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A large-scale nuclear power double-bundle steam-water separation reheating device

A steam-water separation and reheating device technology, applied in separation methods, dispersed particle separation, chemical instruments and methods, etc., can solve the problems of low heat transfer performance, complex structure, low efficiency, etc., to improve heat transfer performance and improve operation Power, the effect of increasing economy

Active Publication Date: 2011-12-07
HARBIN TURBINE +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] In order to solve the problems of low efficiency, low heat transfer performance and complex structure of the existing steam-water separation and reheating device of nuclear power units, the present invention further proposes a large-scale nuclear power double-tube bundle steam-water separation and reheating device

Method used

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  • A large-scale nuclear power double-bundle steam-water separation reheating device
  • A large-scale nuclear power double-bundle steam-water separation reheating device
  • A large-scale nuclear power double-bundle steam-water separation reheating device

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specific Embodiment approach 1

[0007] Specific implementation mode one: as Figure 1-2 As shown, the steam-water separation and reheating device described in this embodiment includes a large-scale nuclear power double-tube bundle, three-intake and four-support steam-water separation and reheating device includes a housing 1, and also includes a two-stage reheater tube bundle 2 and a steam-water separation element 3. The two-stage reheater The tube bundle 2 includes a set of U-shaped heat exchange tubes 2-1 with fins and a set of support plates 2-2, and a set of U-shaped heat exchange tubes 2-1 with fins are coaxially arranged to form a tube bundle. Pass through a group of support plates 2-2 in turn, and each support plate 2-2 is fixedly connected to the tube bundle. The steam-water separation element 3 includes an upper baffle 3-1, a lower baffle 3-2, and several corrugated plates 3 -3 and several water drop catching hooks 3-4, the upper baffle 3-1 and the lower baffle 3-2 are arranged side by side in paral...

specific Embodiment approach 2

[0008] Specific implementation mode two: as Figure 4-5 As shown, the profile of the hook head of each water droplet catching hook 3-4 of a large-scale nuclear power double-bundle steam-water separation and reheating device described in this embodiment is consistent with the shape of the outer surface of the wave crest or wave trough of the corrugated plate 3-3. Other components and connections are the same as those in the first embodiment.

specific Embodiment approach 3

[0009] Specific implementation mode three: as Figure 4-5 As shown, the lower baffle 3-2 of a large-scale nuclear power double-bundle steam-water separation and reheating device described in this embodiment is provided with a drain port 3-5. Other components and connections are the same as those in the first embodiment.

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Abstract

The invention relates to a steam-water separating and reheating device, in particular to a large nuclear power double-pipe bundle steam-water separating and reheating device. The invention aims to solve the problems of low efficiency and heat transfer property and complex structure of the traditional steam-water separating and reheating device of a nuclear power unit. The large nuclear power double-pipe bundle steam-water separating and reheating device comprises a shell, a two-stage reheater pipe bundle and a steam-water separation element, wherein the two-stage reheater pipe bundle comprises a group of U-shaped heat exchange pipes with fins and a group of supporting plates, the group of U-shaped heat exchange pipes with fins are coaxially arranged to form a pipe bundle, the pipe bundle sequentially passes through the group of supporting plates, the steam-water separation element comprises an upper baffle plate, a lower baffle plate, a plurality of corrugated plates and a plurality of water-drop gathering hooks, a plurality of wet steam inlets are arranged on the lower surface of the shell, a plurality of wet steam outlets are arranged on the upper surface of the shell, and a shell dewatering outlet is arranged on the lower surface of the shell. The large nuclear power double-pipe bundle steam-water separating and reheating device is used for dewetting and reheating wet steams discharged by a high pressure cylinder of a nuclear power turboset.

Description

technical field [0001] The invention relates to a steam-water separation and reheating device, in particular to a large-scale nuclear power double-tube bundle steam-water separation and reheating device. Background technique [0002] All existing nuclear power plant saturated steam turbine units need to be equipped with a steam-water separation and reheating device. The steam-water separation and reheating device receives the exhaust gas from the high-pressure cylinder of the steam turbine, removes the moisture in the wet steam and reheats it, and then discharges the superheated steam to the low-pressure cylinder of the steam turbine. , the steam after dehumidification and reheating can protect the blades of the low-pressure cylinder of the steam turbine and ensure the safe operation of the unit. At the same time, it will also greatly increase the power of the unit and increase the economy of the unit. Large loss, low heat transfer performance, complex structure. Contents ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01D45/08
Inventor 杨镇海董爱华付元刚武君郭民
Owner HARBIN TURBINE
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