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A speed control system and method for a steam-driven main feedwater pump of a nuclear power plant

A main feed pump and speed control technology, applied in the field of nuclear power plants, can solve the problems of poor human-computer interaction, poor adjustment accuracy, and many fault points, and achieve the effects of optimizing reliability, improving speed adjustment speed, and improving accuracy.

Active Publication Date: 2020-08-21
CHINA NUCLEAR POWER TECH RES INST CO LTD +4
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] The on-load speed regulation subsystem of the above-mentioned electrical converter (EP) plus mechanical speed governor has complex structure, problems such as poor adjustment accuracy, slow response, difficult debugging, many fault points, difficult troubleshooting, poor human-computer interaction, etc.

Method used

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  • A speed control system and method for a steam-driven main feedwater pump of a nuclear power plant
  • A speed control system and method for a steam-driven main feedwater pump of a nuclear power plant
  • A speed control system and method for a steam-driven main feedwater pump of a nuclear power plant

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Embodiment Construction

[0044] The present invention provides a speed control system for steam-driven main feedwater pump 4 of a nuclear power plant, such as figure 2 As shown, the speed control system includes: a digital controller 1 , a protection trip circuit 8 , a driver 2 , an actuator 3 and two speed sensors 5 .

[0045] The two rotational speed sensors 5 are used to respectively collect the rotational speed of the steam-driven main feedwater pump 4 , generate corresponding rotational speed pulse signals, and send the rotational speed pulse signals to the digital controller 1 .

[0046] The digital controller 1 is used to determine the measured rotational speed value of the steam-driven main feedwater pump 4 according to the two rotational speed pulse signals corresponding to the two rotational speed sensors 5, and generate a corresponding The control signal, and the control signal is sent to the driver 2.

[0047] The driver 2 is used to generate a corresponding driving current according to ...

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Abstract

The invention provides a rotating speed control system and method for a nuclear power station seam-driven main water feeding pump. The system comprises a digital controller, a protection trip circuit,a driver, an actuator and two rotating speed sensors, the two rotating speed sensors respectively collect the rotating speed of the seam-driven main water feeding pump, generate corresponding rotating speed pulse signals and output the rotating speed pulse signals to the digital controller. The digital controller determine the practically-measured rotating speed value of the seam-driven main water feeding pump according to the two rotating speed pulse signals corresponding to the two rotating speed sensors, generates corresponding control signals according to the practically-measured signalsand given rotating speed signals and transmits the control signals to the driver. The driver generates corresponding driving current according to the control signals and feedback signals of the actuator, and outputs the driving current to the actuator to drive the actuator to act, so that the opening of a steam adjusting valve is adjusted. Rotating speed adjusting precision of the seam-driven mainwater feeding pump can be improved, and reliability of the rotating speed control system is optimized.

Description

technical field [0001] The invention relates to the technical field of nuclear power plants, in particular to a speed control system and method for a steam-driven main feed water pump of a nuclear power plant. Background technique [0002] In the process system design of nuclear power plants, the main water supply system is used to supply water to the steam generator, ensuring that the pressure difference between the feed water main pipe and the steam main pipe of the steam generator is equal to a set value of a random load change, so as to maintain the feed water flow control The differential pressure before and after the system regulating valve is approximately constant, which meets the water supply flow requirements of the steam generator. The main feedwater flow control of the evaporator is a cascaded PID closed-loop regulation system, and its inner loop is a PID control system with the speed of the steam-driven main feedwater pump as the control target. In the cascade ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): F04D15/00F04D15/02F01D17/00
CPCF01D17/00F04D15/0066F04D15/0077F04D15/0281F05D2260/80F05D2270/02F05D2270/304F05D2270/706
Inventor 杨壮豪杨林山李大伟吕跃跃熊国华王洪涛赵东升孙跃张天航
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD