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A Periodic Test Device for Protection System of PWR Nuclear Power Plant

A technology of protection system and regular test, applied in general control system, control/regulation system, electrical testing/monitoring, etc. It can solve the problem of lack of injection signal readback function, inability to judge injection signal quality, and no on-site parameter calculation, etc. problems, to achieve the effect of reliable test results, guaranteed reliability and safe operation

Active Publication Date: 2019-04-09
CHINA TECHENERGY +1
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  • Abstract
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  • Application Information

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Problems solved by technology

Currently known methods and equipment for performing periodic tests on the PWR nuclear power plant protection system can only perform a single protection channel test at the same time, and the verification criterion is only the voltage criterion; in addition, the existing test equipment does not have injection The readback function of the signal, without the readback function, it is impossible to judge the quality of the injected signal, so if the injected signal is abnormal, it is impossible to judge whether the test is reliable; in addition, the existing test device does not have the function of local parameter calculation

Method used

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  • A Periodic Test Device for Protection System of PWR Nuclear Power Plant
  • A Periodic Test Device for Protection System of PWR Nuclear Power Plant
  • A Periodic Test Device for Protection System of PWR Nuclear Power Plant

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Embodiment Construction

[0056] This test device (KRG-TESTER) is designed to verify the important analog channel acquisition and processing system of the pressurized water reactor nuclear power plant. test. The function of the test device is to check the availability of the KRG system protection measurement channel during reactor operation. The test device provides an analog signal as close to the actual as possible, and injects the analog signal into the protection system. By checking whether the signal conversion error, whether the threshold relay operates, and whether the action threshold error meets the design requirements, etc., it is judged whether the KRG system protection measurement channel is Fault occurs, therefore, the regular test of KRG is divided into three parts: verification protection channel threshold module XU test (Channel test), display channel test from KRG system to main control room (PAMS test) and dynamic module test of protection channel (Step by Step test).

[0057] When ...

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Abstract

The invention provides a periodic test device for a pressurized water reactor nuclear power plant protection system, which comprises a real-time control system, and a computer in network connection with the real-time control system for executing a human-computer interaction function. The real-time control system is an embedded controller and comprises a central processor and multiple synchronous data communication channels, and the real-time control system is connected with a tested channel of the protection system via the synchronous data communication channels. When the test is executed, the computer provides a test signal and issues a test instruction, and the real-time control system injects the test signal to the tested channel of the protection system via the synchronous data communication channels, executes the test instruction issued by the computer, acquires a test result, and feeds the test result back to the computer. The test device also comprises a self-inspection and annual inspection device which periodically executes self-inspection on the real-time control system and annual inspection on precision verification of analog input and output channels.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant safety measurement and control, in particular to a periodic test device for a protection system of a pressurized water reactor nuclear power plant. Background technique [0002] The instrument control system is the nervous system of the nuclear power plant, which is directly related to the safe, reliable and stable operation of the nuclear power plant. The KRG system is a centralized control analog system, which is the key system of the instrument control system of the nuclear power plant. Its function defines the output from the on-site sensor, The input signal to the reactor protection system (RPR system), after the signal is processed in the KRG system (including square extraction, linearization, filtering, differentiation, lead-lag, etc.), threshold comparison is performed, when the signal exceeds the set limit After the value is set, the protection signal will be triggered and sen...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G05B23/02
CPCG05B23/0208
Inventor 李景志刘旭东张红梅彭帅国汪波汪海艳孙洪涛郑伟智宋立新
Owner CHINA TECHENERGY
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