Nuclear power station containment

Abstract

The utility model discloses a nuclear power station containment. The nuclear power station containment comprises an outer shell and an inner shell, the shell is made of concrete; the inner shell comprises a prestressed concrete containment and a lining, the lining comprises a cylinder body and a dome which are arranged in a split mode, the cylinder body is of a cylindrical structure made of a sealing material and embedded in the outer shell, and the dome is of a steel structure, is located outside the prestressed concrete containment, is connected to the top of the cylinder body and defines a containing cavity together with the cylinder body; the containing cavity is used for containing a pressure container. According to the embodiment, the lining comprises the cylinder body and the dome, in order to meet the heat dissipation performance, the dome is made of steel with high heat conductivity, the cylinder body only needs to be made of sealing materials, and due to the fact that the cylinder body is embedded in the prestressed concrete containment, the requirement for the strength of the cylinder body is low. Therefore, the barrel body can be arranged into other structures which are lower in processing difficulty and lower in cost compared with a dome, so that the construction cost of the nuclear power station is reduced.

Description

Technical Field

[0001] This utility model relates to the field of nuclear power safety technology, and in particular to a nuclear power plant containment vessel. Background Technology

[0002] The containment vessel is the most important structure in a nuclear power plant. Its main functions are to withstand internal pressure, contain airborne radioactive releases, and provide a barrier for the reactor core and coolant system during normal operation. In some technologies, the containment vessel is designed as a double-layered structure, consisting of an outer shell and an inner shell. The outer shell is a concrete structure with ventilation holes, while the inner shell is a one-piece steel structure that utilizes the high thermal conductivity of steel for heat dissipation, thereby ensuring the safety of the nuclear power plant during operation. However, the one-piece steel structure is not only more difficult to manufacture but also more expensive, leading to increased construction costs for the nuclear power plant. Utility Model Content

[0003] This invention aims to solve at least one of the technical problems existing in the prior art. To this end, this invention proposes a nuclear power plant containment structure that can be used in nuclear power plants, reducing the construction cost of nuclear power plants.

[0004] The nuclear power plant containment vessel according to an embodiment of the present invention includes an outer shell and an inner shell.

[0005] The outer shell is made of concrete; the inner shell is disposed inside the outer shell, and the inner shell includes a prestressed concrete containment shell and an inner liner. The inner liner includes a separately disposed cylindrical body and a dome. The cylindrical body is a cylindrical structure made of sealing material and is embedded in the prestressed concrete containment shell. The dome is a steel structure and is connected to the top of the cylindrical body. The dome is located outside the prestressed concrete containment shell and together with the cylindrical body defines a receiving cavity for accommodating a pressure vessel.

[0006] The nuclear power plant containment vessel according to the embodiments of this utility model has at least the following beneficial effects:

[0007] The liner comprises a separate cylindrical body and a dome. Because hot air has a lower density, it tends to accumulate at the top of the containment chamber. Therefore, in this embodiment, the dome is made of steel with high thermal conductivity to meet the heat dissipation requirements of the liner. The cylindrical body, on the other hand, only needs to be made of sealing material to ensure the liner's airtightness. Furthermore, since the cylindrical body is embedded within the prestressed concrete containment vessel, which provides sufficient strength, its strength requirements are lower. Thus, in this embodiment, the cylindrical body can be designed as a structure that is less difficult to manufacture and less expensive than the dome, thereby simplifying the heat removal system configuration and reducing the construction cost of the nuclear power plant.

[0008] According to some embodiments of the present invention, the cylindrical body includes a first shell portion and a second shell portion. The first shell portion is a cylindrical structure with an upward opening at the top. The second shell portion is a steel annular structure and is connected to the top of the second shell portion. The wall thickness of the second shell portion is greater than the wall thickness of the first shell portion. The dome is welded to the second shell portion.

[0009] According to some embodiments of this utility model, the first shell portion is a steel structure; or...

[0010] The first shell is a sealed non-metallic structure.

[0011] According to some embodiments of the present invention, the dome and the inner wall of the outer shell are spaced apart, and the dome, the outer shell and the prestressed concrete safety shell form a heat dissipation cavity. The outer shell also has an air outlet and an air inlet communicating with the heat dissipation cavity, and the position of the air inlet is lower than the position of the air outlet.

[0012] According to some embodiments of the present invention, the containment further includes a first spray device, the first spray device including a first spray head disposed in the heat dissipation cavity, the first spray head being capable of spraying coolant toward the dome.

[0013] According to some embodiments of the present invention, the first spray head is arranged around the outer wall of the dome, the shape and size of the first spray head are adapted to the shape and size of the dome, and the first spray head has through heat dissipation holes.

[0014] According to some embodiments of the present invention, the air inlet is positioned higher than the bottom wall of the heat dissipation cavity, the heat dissipation cavity can temporarily store the coolant sprayed by the first spray head, and the first spray device further includes a first reflux system and a liquid storage tank, the first reflux system being connected to the heat dissipation cavity and the liquid storage tank.

[0015] According to some embodiments of the present invention, the containment further includes a diverter connected to the outer shell or the dome. The diverter includes a diverting section extending downward from the air inlet to the bottom of the heat dissipation cavity. There are gaps between the diverting section and the outer shell, and between the diverter plate and the dome, so that air entering the heat dissipation cavity through the air inlet first flows along the gap between the diverting section and the outer shell to the bottom of the heat dissipation cavity, and then flows upward through the gap between the diverting section and the dome.

[0016] According to some embodiments of the present invention, a sealed cavity is defined between the outer shell and the prestressed concrete safety shell, the sealed cavity surrounds the cylinder body, and the safety shell further includes a negative pressure generating device and a penetrating member. The negative pressure generating device is connected to the sealed cavity, and the penetrating member passes through the outer shell and the inner lining, and through the sealed cavity.

[0017] According to some embodiments of the present invention, the housing further includes a pressure sensor disposed within the sealed cavity. The pressure sensor is communicatively connected to the negative pressure generating device. The pressure sensor is configured such that when the detection signal of the pressure sensor changes, the pressure sensor transmits the detection signal to the negative pressure generating device to activate the negative pressure generating device.

[0018] Additional aspects and advantages of this invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention. Attached Figure Description

[0019] The present invention will be further described below with reference to the accompanying drawings and embodiments, wherein:

[0020] Figure 1 This is a schematic diagram of the structure of the nuclear power plant containment vessel according to the first embodiment of this utility model;

[0021] Figure 2 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the second embodiment of this utility model;

[0022] Figure 3 for Figure 2 Enlarged view of region A in the middle;

[0023] Figure 4 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the third embodiment of this utility model;

[0024] Figure 5 This is a schematic diagram of the structure of the nuclear power plant containment vessel according to the fourth embodiment of this utility model;

[0025] Figure 6 This is a schematic diagram of the structure of the nuclear power plant containment vessel according to the fifth embodiment of this utility model;

[0026] Figure 7 This is a schematic diagram of the structure of the nuclear power plant containment vessel according to the sixth embodiment of this utility model;

[0027] Figure 8 This is a structural schematic diagram of the containment vessel of a nuclear power plant, according to the seventh embodiment of this utility model.

[0028] Figure label:

[0029] The outer casing is 100, the air outlet is 110, the air inlet is 120, the shield is 130, and the sealing cavity is 140.

[0030] Liner 200, cylinder body 210, first shell 211, second shell 212, dome 220, receiving cavity 230;

[0031] Heat dissipation cavity 300;

[0032] First spray device 400, first spray head 410, first reflux system 420, liquid storage tank 430;

[0033] Diverter component 500, diverter section 510;

[0034] Penetrating component 600;

[0035] Second spray device 700, second spray head 710, second reflux system 720;

[0036] Inner shell 800, prestressed concrete containment shell 900. Detailed Implementation

[0037] The embodiments of this utility model are described in detail below. Examples of these embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain this utility model, and should not be construed as limiting this utility model.

[0038] In the description of this utility model, it should be understood that the directional descriptions, such as up, down, front, back, left, right, etc., indicate the directional or positional relationship based on the directional or positional relationship shown in the accompanying drawings. They are only for the convenience of describing this utility model and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this utility model.

[0039] In the description of this utility model, "several" means one or more, "multiple" means two or more, "greater than," "less than," and "exceeding" are understood to exclude the stated number, while "above," "below," and "within" are understood to include the stated number. The use of "first" and "second" in the description is merely for distinguishing technical features and should not be construed as indicating or implying relative importance, or implicitly indicating the number of indicated technical features, or implicitly indicating the order of the indicated technical features.

[0040] In the description of this utility model, unless otherwise explicitly defined, terms such as "setting," "installation," and "connection" should be interpreted broadly, and those skilled in the art can reasonably determine the specific meaning of the above terms in this utility model in conjunction with the specific content of the technical solution.

[0041] The containment vessel is the most important structure in a nuclear power plant. Its main functions are to withstand internal pressure, contain airborne radioactive releases, and provide a barrier for the reactor core and coolant system during normal operation. In some technologies, the containment vessel is designed as a double-layered structure, consisting of an outer shell and an inner shell. The outer shell is a concrete structure with ventilation holes, while the inner shell is a one-piece steel structure that utilizes the high thermal conductivity of steel for heat dissipation, thereby ensuring the safety of the nuclear power plant during operation. However, the one-piece steel structure is not only more difficult to manufacture but also more expensive, leading to increased construction costs for the nuclear power plant.

[0042] To address the aforementioned problems, this invention proposes a containment structure suitable for use in nuclear power plants, thereby reducing the construction costs of nuclear power plants. (Refer to...) Figure 1 , Figure 1 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the first embodiment of the present invention. The nuclear power plant containment vessel of this embodiment (hereinafter referred to as containment vessel unless otherwise specified) includes: an outer shell 100 and an inner shell 800.

[0043] The outer shell 100 is made of concrete, providing sufficient strength for the containment vessel and shielding it from radiation. The outer shell 100 can be formed by monolithic casting or by segmented casting followed by assembly. The inner shell 800 is located inside the outer shell 100 and includes a prestressed concrete containment vessel 900 and an inner liner 200. The inner liner 200 is located inside the outer shell 100 and includes a separately configured cylindrical body 210 and a dome 220. The cylindrical body 210 is a cylindrical structure made of sealing material and is embedded within the prestressed concrete containment vessel 900. The dome 220 is a steel structure located outside the prestressed concrete containment vessel 900 and connected to the top of the cylindrical body 210. Together with the cylindrical body 210, the dome defines a receiving cavity 230 for accommodating the pressure vessel. Specifically, it can be understood that hot air has a lower density, therefore, the heat is mainly concentrated at the top of the containment cavity 230, corresponding to the dome 220. Therefore, in this embodiment, the dome 220 is made of steel with high thermal conductivity to meet the heat dissipation requirements of the containment structure. The bottom cylinder 210 only needs to be made of sealing material to ensure the sealing of the liner 200 under various operating conditions in the power plant. Furthermore, since the cylinder 210 is embedded within the prestressed concrete containment structure 900, the prestressed concrete provides sufficient strength; therefore, the strength requirement for the cylinder 210 is relatively low. Thus, in this embodiment, the cylinder 210 can be designed as a structure that is easier to manufacture and has lower material costs than the dome 220, without needing to be identical to the dome 220, thereby reducing the construction cost of the nuclear power plant.

[0044] For example, in some embodiments, both the cylinder 210 and the dome 220 are made of steel, with the wall thickness of the cylinder 210 being less than that of the dome 220. Specifically, since the strength requirements for the cylinder 210 are lower, its wall thickness can be thinner than that of the dome 220, as long as its airtightness is ensured. This reduces the material cost of the cylinder 210, and when the cylinder 210 is formed by multi-segment welding, it is easier to weld, thereby reducing the processing cost of the cylinder 210 and thus reducing the construction cost of the nuclear power plant. Furthermore, the cylinder 210 can also be made of non-metallic materials with strong sealing properties, such as epoxy resin or ceramics. Compared to steel, these materials are easier to process into a cylindrical structure and have lower material costs, thus reducing the manufacturing cost of the cylinder 210.

[0045] Reference Figure 1 In some embodiments, the dome 220 is spaced apart from the inner wall of the outer shell 100. The dome 220, the outer shell 100, and the prestressed concrete containment 900 together define a heat dissipation cavity 300. The outer shell 100 also has an air inlet 120 and an air outlet 110 communicating with the receiving cavity 230. The position of the air inlet 120 is lower than that of the air outlet 110. Specifically, during operation, the heat from the dome 220 dissipates into the heat dissipation cavity 300, forming hot air inside the heat dissipation cavity 300. The hot air then flows out through the air outlet 110. At the same time, cold air from outside the outer shell 100 flows into the heat dissipation cavity 300 through the air inlet 120. Thus, natural convection heat exchange is formed in the dome 220 area of ​​the outer shell 100 to improve the heat dissipation efficiency of the containment. It should be noted that the reason why the height of the air inlet 120 is lower than that of the air outlet 110 is because the density of hot air is lower than that of cold air. Therefore, the hot air will float upwards when it flows out of the heat dissipation cavity 300. In order to prevent the exhaust hot air from entering the heat dissipation cavity 300 through the air inlet 120, the air inlet 120 is set below the air outlet 110 to ensure the heat dissipation performance of the containment in this embodiment.

[0046] Reference Figures 2 to 4 , Figure 2 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the second embodiment of this utility model. Figure 3 for Figure 2 Enlarged diagram of region A in the middle. Figure 4 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to a third embodiment of the present invention. In some embodiments, the shell 210 includes a first shell portion 211 and a second shell portion 212 (e.g., Figure 3As shown, the first shell portion 211 is a cylindrical structure with an upward opening at the top, and the second shell portion 212 is a steel annular structure connected to the top of the second shell portion 212. The wall thickness of the second shell portion 212 is greater than the wall thickness of the first shell portion 211. The dome 220 is welded to the second shell portion 212. Specifically, the second shell portion 212 is used to connect with the dome 220 by welding. The greater wall thickness of the second shell portion 212 than the first shell portion 211 improves the connection strength between the dome 220 and the second shell portion 212, thereby improving the overall strength of the inner liner 200. In this embodiment, for example, in some embodiments, the wall thickness of the second shell portion 212 is equal to the wall thickness of the dome 220, without needing the overall thickness of the cylindrical body 210 to be equal to the thickness of the dome 220. Thus, while ensuring the connection strength between the second shell portion 212 and the dome 220, the manufacturing cost of the cylindrical body 210 can be reduced. It should be noted that, in this embodiment, the first shell portion 211 is not limited to a steel structure; it can also be a non-metallic structure (such as...). Figure 4 As shown in the figure, as long as the sealing performance of the lining 200 can be guaranteed under various operating conditions in the power plant, it is acceptable.

[0047] Reference Figure 5 , Figure 5 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the fourth embodiment of the present invention. In some embodiments, the containment vessel further includes a first spray device 400, which includes a first spray head 410 disposed in the heat dissipation cavity 300. The first spray head 410 can spray coolant toward the dome 220, thereby rapidly cooling the outer surface of the dome 220, thereby improving the efficiency of heat transfer from the dome 220 to the heat dissipation cavity 300 inside the containment cavity 230, and improving the heat dissipation efficiency of the containment vessel in this embodiment.

[0048] Based on the above embodiments, the containment is also equipped with a first temperature sensor, and the first spray device 400 also includes a liquid storage tank 430 and a valve. The liquid storage tank 430 is connected to the first spray head 410, and the valve is located at the liquid outlet of the liquid storage tank 430. The first temperature sensor is communicatively connected to the valve. The first temperature sensor is used to detect the temperature of the dome 220 and transmit the signal to the valve so that the valve adjusts the opening and closing degree of the liquid outlet according to the temperature of the dome 220, thereby adjusting the flow rate of the coolant so that the coolant entering the heat dissipation cavity 300 is vaporized and discharged through the air outlet 110 without the need to set up a return system, thereby making the containment structure more compact.

[0049] Alternatively, in some embodiments, the air inlet 120 is positioned higher than the bottom wall of the heat dissipation cavity 300 (e.g., Figure 5As shown, the first spray device 400 is designed to store the coolant sprayed from the first spray head 410 within the heat dissipation cavity 300. The first spray device 400 also includes a first return system 420 and a storage tank 430, with the first return system 420 connecting the heat dissipation cavity 300 and the storage tank 430. Therefore, during operation, the coolant can be temporarily stored within the heat dissipation cavity 300 and returned to the storage tank via the first return system 420. Consequently, this embodiment does not require monitoring the temperature of the dome 220 and thus eliminates the need for a temperature sensor, resulting in a lower containment cost.

[0050] Reference Figure 5 Based on the above embodiments, the outer casing 100 also includes a shielding part 130, which is disposed at the air inlet 120 to reduce external dust and other debris from falling into the heat dissipation cavity 300 through the air inlet, thereby reducing the risk of the first spray device 400 being blocked.

[0051] Reference Figure 5 In some embodiments, the first spray head 410 is arranged around the outer wall of the dome 220, and the shape and size of the first spray head 410 are adapted to the shape and size of the dome 220, so that the coolant sprayed by the first spray device 400 evenly covers the outer wall of the dome 220, thereby improving the heat dissipation efficiency of the dome 220. At the same time, it can make the temperature of the outer wall of the dome 220 more uniform, improving the lifespan of the dome 220. Furthermore, the first spray head 410 has through-holes for heat dissipation, thereby reducing the obstruction of hot air flow to the air outlet 110.

[0052] Reference Figure 8 , Figure 8 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the seventh embodiment of the present invention. In some embodiments, the containment vessel further includes a second spray device 700. The second spray device 700 includes a second spray head 710 located inside the containment cavity 230. Once a failure occurs in the equipment inside the containment vessel, causing a rapid temperature rise, coolant is sprayed into the containment cavity 230 through the second spray head 710 to quickly cool the containment cavity 230, thereby preventing accidents such as containment vessel explosions. For example, a second temperature sensor is installed inside the containment cavity 230 and is communicatively connected to the second spray device 700. When the second temperature sensor detects that the temperature inside the containment cavity 230 is greater than a set value, the second temperature sensor transmits a signal to the second spray device 700, causing the second spray head 710 to spray coolant into the containment cavity 230, achieving emergency cooling of the containment cavity 230.

[0053] Furthermore, in some embodiments, the second spray device 700 further includes a second reflux system 720, which is used to discharge the coolant from the containment cavity 230 for heat exchange, so that the coolant can be reused, thereby saving operating costs.

[0054] Reference Figure 6 In some embodiments, the containment enclosure further includes a diverter 500 connected to the outer shell 100 or the dome 220. The diverter 500 includes a diverter section 510 extending downward from the air inlet 120 to the bottom of the heat dissipation cavity 300. The diverter section 510 has gaps between itself and the outer shell 100 and the dome 220, so that the air entering the heat dissipation cavity 300 through the air inlet 120 first flows along the gap between the diverter section 510 and the outer shell 100 to the bottom of the heat dissipation cavity 300, and then flows upward through the gap between the diverter section 510 and the dome 220, thereby allowing the external cold air to fully contact the dome 220 to improve the cooling efficiency of the outer shell 100.

[0055] Reference Figure 7 , Figure 7 This is a schematic diagram of the structure of a nuclear power plant containment vessel according to the sixth embodiment of the present invention. In some embodiments, a sealed cavity 140 is defined between the outer shell 100 and the prestressed concrete containment vessel 900. The sealed cavity 140 surrounds the cylindrical body 210. The containment vessel also includes a negative pressure generating device and a penetrating member 600. The penetrating member 600 is, for example, an electrical penetrating member or a mechanical penetrating member. The mechanical penetrating member is mainly used to connect fluid pipelines inside and outside the nuclear power plant containment vessel, and the electrical penetrating member is used for cables to pass through the nuclear power plant containment vessel. The penetrating member 600 passes through the outer shell 100 and the inner liner 200, and passes through the sealed cavity 140. The negative pressure generating device is, for example, a vacuum pump, a negative pressure fan, or a venturi. The negative pressure generating device is connected to the sealed cavity 140 and is used to maintain a negative pressure state inside the sealed cavity 140. Therefore, once a leak occurs at the connection between the penetrating member 600 and the inner liner 200, the leaked radioactive material enters the sealed cavity 140 under the action of negative pressure, thereby preventing the radioactive material from being directly discharged into the external environment without treatment, and thus improving the sealing performance of the containment vessel in this embodiment.

[0056] Furthermore, in some embodiments, the containment also includes a pressure sensor disposed within the sealed cavity 140 and communicatively connected to the negative pressure generating device. The pressure sensor is configured to transmit a signal to the negative pressure generating device when its detected signal changes, thereby activating the negative pressure generating device. Therefore, during operation, the negative pressure generating device does not need to be continuously operational, reducing equipment operating costs. Specifically, in the initial stage of equipment operation, the negative pressure generating device creates a negative pressure environment in the sealed cavity 140. When the pressure inside the sealed cavity 140 reaches a certain value (less than a certain pressure inside the containment cavity 230), the system shuts down. During nuclear power plant operation, if a leak occurs in the liner 200, causing a change in the pressure inside the sealed cavity 140, the pressure sensor's detection signal changes, and the signal is transmitted to the negative pressure generating device, activating it and maintaining the sealed cavity 140 in a negative pressure state. Thus, the negative pressure generating device in this embodiment does not need to be constantly operational, but only operates when the containment leaks, thereby saving energy.

[0057] The embodiments of the present invention have been described in detail above with reference to the accompanying drawings. However, the present invention is not limited to the above embodiments, and various changes can be made within the scope of knowledge possessed by those skilled in the art without departing from the spirit of the present invention. Furthermore, in the description of the present invention, the reference to terms such as "one embodiment," "some embodiments," "illustrative embodiment," "example," "specific example," or "some examples," etc., indicates that the specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described can be combined in any suitable manner in one or more embodiments or examples.

Claims

1. A containment vessel for a nuclear power plant, characterized in that, include: The outer shell is made of concrete; An inner shell is disposed inside the outer shell. The inner shell includes a prestressed concrete containment shell and an inner liner. The inner liner includes a separately disposed cylindrical body and a dome. The cylindrical body is a cylindrical structure made of sealing material and is embedded in the prestressed concrete containment shell. The dome is a steel structure located outside the prestressed concrete containment shell and connected to the top of the cylindrical body. Together with the cylindrical body, the dome defines a receiving cavity for accommodating a pressure vessel.

2. The nuclear power plant containment vessel according to claim 1, characterized in that, The cylindrical body includes a first shell and a second shell. The first shell is a cylindrical structure with an opening at the top. The second shell is a steel annular structure connected to the top of the second shell. The wall thickness of the second shell is greater than that of the first shell. The dome is welded to the second shell.

3. The nuclear power plant containment vessel according to claim 2, characterized in that, The first shell portion is a steel structure; or... The first shell is a sealed non-metallic structure.

4. The nuclear power plant containment vessel according to claim 1, characterized in that, The dome and the inner wall of the outer shell are spaced apart. The dome, the outer shell and the prestressed concrete safety shell form a heat dissipation cavity. The outer shell also has an air outlet and an air inlet communicating with the heat dissipation cavity. The height of the air inlet is lower than the height of the air outlet.

5. The nuclear power plant containment vessel according to claim 4, characterized in that, The containment also includes a first spray device, which includes a first spray head disposed inside the heat dissipation cavity and is capable of spraying coolant toward the dome.

6. The nuclear power plant containment vessel according to claim 5, characterized in that, The first spray head is arranged around the outer wall of the dome, and the shape and size of the first spray head are adapted to the shape and size of the dome.

7. The nuclear power plant containment vessel according to claim 5, characterized in that, The air inlet is positioned higher than the bottom wall of the heat dissipation cavity, which can temporarily store the coolant sprayed by the first spray head. The first spray device also includes a first reflux system and a liquid storage tank, with the first reflux system connected to the heat dissipation cavity and the liquid storage tank.

8. The nuclear power plant containment vessel according to claim 7, characterized in that, The containment structure also includes a flow divider connected to the outer shell or the dome. The flow divider includes a flow divider section extending downward from the air inlet to the bottom of the heat dissipation cavity. There are gaps between the flow divider section and the outer shell, and between the flow divider section and the dome, so that air entering the heat dissipation cavity through the air inlet first flows along the gap between the flow divider section and the outer shell to the bottom of the heat dissipation cavity, and then flows upward through the gap between the flow divider section and the dome.

9. The nuclear power plant containment vessel according to claim 1, characterized in that, A sealed cavity is defined between the outer shell and the prestressed concrete containment shell, the sealed cavity surrounding the cylinder body, the containment shell further including a negative pressure generating device and a penetrating member, the penetrating member passing through the outer shell and the inner lining and through the sealed cavity, the negative pressure generating device communicating with the sealed cavity.

10. The nuclear power plant containment vessel according to claim 9, characterized in that, The housing also includes a pressure sensor, which is disposed in the sealed cavity and is communicatively connected to the negative pressure generating device. The pressure sensor is configured to transmit the detection signal to the negative pressure generating device when the detection signal of the pressure sensor changes, so as to start the negative pressure generating device.

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