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Nuclear power plant steam-driven pump rotating speed sensor cross comparison system and method

A speed sensor, cross-comparison technology, applied in nuclear power generation, speed/acceleration/shock measurement equipment testing/calibration, instruments, etc., can solve the problem that two or more speed sensors cannot be calibrated, and the governor has no signal storage record and other issues, to achieve the effect of improving independent maintenance capabilities, improving reliability, and improving efficiency

Active Publication Date: 2020-05-22
CNNC FUJIAN FUQING NUCLEAR POWER
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  • Summary
  • Abstract
  • Description
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AI Technical Summary

Problems solved by technology

[0004] Since the two speed signals are not directly connected to the control system of the whole plant, and the governor has no signal storage and recording function, it is impossible to diagnose the fault of the steam-driven pump through online monitoring of the speed signals
[0005] The traditional speed sensor calibration platform can only calibrate a single sensor, and cannot calibrate two or more speed sensors at the same time

Method used

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  • Nuclear power plant steam-driven pump rotating speed sensor cross comparison system and method
  • Nuclear power plant steam-driven pump rotating speed sensor cross comparison system and method

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Embodiment Construction

[0036] The present invention will be further described below in conjunction with accompanying drawing and specific embodiment:

[0037] The preferred embodiments of the present invention will be described below in conjunction with the accompanying drawings. It should be understood that the preferred embodiments described here are only used to illustrate and explain the present invention, and are not intended to limit the present invention.

[0038] A cross-comparison system for the speed sensor of a steam-driven pump in a nuclear power plant. The system is centered on the signal terminal block 1, and the 380V power supply 2 supplies power to the motor 3. The motor 3 receives the signal from the signal terminal block 1 at the same time, so that it is control;

[0039] The motor 3 is connected to the speed cross comparison device 4, and the speed cross comparison device 4 is connected to the signal terminal block 1 to receive the signal transmitted by the signal terminal block 1...

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Abstract

The invention belongs to the technical field of instrument calibration, operation and maintenance, and particularly relates to a nuclear power plant steam-driven pump rotating speed sensor cross comparison system and method. According to the invention, off-line cross comparison is carried out on a rotating speed sensor of a steam-driven pump, the performance change and difference of the rotating speed sensor can be known in advance, targeted pre-maintenance measures can be taken, the overhaul and maintenance efficiency of the steam-driven pump is improved, the equipment reliability is improved, and after the device is put into use, spare part testing, machine copying, personnel training and personnel autonomous overhaul capacity improvement can be achieved.

Description

technical field [0001] The invention belongs to the technical field of instrument calibration and operation and maintenance, and in particular relates to a system and method for cross-comparison of rotational speed sensors of steam-driven pumps in nuclear power plants. Background technique [0002] As one of the special safety facilities for nuclear power plants, the steam-driven pump ensures that steam can still be used as power to export core heat in the event of a power failure in the nuclear power plant. It is an important safety barrier for nuclear power plants. The speed of the steam-driven pump is not only an important indicator of the operation performance of the steam-driven pump, but also the input signal of the steam-driven pump control system. Failure or fluctuation of the speed signal will cause the steam-driven pump to skip the pump, seriously affecting the safety and stability of the nuclear power unit. [0003] The control scheme of the steam-driven pump is t...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01P21/02G21D3/08
CPCG01P21/02G21D3/08Y02E30/00
Inventor 郑健伟李洪王东祥王冲徐震商海龙万舒李晓振陈烨王向阳梁鑫姚路锋
Owner CNNC FUJIAN FUQING NUCLEAR POWER
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