Corrugated plate for steam-water separation in nuclear power plant
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- JIANGSU SEAGATE NEW ENERGY ENG TECH CO LTD
- Filing Date
- 2025-07-01
- Publication Date
- 2026-08-07
AI Technical Summary
然而单层的分离效率略显不足
[0013] 1. By setting up upper and lower steam flow spaces, the contact area between steam and the plate is increased, achieving efficient steam-water separation.
Smart Images

Figure CN224607675U_ABST
Abstract
Description
Technical Field
[0001] This utility model relates to a steam-water separation device, specifically used for steam-water separation in nuclear power plants. Background Technology
[0002] In the operation of nuclear power plants, the steam system is a critical component. Excessive moisture in the steam can lead to water erosion of steam turbine blades, reducing turbine efficiency and service life, and can also cause corrosion of the piping system. Currently, Chinese nuclear power plants use corrugated plate steam-water separators, which are widely adopted due to their large contact area and good separation performance. How to further improve the structure to enhance steam-water separation efficiency is currently a hot research topic in this field.
[0003] An existing patent (application number: CN 201520263241.5) discloses a baffle plate assembly for a nuclear island steam separator dryer. The baffle plate assembly includes a baffle plate body and a heating device. The baffle plate body is made of a heat-conducting material, and the heating device is connected to the baffle plate body. The baffle plate body includes a corrugated plate and a water-blocking hook, with the corrugated plate welded to the water-blocking hook. This utility model's baffle plate assembly for a nuclear island steam separator dryer employs a design that heats the baffle plate, rapidly heating the water vapor containing a large amount of moisture generated by the steam generator before it enters the baffle plate of the vapor-liquid separator, evaporating the moisture and increasing the dryness of the water vapor. This reduces the moisture retained by the subsequent vapor-liquid separator, improving the efficiency of the nuclear island steam generator in producing dry steam. However, the separation efficiency of a single layer is slightly insufficient. Summary of the Invention
[0004] The purpose of this invention is to address the shortcomings of existing technologies by providing a corrugated plate device with a simple structure and good separation effect.
[0005] Specifically, it is implemented as follows: a corrugated plate for steam-water separation in a nuclear power plant includes a corrugated plate, a hook plate, and a water collection trough. The corrugated plate consists of three pieces, with two internal upper and lower steam flow channels formed by spacers at both ends. A hook plate is provided above the spacers at both ends, with the hook of the hook plate facing the middle of the corrugated plate. The corrugated plate has crest areas and trough areas. Each trough area is provided with a triangular guide plate in the shape of a triangular arrow. A guide line is connected to the arrow of the triangular guide plate, leading to a small hole in the trough area of the lower corrugated plate. A horizontal water collection trough is provided outside the trough area of the bottom layer of corrugated plate.
[0006] The water-containing dry steam flows horizontally into the interior of the upper and lower corrugated plates. Inside the corrugated plates, the steam forms a liquid film after contacting the plate wall and triangular guide plate, and then flows into the trough area. It then flows into the next layer through the fine holes. The steam and water collected in the trough area of the lowest corrugated plate flows out into the bottom water collection tank and is discharged.
[0007] Furthermore, the triangular guide plate is at an angle of 120-150 degrees to the horizontal steam entry direction.
[0008] Furthermore, the area of the triangular guide plate is between one-sixth and one-fifth of the vertical cross-section of two adjacent wave crest regions.
[0009] Furthermore, the connection angle between the crest and trough areas of the corrugated plate is set to an arc angle.
[0010] Furthermore, a set of rubber gaskets is provided at the bottom of both ends of the bottom corrugated plate to facilitate the installation and sealing of the corrugated plate.
[0011] Furthermore, a guide line is provided at the hook of the hook plate at both ends, and the guide line is led down to the fine hole on the corrugated plate 1 at the lower end.
[0012] The beneficial effects of this utility model are:
[0013] 1. By setting up upper and lower steam flow spaces, the contact area between steam and the plate is increased, achieving efficient steam-water separation.
[0014] 2. By setting up a tilting plate. Attached Figure Description
[0015] Figure 1 This is a schematic diagram of the structure of the utility model.
[0016] Figure 2 This is a top view of the device.
[0017] Figure 3 A bottom view of the device.
[0018] In the diagram: 1. Corrugated plate, 1-1. Crest area, 1-2. Trough area, 1-3. Triangular guide plate, 1-4. Fine hole, 2. Hook plate, 3. Drainage line, 4. Water collection trough, 5. Rubber pad, 6. Spacing frame Detailed Implementation Example 1
[0019] like Figure 1 , Figure 2 , Figure 3As shown, a corrugated plate for steam-water separation in a nuclear power plant includes a corrugated plate 1, hook plates 2, and a water collection tank 3. The corrugated plate 1 consists of three pieces, supported at both ends by spacers 6, forming two internal steam flow channels (upper and lower). A hook plate 2 is located above each of the spacers 6 at both ends, with the hooks of the hook plates 2 facing the center of the corrugated plate. A guide line 3 is located at the hook of each hook plate 2, leading down to a fine hole 1-4 on the lower corrugated plate 1. The corrugated plate 1 has crest areas 1-1 and trough areas 1-2, with an arc-shaped connection angle between the crest areas 1-1 and trough areas 1-2. Each trough area 1-2 has a triangular guide plate 1-3 with a triangular arrowhead shape. A guide line 3 is connected to the arrowhead of the triangular guide plate 1-2, leading down to a fine hole 1-4 in the lower corrugated plate trough area 1-2. The triangular guide plate 1-2 forms a 120-150 degree angle with the horizontal steam entry direction. The area of the triangular guide plate 1-2 is between one-sixth and one-fifth of the vertical cross section of the two adjacent crest areas 1-1; a horizontal water collection trough 4 is provided outside the trough area of the bottom corrugated plate 1, and a set of rubber pads 5 are provided at the bottom of both ends of the bottom corrugated plate 1 to facilitate the installation and sealing of the corrugated plate.
[0020] The water-containing dry steam flows horizontally into the interior of the upper and lower corrugated plates 1. Inside the corrugated plates 1, the steam forms a liquid film after contacting the plate wall and the triangular guide plates 1-3, and then flows into the trough area 1-2. It then flows into the next layer through the fine holes 1-4. The steam and water collected in the trough area 1-2 of the lowest corrugated plate 1 flows out into the bottom water collection tank 4 and is then discharged.
Claims
1. A corrugated plate for steam-water separation in nuclear power plants, comprising a corrugated plate, a hook plate, and a water collection tank, characterized in that: The corrugated plate consists of three pieces, each supported at both ends by a spacer to form two internal steam flow channels, one above the other. A hook plate is located above the spacer at both ends, with the hook facing the center of the corrugated plate. The corrugated plate has crest and trough areas, and each trough area has a triangular guide plate shaped like a triangular arrow. A guide line is connected to the arrow of the triangular guide plate, leading to a small hole in the trough area of the lower corrugated plate. A horizontal water collection trough is located outside the trough area of the lowest layer of corrugated plate.
2. A corrugated plate for steam-water separation in nuclear power plants according to claim 1, characterized in that: The triangular guide plate is at an angle of 120-150 degrees to the horizontal steam entry direction.
3. A corrugated plate for steam-water separation in nuclear power plants according to claim 1, characterized in that: The area of the triangular guide plate is between one-sixth and one-fifth of the vertical cross-section of two adjacent wave crest regions.
4. A corrugated plate for steam-water separation in nuclear power plants according to claim 1, characterized in that: The connection angle between the crest and trough areas of the corrugated plate is set as an arc angle.
5. A corrugated plate for steam-water separation in nuclear power plants according to claim 1, characterized in that: A set of rubber pads is provided at the bottom of both ends of the corrugated plate at the bottom.
6. A corrugated plate for steam-water separation in nuclear power plants according to claim 1, characterized in that: A guide line is provided at the hook of the hook plate at both ends, and the guide line is led down to the fine hole on the corrugated plate at the lower end.
Citation Information
Patent Citations
Baffle separation board subassembly of nuclear island vapor removal desicator
CN204704804U