A device and method for adjusting the speed of a steam-driven main feedwater pump in a nuclear power plant

Abstract

The invention provides a rotating speed regulating device for a steam-driven main feed water pump of a nuclear power station; the rotating speed regulating device comprises a regulating control unit,a rotating speed preset unit, a rotating speed collection unit, an operating state collection unit, a starting command collection unit and a drive unit, wherein the rotating speed preset unit receives the theoretical rotating speed preset to the steam-driven main feed water pump; the rotating speed collection unit acquires the actual rotating speed of the steam-driven main feed water pump; the operating state collection unit acquires the real-time temperature of the steam-driven main feed water pump; the starting command collection unit acquires a starting mode command issued by an user; theregulating control unit determines the current working stage of the steam-driven main feed water pump according to the actual rotating speed and the real-time temperature, and further selects the starting mode command or the theoretical rotating speed to realize the starting and / or rotating speed control of the steam-drive main feed water pump. The rotating speed regulating device and the method provided by the invention have the characteristics of flexible adjustment mechanism, high maintainability and fast system response, and can realize safe start control and smooth operation control of the steam-driven main feed water pump.

Description

technical field [0001] The invention relates to the technical field of steam-driven main feed water pumps in nuclear power plants, in particular to a device and method for adjusting the speed of steam-driven main feed water pumps in nuclear power plants. Background technique [0002] In the process system design of nuclear power plants, the feed water flow control system (ARE) controls the water demand of the secondary circuit of the entire nuclear power plant. The feed water flow control system changes the feed water flow and pressure based on the speed adjustment of the steam-driven main feed water pump, realizes the water supply to the three steam generators, and eliminates the feed water coupling phenomenon between the three steam generators to ensure the supply of the steam generators. The pressure difference between the jellyfish pipe and the steam main pipe is equal to the setting value of a random group load change, so the speed adjustment of the steam-driven main fe...

AI Technical Summary

Problems solved by technology

[0003] However, at present, most of the steam-driven main feedwater pump speed adjustments of domestic and foreign nuclear power generating units are realized by the adjustment devices designed by the feed pump manufacturers. However, the adjustment devices designed by the existing manufacturers have backward technology and adjustment mechanisms Stiffness, poor maintainability, slow system response and other characteristics, resulting in poor control over the start-up control and stable operation of the steam-driven main feed water pump

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