Nuclear power station steam generator cooling system

Abstract

The invention relates to the technical field of nuclear power station steam generator cooling, in particular to a nuclear power station steam generator cooling system, which is characterized in that a pressure reduction and temperature reduction pipeline is led out from an outlet end of a steam generator and is connected to an inlet of the steam generator, and a pressure reduction valve and a water spray temperature reduction device are arranged on the pressure reduction and temperature reduction pipeline; and an electric boiler, a steam superheater and a steam booster pump are arranged on the auxiliary steam pipeline. And when a single reactor is shut down emergently, main steam generated by the steam generator in normal operation is subjected to temperature and pressure reduction and is introduced into the steam generator corresponding to the emergency shut down for cooling. When the double reactors are shut down emergently, the auxiliary steam generated by the electric boiler is heated and boosted to be respectively introduced into the two steam generators for cooling, and the unit is restarted for grid-connected power generation until the steam generators are cooled to the feed water temperature, so that the cooling time of the steam generators can be greatly shortened, and the unit can perform grid-connected power generation again in a relatively short time; the operation efficiency of the nuclear power station is improved.

Description

technical field [0001] The invention relates to the technical field of cooling of steam generators in nuclear power plants, in particular to a cooling system for steam generators in nuclear power plants. Background technique [0002] When the high-temperature gas-cooled reactor is running at full power, the temperature at the tube sheet at the outlet of the steam generator is as high as 540°C. At this time, the reactor is shut down in an emergency. If the feed water at 180°C enters the steam generator directly, the tube sheet at the outlet of the steam generator will suffer from transient heat. The impact may easily cause the weld seam between the heat transfer tube and the outlet tube plate to fall off and tear, and damage the steam generator. Therefore, it is necessary to cool the outlet tube sheet of the steam generator to a temperature close to that of the feed water before feeding the feed water. [0003] At the same time, due to the special structure of the once-throu...

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Problems solved by technology

[0004] Therefore, the technical problem to be solved by the present invention is to overcome the defects in the prior art that the high-temperature gas-cooled reactor needs to be cooled for a long time before it can be re-connected to the grid for power generation after shutdown, which affects the operating efficiency of the high-temperature gas-cooled reactor. Thereby providing a nuclear power plant steam generator cooling system

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