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

A technology for driving equipment and simulating devices, used in nuclear power plants, nuclear power generation, nuclear power plant control, etc. Reliable effect

Active Publication Date: 2012-02-22
中广核工程有限公司 +1
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  • Abstract
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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 defe...

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

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[0093] The simulation device and simulation method of the on-site driving equipment of the nuclear power plant of the present invention will be explained in more detail below in conjunction with the accompanying drawings and embodiments. Items marked with the same number in each drawing are identical or functionally similar items.

[0094] see Figure 4 , 7 And 14, the simulation device of the field driving equipment of the nuclear power plant of the present invention includes a simulator and an interface cable, and the simulator exchanges signals with the digital control system (DCS) through the interface cable; the simulator includes a housing 100 and is arranged in the housing 100 The multi-channel motor / valve simulator circuit, the multi-channel motor / valve simulator circuit includes at least one channel circuit T100, wherein the channel circuit T100 includes a close command relay R1, an open command relay R2 and a feedback relay R3; the channel circuit T100 also includes...

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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: ...

Claims

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Application Information

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IPC IPC(8): G21D3/00
CPCY02E30/00
Inventor 张彦牛茂龙张国军
Owner 中广核工程有限公司
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