Normal afterheat discharging pump for third-generation AP1000 advanced pressurized water reactor nuclear power station

A technology for pressurized water reactor nuclear power plant and waste heat removal, which is applied to the components, pumps, and pump components of the pumping device for elastic fluids, which can solve the problem that the pump body and the motor cannot meet the requirements of regular and rapid maintenance and replacement of parts. Can not meet the requirements of the leakage rate of nuclear power plants, can not ensure the integrity of the pressure boundary and other problems, to achieve reliable long-term operation, simple structure, improve the effect of smoothness

Inactive Publication Date: 2014-05-28
DALIAN DEEP BLUE PUMP CO LTD +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] First: Under high-pressure working conditions, the mechanical seal of the pump is damaged, which cannot meet the leakage rate requirements of nuclear power plants;
[0005] Second: In the operating environment under high temperature and thermal conditions, the stable and reliable long-term operation of the bearing cannot be guaranteed;
[0006] Third: In the harsh irradiation environment, the integrity of the pressure boundary cannot be guaranteed;
[0007] Fourth: The pump body and motor need to be disassembled when maintaining the bearing components, which cannot meet the requirements of regular and rapid maintenance and replacement of parts

Method used

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  • Normal afterheat discharging pump for third-generation AP1000 advanced pressurized water reactor nuclear power station
  • Normal afterheat discharging pump for third-generation AP1000 advanced pressurized water reactor nuclear power station
  • Normal afterheat discharging pump for third-generation AP1000 advanced pressurized water reactor nuclear power station

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Embodiment Construction

[0029] The present invention will be described in further detail below in conjunction with the accompanying drawings.

[0030] as attached figure 1 As shown, the three generations of AP1000 advanced pressurized water reactor nuclear power plant stack type provided by the present invention use the normal residual heat removal pump, as attached figure 1 As shown, the pump is a vertical, single-stage, single-suction, cantilever, and radially split structure. The working medium is sucked in from the bottom of the pump and discharged horizontally. The main components of the pump include a discharge chamber cover plate 1, an impeller 2, a pump body 3, a discharge chamber 4, a pump cover 5, a throat bush 6, a sealing member 7, a pump shaft 8, an intermediate connecting section 9, and a bearing 10. Bearing box 11, bearing box body 12, bearing forced cooling structure 13 and coupling etc. An impeller is installed in the pump body, the pump shaft is connected to the motor through a ...

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Abstract

The invention relates to a normal afterheat discharging pump applicable to an advanced pressurized water reactor nuclear power station adopting third-generation AP1000. Major components of the normal afterheat discharging pump for a third-generation AP1000 advanced pressurized water reactor nuclear power station comprise a press-out chamber cover plate, an impeller, a pump body, a press-out chamber, a pump cover, a throat bushing, a sealing component, a bearing forced cooling structure and a shaft coupler, wherein the throat bushing is arranged on a pump shaft, and the upper part of a bearing component is provided with the bearing forced cooling structure. The normal afterheat discharging pump provided by the invention has the characteristics that the structure is simple, safe and reliable, the efficiency is high, the integral anti-seismic performance is good, and the maintenance is convenient and fast; the requirements of high-temperature, high-voltage and severe radiation environment of power plants and strong seismic oscillation can be met.

Description

technical field [0001] The invention relates to a vertical cantilever pump, in particular to a normal residual heat removal pump suitable for a power plant adopting AP1000 nuclear power technology. Background technique [0002] The normal waste heat export pump in the power plant using AP1000 nuclear power technology is one of the important equipment in the normal waste heat export system of this type of nuclear power plant. The aforementioned normal waste heat removal pump is a nuclear safety three-level pump, located in the auxiliary building of the power plant, and performs the function of removing waste heat in the reactor coolant system during the normal shutdown of the power plant, and plays an important role in the safe operation of a class of power plants using AP1000 nuclear power technology. [0003] At present, there are deficiencies in the technology of ordinary water pumps in China: [0004] First: Under high-pressure working conditions, the mechanical seal of...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): F04D29/043F04D29/046
Inventor 尹贤圆邹颖男张化川宋英东罗扬
Owner DALIAN DEEP BLUE PUMP CO LTD
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