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

A protection system and periodic test technology, applied in the direction of measuring electricity, measuring electrical variables, instruments, etc., can solve the problems of not having the readback function of the injected signal, the inability to judge the quality of the injected signal, and no local parameter calculation, etc., to achieve the test results The effect of reliability, ensuring effectiveness, and safe operation of the device

Active Publication Date: 2019-03-15
CHINA TECHENERGY +1
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

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

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Embodiment Construction

[0060] This test device (KRG-TEST) 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).

[0061] When th...

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Abstract

The invention provides a periodic test system for protection systems for pressurized water reactor nuclear power plants. The periodic test system comprises an upper computer system and a lower computer system. Database in the upper computer system are managed, so that data required by tests can be provided; each channel test comprises at least one test, each test corresponds to a function module, the corresponding function modules are called when the channel tests are executed, then the data which correspond to the function modules and are required by the tests are called from the databases and are transmitted to the lower computer system via networks, and instructions for executing the function modules are transmitted to the lower computer system; the lower computer system comprises test items corresponding to the function modules of the channel tests, and the corresponding test items are executed when the instructions transmitted by the upper computer system are received by the lower computer system.

Description

technical field [0001] The invention belongs to the technical field of safety protection systems of nuclear power plants, in particular to a periodic test system for the protection systems of pressurized water reactor nuclear power plants. 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 se...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01R31/00
Inventor 汪海艳汪波刘旭东李景志彭帅国张红梅宋立新曹宗生
Owner CHINA TECHENERGY
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