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Simulation platform for rod control system of nuclear power station

A system simulation and nuclear power plant technology, applied in the field of nuclear power plant rod control system, can solve problems such as long maintenance period, self-renovation and maintenance of spare parts that cannot be diagnosed, and inflated maintenance costs of boards returned to the factory

Inactive Publication Date: 2017-09-01
CHINA GENERAL NUCLEAR POWER OPERATION +2
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This maintenance method has three disadvantages: 1) The spare parts are put into use without functional verification, which brings certain risks to the running unit; 2) Since there is no verification means, the replaced spare parts cannot be diagnosed and repaired independently; 3) Due to the production stoppage of the manufacturer or the long maintenance cycle, the number of on-site spare parts cards is gradually decreasing, and the pressure on the supply of on-site spare parts is increasing day by day, and the maintenance cost of the board parts is also inflated due to monopoly.

Method used

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  • Simulation platform for rod control system of nuclear power station

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Embodiment Construction

[0024] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific implementation manners of the present invention will now be described in detail with reference to the accompanying drawings.

[0025] figure 1 It shows the simulation platform of the rod control system of the pressurized water reactor nuclear power plant in some embodiments of the present invention, which is used to analyze the cause of failure of the rod control system equipment of the nuclear power plant, and provides a test platform for the development and copying of key boards and cards of the nuclear power plant and Conduct skill training for maintenance personnel on the rod control system. The simulation platform of the rod control system of a nuclear power plant in some embodiments of the present invention adopts a host computer and a lower computer structure. The upper computer is a logic cabinet 30, and the lower computer is a power ca...

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Abstract

The invention discloses a simulation platform for a rod control system of a pressurized water reactor nuclear power station. The simulation platform comprises a simulation and data acquisition cabinet, wherein the simulation and data acquisition cabinet comprises a simulation unit and a data acquisition unit, and the simulation unit outputs a simulation signal; the data acquisition unit acquires a process signal; a manual control console simulates a master control room and outputs a control signal; a logic cabinet produces a rod position movement command; a power cabinet comprises a circulatory monitoring logic unit and a silicon controlled rectifier circuit, and the circulatory monitoring logic unit controls the silicon controlled rectifier circuit to output a coil running signal; a load simulation cabinet simulates lifting and thrusting actions of a control rod according to the coil running signal; and a distribution box is used for power distribution of all the other cabinets. As the simulation platform for the rod control system of the nuclear power station comprises all typical equipment of the rod control system, on-site equipment failure analysis and maintenance of the rod control system, functional verification and burning of key equipment, and technical training and software and hardware operation training of on-site maintenance personnel of the rod control system are realized.

Description

technical field [0001] The invention relates to the field of rod control systems in nuclear power plants, in particular to a simulation platform for rod control systems in nuclear power plants. Background technique [0002] Control rod control system (referred to as rod control system) is one of the main reactor control systems. Its main function is: according to the change of grid load, the system correspondingly raises or inserts control rods to adjust the reactivity of the reactor core, thereby controlling the core temperature and Nuclear power, enabling reactor control in G-mode. When the reactor is in an unstable operating condition, the control rod control system can also bring the reactor from zero power to full power during the reactor start-up phase and perform shutdown during the normal shutdown phase or emergency shutdown in case of an accident to protect the reactor. Ensure core safety. The rod control system mainly includes three parts, which are rod control l...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00G21D3/00G09B25/02
CPCG09B25/02G21C17/001G21D3/001G21D3/002Y02E30/00Y02E30/30
Inventor 刘美军王斌高夫领李生茂张军娄毅孙波陈毓犹代伦董国印沙洪伟邵帅李强
Owner CHINA GENERAL NUCLEAR POWER OPERATION
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