Corrugated plate for nuclear power plant reactor cooling loop

CN224841286UActive Publication Date: 2026-10-09JIANGSU SEAGATE NEW ENERGY ENG TECH CO LTD
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Patent Information

Application Number
CN202521784662.2
Authority / Receiving Office
CN · China
Patent Type
Utility models(China)
Current Assignee / Owner
Filing Date
2025-08-21
Publication Date
2026-10-09
Estimated Expiration
2035-08-21

AI Technical Summary

Technical Problem

然而竖向的波纹板进行汽水分离出现上下端分离效率差异大的问题

Benefits of technology

1.通过设置上部L型板和下部波纹板的结构,可增加蒸汽与板材的接触,提升蒸汽凝结成水的效率。

✦ Generated by Eureka AI based on patent content.

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Abstract

A kind of nuclear power plant reactor cooling loop corrugated plate, mainly used for nuclear power plant reactor steam water separation, including several horizontal connecting panel composition upper flat layer, triangular guide vane, distance frame, corrugated plate, water collecting pipe, upper flat layer and lower corrugated plate are formed hollow structure by distance frame at both ends;The upper surface of the flat layer is spliced by the long straight section of L-shaped plate, and the short handle section of L-shaped plate is inclined downward to the corrugated plate at the lower end;The trough area of the corrugated plate is provided with a through hole, and a horizontal long strip water collecting pipe is arranged below the corrugated plate outside the through hole.The device has the characteristics of simple structure and good steam-water separation effect.
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Description

Technical Field

[0001] This utility model relates to a steam-water separation device, specifically used for steam-water separation in nuclear power plant reactors. Background Technology

[0002] Steam generators are crucial equipment in pressurized water reactor nuclear power plants. Their task is to exchange heat between the primary and secondary cooling loops of the reactor, generating a certain quantity and quality of steam. The higher the steam humidity, the worse the steam quality. Therefore, steam-water separation devices are needed for steam-water separation. The performance of these devices is key to the entire system. Currently, many nuclear power plants use corrugated plate steam-water separators due to their wide contact area. However, further improving steam-water separation efficiency is a key research focus in this field.

[0003] An existing patent (application number: CN 201120214999.1) discloses a steam-water separation device for a megawatt-class nuclear power plant MSR, specifically a steam-water separation device for a megawatt-class nuclear power plant MSR. This invention aims to solve the problems of low steam-water separation efficiency, complex structural layout making manufacturing inconvenient, and high manufacturing costs associated with existing steam-water separation devices. This invention includes an upper baffle and a lower baffle, arranged parallel to each other from top to bottom and parallel to the horizontal plane. It also includes several corrugated plates and several water droplet capturing hooks. Each corrugated plate has a water droplet capturing hook installed on the outer surface of its crest and trough. The corrugated plates are arranged parallel to each other, with the upper end of each plate connected to the upper baffle and the lower end connected to the lower baffle. The plane of each corrugated plate is perpendicular to the upper and lower baffles. This invention is used to separate water droplets from the wet steam discharged from the high-pressure cylinder of a steam turbine. However, vertical corrugated plates cause a large difference in separation efficiency between the upper and lower ends when used for steam-water separation. Summary of the Invention

[0004] The purpose of this invention is to address the shortcomings of existing technologies by providing a simple-structured corrugated plate for steam-water separation in nuclear power plant reactor cooling and reuse, which offers excellent steam-water separation performance.

[0005] Specifically, it is implemented as follows: a corrugated plate for a nuclear power plant reactor cooling circuit includes an upper flat plate layer composed of several horizontally connected L-shaped plates, a triangular guide plate, a spacer frame, a corrugated plate, and a water collection pipe. The upper flat plate layer and the lower corrugated plate form a hollow structure through the spacer frame at both ends. The upper surface of the flat plate layer is spliced ​​from the long straight sections of the L-shaped plates, and the short stem sections of the L-shaped plates point obliquely downwards towards the lower corrugated plate. A through hole is provided in the trough area of ​​the corrugated plate, and a horizontal elongated water collection pipe is installed below the corrugated plate outside the through hole.

[0006] Steam enters horizontally into the hollow layer structure between the flat plate and the corrugated plate. Through contact with the plates of the upper and lower structures, the liquid film on the plate wall thickens and flows downward by gravity. Most of it is guided by the triangular guide plate to flow into the trough area of ​​the lower corrugated plate. After flowing out through the through holes, it flows into the water collection pipe for discharge, thus realizing steam-water separation.

[0007] Furthermore, a triangular guide plate is provided at the bend of the horizontally arranged L-shaped plates.

[0008] Furthermore, a rubber sealing gasket is provided at each end of the corrugated plate.

[0009] Furthermore, the corrugation angle of the corrugated plate is between 120 and 135 degrees.

[0010] Furthermore, the vertical distance between the highest point of the crest region and the lowest point of the trough region is between 1 and 1.5 centimeters.

[0011] Furthermore, the horizontal distance between the center vertical lines of adjacent corrugated plate crest areas is between 10 and 12 centimeters.

[0012] The beneficial effects of this utility model are: 1. By setting an upper L-shaped plate and a lower corrugated plate structure, the contact between steam and the plate can be increased, thereby improving the efficiency of steam condensation into water.

[0013] 2. Triangular guide plates are installed to guide the flow, so that the steam condensate can quickly collect and fall into the trough area of ​​the corrugated plate for collection.

[0014] 3. By adding multiple baffles, the condensed steam water can be easily collected and discharged. Attached Figure Description

[0015] Figure 1 This is a schematic diagram of the structure of the utility model.

[0016] Figure 2 This is a bottom view of the utility model.

[0017] In the diagram: 1 Flat plate, 1-1 L-shaped plate, 2 Triangular guide plate, 3 Spacing frame, 4 Corrugated plate, 4-1 Corrugated peak area, 4-2 Corrugated trough area, 5 Through hole, 6 Water collection pipe, 7 Rubber sealing gasket Detailed Implementation Example 1

[0018] like Figure 1 , Figure 2As shown, a corrugated plate for a nuclear power plant reactor cooling circuit includes an upper flat plate layer 1 composed of several horizontally connected L-shaped plates, a triangular guide plate 2, a spacer frame 3, a corrugated plate 4, and a water collection pipe 6. The upper flat plate layer 1 and the lower corrugated plate 4 form a hollow structure through the spacer frames 3 at both ends. The upper surface of the flat plate layer 1 is formed by splicing long straight sections of L-shaped plates 1-1. The short stem section of the L-shaped plates 1-1 points obliquely downwards towards the lower corrugated plate 2. The highest point of the crest region 4-1 of the corrugated plate 2 and the trough region... The vertical distance between the lowest points of 4-2 is between 1 and 1.5 cm, the corrugation angle of the corrugated plate 4 is between 120 and 135 degrees, the horizontal distance between the center vertical lines of the corrugated plate crest areas 4-1 of adjacent corrugated plates is between 10 and 12 cm, and a triangular guide plate 2 is provided at the bend of the horizontally arranged L-shaped plates 1-1; a through hole 5 is provided in the trough area 4-1 of the corrugated plate 4, and a horizontal elongated water collection pipe 6 is installed below the corrugated plate 4 outside the through hole; a rubber sealing gasket 7 is provided at each end of the corrugated plate 4.

[0019] Water vapor enters horizontally into the hollow layer structure between the flat plate layer 1 and the corrugated plate 4. Through contact with the upper and lower plates, the liquid film on the plate wall thickens and flows downward by gravity. Most of it is guided by the triangular guide plate 2 to flow into the trough area 4-1 of the lower corrugated plate 4. After flowing out through the through hole 5, it flows into the water collection pipe 6 for discharge, thus realizing the separation of steam and water.

Claims

1. A corrugated plate for a nuclear power plant reactor cooling circuit, comprising an upper flat plate layer composed of several horizontally connected profiled plates, a triangular guide plate, a spacer frame, a corrugated plate, and a water collection pipe, characterized in that: The upper flat plate layer and the lower corrugated plate form a hollow structure through the fixed-distance frame at both ends; the upper surface of the flat plate layer is spliced ​​from the long straight sections of L-shaped plates, and the short stem sections of the L-shaped plates point obliquely downwards towards the corrugated plate at the lower end; a through hole is provided in the trough area of ​​the corrugated plate, and a horizontal strip-shaped water collection pipe is installed below the corrugated plate outside the through hole.

2. The corrugated plate for a nuclear power plant reactor cooling circuit according to claim 1, characterized in that: A triangular guide plate is installed at the bend of the horizontally arranged L-shaped plates.

3. A corrugated plate for a nuclear power plant reactor cooling circuit according to claim 1, characterized in that: A rubber sealing gasket is provided at each end of the corrugated plate.

4. A corrugated plate for a nuclear power plant reactor cooling circuit according to claim 1, characterized in that: The corrugation angle of the corrugated sheet is between 120 and 135 degrees.

5. A corrugated plate for a nuclear power plant reactor cooling circuit according to claim 1, characterized in that: The vertical distance between the highest point of the crest and the lowest point of the trough is between 1 and 1.5 centimeters.

6. A corrugated plate for a nuclear power plant reactor cooling circuit according to claim 1, characterized in that: The horizontal distance between the center vertical lines of adjacent corrugated plate crest areas is between 10 and 12 centimeters.

Citation Information

Patent Citations

  • Steam-water separating device used for million-kilowatt-class nuclear power MSR (moisture separator reheater)

    CN202113704U