Simulation device and simulation method of on-site driving apparatus of nuclear power station

Abstract

The invention discloses a simulation device and simulation method of an on-site driving apparatus of a nuclear power station. Simulation of the on-site driving apparatus of the nuclear power station is realized in a function test of a DCS (Digital Control System) of the nuclear power station. The simulation device of the on-site driving apparatus of the nuclear power station comprises a simulator and an interface cable; and the simulator is seamlessly terminated with the digital control system through the interface cable. The simulator comprises at least a channel circuit; and each channel circuit enables the simulator to respectively simulate corresponding apparatuses by switching states of interconnected first switching component and second switching component so as to make a corresponding response to a command signal sent from the digital control system, so that a user has no need to build a model and organize states in the function test of the DCS control system of the nuclear power station. However, a plurality of independent channel circuits enables the simulation device of the on-site driving apparatus of the nuclear power station disclosed by the invention to have high operational reliability and discover and remove fault points conveniently.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant digital control, and more specifically, relates to a simulation device and a simulation method for on-site driving equipment of a nuclear power plant in functional testing of a nuclear power plant digital control system. Background technique [0002] 1. Definition of abbreviations and key terms: [0003] MVS-5: Motor&Valve Simulator(5 channels), five-channel motor / valve simulator. [0004] CPR1000: Chinese Pressurized Water Reactor 1000 (MW), a localized million-kilowatt pressurized water reactor nuclear power unit. [0005] EPR: European Pressurized Water Reactor; European Pressurized Water Reactor. [0006] DCS: Digital Control System, digital control system. Here it specifically refers to the general term of non-safety level control system and safety level control system of nuclear power plant, that is, DCS digital instrument control system of nuclear power plant. [0007] I&C: ...

AI Technical Summary

Problems solved by technology

[0049] The technical problem to be solved by the present invention is that in the function test of the DCS control system of a nuclear power plant in view of the prior art, the user needs to model and configure by himself according to the task; the operation is complicated, and the terminal connection with the DCS cabinet is complicated; It is difficult to quickly find and troubleshoot the fault point and the defects of low work reliability, providing a configuration that does not require users to model themselves; it has a good interface with both TXP and TXS platforms, and realizes seamless connection with the main DCS system; it is equipped with multiple independent channel to ensure that a channel failure will not affect other channels of the simulation device and simulation method of nuclear power plant field drive equipment

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