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Leakage abnormity processing system and method for main pump of nuclear power station

An abnormality handling system and abnormality handling technology, which is applied in nuclear power plant auxiliary equipment, nuclear power generation, power plant safety devices, etc., can solve the problem of sufficient exhaust of the main pump No. 2 shaft seal leakage pipeline, etc.

Active Publication Date: 2019-11-22
LINGAO NUCLEAR POWER +5
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  • Claims
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AI Technical Summary

Problems solved by technology

[0005] The embodiment of the present invention provides a system and method for abnormal leakage of the main pump of a nuclear power plant to solve the problem of simply realizing the sufficient exhaust of the leakage pipeline of the No. 2 shaft seal of the main pump

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  • Leakage abnormity processing system and method for main pump of nuclear power station

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Embodiment Construction

[0027] The following will clearly and completely describe the technical solutions in the embodiments of the present invention with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are some of the embodiments of the present invention, but not all of them. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without creative efforts fall within the protection scope of the present invention.

[0028] The fluctuation problem of narrow-range flowmeter leakage of the No. 2 shaft seal of the 100-type main pump is a common problem of this type of main pump, and some fluctuations or even flashes of high leakage flow alarms. After analyzing the changes in the leakage flow of the No. 1 seal and other parameters, it is confirmed that The fluctuations shown in the figure are all false fluctuations.

[0029] Such as figure 2 As shown, the flow chart ...

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Abstract

The invention relates to the technical field of nuclear power station primary loop main pumps. The invention discloses leakage abnormity processing system and method for a main pump of a nuclear powerstation. The system comprises a main controller, a nuclear power station main pump and a liquid collection tank, wherein the nuclear power station main pump comprises a second shaft seal and includesa leakage pipeline which is used for connecting the second shaft seal with the liquid collecting tank; an impurity isolation valve is arranged on the side, close to the second shaft seal, of the leakage pipeline. At least one water filling isolation valve is arranged on the leakage pipeline between the impurity isolation valve and the liquid collection tank; the liquid collecting tank is providedwith a water supplementing isolating valve used for controlling reverse water filling and exhausting, and the main controller is used for controlling the water supplementing isolating valve and at least one water filling isolating valve to be opened when the impurity isolating valve is closed, so that reverse water filling and exhausting can be conducted on the leakage pipeline through the liquidcollecting tank. According to the system, the liquid collection tank can be used for fully and reversely filling water into the leakage pipeline for exhausting, and meanwhile, impurities in the liquid collection tank can be isolated through the impurity isolation valve.

Description

technical field [0001] The invention relates to the technical field of a main pump of a primary circuit of a nuclear power plant, in particular to a system and method for handling abnormal leakage of a main pump of a nuclear power plant. Background technique [0002] The No. 2 shaft seal of the 100 type main pump is a friction surface type shaft seal, which consists of a graphite-coated stainless steel static ring and a stainless steel moving ring with a sprayed chromium carbide coating that rotates with the shaft, such as figure 1 shown. The function of the No. 2 shaft seal is to block the leakage water of the No. 1 shaft seal and guide it to flow back to the RCV (Chemical and Volume Control System) system. The static ring is pressed against the moving ring by liquid pressure and spring force, and the friction surface between the moving and static rings is lubricated and cooled by a small part of the leakage flow of the No. 1 shaft seal. The normal leakage through the No....

Claims

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Application Information

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IPC IPC(8): G21D1/02G21D3/06
CPCG21D1/02G21D3/06Y02E30/00
Inventor 岑相成侯晔何继强陈士强代东亮
Owner LINGAO NUCLEAR POWER
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