speed control system, and the power supply management module supplies power to the simulation module. The device simulates the steam-driven main feed pump of the nuclear power plant and provides a virtual control object for a governor of the steam-driven main feed pump, so that off-line debugging and machine baking are facilitated, on-site debugging risks are reduced, and the operation stability and reliability of the nuclear power plant are improved.

Description

technical field [0001] The invention relates to the debugging of the rotational speed control system of a steam-driven main feed water pump in a nuclear power plant. Background technique [0002] The water level control system of the steam generator in the nuclear power plant is the control center of the entire secondary loop. The control loop is composed of a cascaded PID. The inner loop is the single-loop PID control system with the speed of the feed pump as the control object. An important part that directly affects the adjustment quality. [0003] The power source of the secondary circuit of the nuclear power plant is two steam-driven main feed water pumps and one electric main feed water pump. During the normal start-up process, start the electric feed water pump first; when the nuclear power rises to 8% Pn platform, the first steam-driven main feed water pump starts; when the nuclear power rises to 30% Pn platform, start the second steam-driven main feed water pump A...

AI Technical Summary

Problems solved by technology

[0005] However, with this current test method, since the adjustment quality of the speed control system cannot be determined, and the process systems of different manufacturers are greatly different, the PID parameters preset by the manufacturer may not be able to match the current control object.

Moreover, when the speed control system is working normally, it receives the command of given speed, and measures the current real-time speed, and generates control output after PID calculation, and controls the current speed to be in a given state. Since the control loop of the traditional test method is disconnected, the control The output cannot act on the real-time speed, so the traditional test method cannot judge the control quality

Images