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Nuclear power plant reactor protection system plate test method, platform, device and terminal

A technology for a nuclear power plant reactor and a protection system is applied in the field of nuclear power plant reactor protection system board testing and computer-readable storage media, which can solve the problem that boards cannot be tested offline, and achieve the effect of positioning

Active Publication Date: 2019-04-19
LINGAO NUCLEAR POWER +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] In view of this, an embodiment of the present invention provides a method, device, platform, processing terminal, and computer-readable storage medium for testing a panel of a reactor protection system in a nuclear power plant, so as to solve the problem that the panels of the reactor protection system of a nuclear power plant cannot be tested offline

Method used

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  • Nuclear power plant reactor protection system plate test method, platform, device and terminal
  • Nuclear power plant reactor protection system plate test method, platform, device and terminal
  • Nuclear power plant reactor protection system plate test method, platform, device and terminal

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Embodiment 1

[0072] The following embodiment will describe the specific structure of the test platform for the reactor protection system of the nuclear power plant.

[0073] See figure 1 , is a schematic block diagram of the structure of the nuclear power plant reactor protection system board test platform provided by the embodiment of the present invention, the platform may include a data processing module 11, a data acquisition module 12 connected to the data processing module 11, and a signal connected to the data acquisition module 12 The transition module 13, the signal isolation module 14 connected to the signal transition module 13, and at least one slot 15 connected to the signal isolation module 14; the slot is used for installing the board to be tested. Optionally, a human-computer interaction module 16 connected to the data processing module 11 may also be included. The data acquisition module includes at least one data acquisition card, and the signal conversion module include...

Embodiment 2

[0088] In order to better introduce the nuclear power plant reactor protection system panel test platform provided by the embodiment of the present invention, the following will combine figure 2 An exemplary architecture diagram of the nuclear power plant reactor protection system panel test platform shown is introduced.

[0089] Such as figure 2 As shown, the platform includes the tested board, signal isolation layer, signal transfer layer, NI PXIe-1065 chassis, and PC. The signal transfer layer includes three different types of junction boxes: TBX-50B, SCB-68A, and SCB-100, and the signal isolation layer includes a current and voltage selection switch box and a signal isolator. NI PXIe-1065 is a chassis model, which includes a real-time controller model PXIe-8840RT, and the right side of the controller is a data acquisition card. Labview software is installed on the PC. The PC can be connected to the controller in the chassis through the network cable, and the controlle...

Embodiment 3

[0098]After introducing the structure of the nuclear power plant reactor protection system board test platform, the following will introduce the nuclear power plant reactor protection system board test method, which is specifically executed by the processing terminal in the nuclear power plant reactor protection system board test platform.

[0099] See image 3 , is a schematic flowchart of a test method for a nuclear power plant reactor protection system panel provided by an embodiment of the present invention. The nuclear power plant reactor protection system panel test method is applied to any one of the nuclear power plant reactor protection system panel test platforms described above. The nuclear power plant reactor protection system panel testing method may include the following steps:

[0100] Step S301, acquiring test parameters.

[0101] It should be noted that the above test parameters can be specifically configured by the user through the Labview software, or can b...

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Abstract

The embodiment of the invention relates to the technical field of nuclear power plant reactor protection systems, and discloses a nuclear power plant reactor protection system plate test platform, method and device, a terminal and a storage medium. The method includes the steps of obtaining test parameters, generating a test signal according to the test parameters; injecting the test signal into ato-be-tested plate, and testing the to-be-tested plate; receiving an output feedback signal of the to-be-tested plate through a data acquisition module; and obtaining a test result of the to-be-tested plate according to the output feedback signal. The embodiment of the invention discloses a nuclear power station reactor protection system plate test platform. A test signal is injected into a to-be-tested plate according to test parameters, an output feedback signal of the to-be-tested plate is received, and a test result is obtained according to the output feedback signal to realize offline test of the nuclear power plant reactor protection system plate, thereby realizing plate fault reason positioning, plate performance detection or plate reliability test.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant reactor protection systems, and in particular relates to a test method, device, platform, processing terminal and computer-readable storage medium for a nuclear power plant reactor protection system board. Background technique [0002] At present, the reactor protection system RPR of the nuclear power plant receives the switching signal sent by the upstream KRG, RPN and other systems, and after logical operation, it gives protection signals such as emergency shutdown of the reactor and activation of special safety facilities. That is, the RPR system monitors the operation of the reactor in real time, and according to the change of the operating parameters, it controls the emergency shutdown of the reactor and the action of special safety facilities through its logic to prevent the state of the reactor from exceeding the specified safety limit, which is directly related to nuclear safety...

Claims

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Application Information

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IPC IPC(8): G01R31/28
CPCG01R31/2855
Inventor 王正斌曹才李广森季涛易函平
Owner LINGAO NUCLEAR POWER
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