Heat-exchange recovery device for nuclear power plant thermal energy

By using trapezoidal outer shell, V-shaped internal heat exchange pipe and variable cross-section water distribution assembly in the thermal energy exchange device of nuclear power plants, combined with the Carmen vortex principle, the problems of short contact time and low heat exchange efficiency in traditional devices are solved, and efficient and flexible thermal energy recovery is achieved.

WO2025107424A1PCT designated stage expired Publication Date: 2025-05-30ZHEJIANG JIACHENG ENERGY TECHNOLOGY CO LTD
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Patent Information

Application Number
PCT/CN2024/075376
Authority / Receiving Office
WO · WO
Patent Type
Applications
Current Assignee / Owner
Priority Date
2023-11-24
Filing Date
2024-02-02
Publication Date
2025-05-30

AI Technical Summary

Technical Problem

During the contact process between high-temperature liquid and heat exchange pipes, the traditional nuclear power plant thermal energy heat exchange device has a short contact time and a single heat exchange form, resulting in low heat exchange efficiency and difficulty in optimizing heat exchange for liquids of different temperatures.

Method used

A thermal energy heat exchange recovery device for nuclear power plants is designed, using trapezoidal outer shell and V-shaped internal heat exchange pipe, combined with variable cross-sectional water separation assembly and Carmen vortex principle to realize high-temperature liquid wrap-around heat exchange, increase contact time and efficiency, and adjust the heat exchange form according to the liquid temperature.

Benefits of technology

The heat exchange efficiency of a single heat exchange tube is improved, efficient heat exchange for liquids with different temperatures is achieved, the incomplete heat exchange and repeated heat exchange are reduced, and the overall heat exchange efficiency and energy utilization are improved.

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Abstract

The present invention relates to the technical field of heat exchangers, and disclosed is a heat-exchange recovery device for nuclear power plant thermal energy. The device comprises an outer housing, internal heat exchange pipes, and a variable-section water distribution assembly, thus enabling an improved heat exchange efficiency and a variable heat exchange mode. A water inlet and a water outlet are formed in the outer housing; partition plates are provided in the outer housing and divide the outer housing into eight trapezoids; and a V-shaped internal heat exchange pipe is mounted inside each trapezoid. This design allows a high-temperature liquid to undergo surrounding heat exchange around the vertical heat exchange pipes, thus improving the heat exchange efficiency of individual heat exchange pipes, and thereby improving the overall heat exchange efficiency. Additionally, the method of connecting the trapezoids enables progressive heat exchange. The variable-section water distribution assembly can adjust the contact area based on the heat of an input liquid, thereby adjusting the heat exchange form and efficiency to allow for the complete absorption of heat from a liquid at different temperatures, thus preventing waste. The device has the advantages of high efficiency, saving energy, strong adaptability, etc., and is suitable for use in fields such as nuclear power plant thermal energy recovery.
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Description

A heat exchange recovery device for a nuclear power plant Technical Field

[0001] The present invention relates to the technical field of heat exchangers, in particular to a heat exchange type recovery device for heat energy in a nuclear power plant. Background Art

[0002] In the early days, nuclear power plants focused primarily on efficiently generating electricity, with little emphasis on utilizing waste heat. However, with increasing energy resource scarcity and growing awareness of environmental protection, attention has shifted to improving the energy efficiency of nuclear power plants and reducing their environmental impact. This has led to the development and application of heat recovery devices. These devices primarily aim to improve the energy efficiency of nuclear power plants by recovering waste heat from them and converting it into useful heat or electricity. These devices utilize waste heat from nuclear power plants, transferring it to other media, such as water or air, through a heat exchanger, converting it into useful heat or electricity. With continuous technological advancements, heat recovery devices have evolved into various types, including direct contact, indirect contact, and hybrid types. Simultaneously, their application areas have expanded beyond nuclear power plants to include industrial waste heat recovery and geothermal power generation. In short, the development of heat recovery devices for nuclear power plants has progressed in tandem with the advancement of nuclear power technology and the growing need for environmental protection. In the future, with the continuous innovation of technology and the improvement of environmental protection requirements, the application prospects of heat exchange recovery devices will be broader.

[0003] When traditional heat exchange devices are performing heat exchange, the high-temperature liquid flows at a fast rate and the high-temperature liquid is simply in parallel contact flow heat exchange when flowing through the surface of the heat exchange tube. This form of heat exchange makes the contact time of the high-temperature liquid in contact with the heat exchange tube for heat exchange too short and the direct parallel flow contact. The heat exchange tube has not yet completely absorbed the heat in the high-temperature heat body, and the high-temperature liquid flows away quickly, resulting in low heat exchange efficiency; secondly, the traditional heat exchange device has the same heat exchange rate and heat exchange form for liquids of different temperatures flowing in, and it is difficult to perform different forms of heat exchange for high-temperature liquids of different temperatures. Specifically, for liquids with higher temperatures, the temperature of the liquid may still be very high after one round of heat exchange, that is, the heat exchange is incomplete, and a second repeated heat exchange is required, which wastes resources and time; for liquids with lower temperatures, the heat exchange may be completely completed after half of the heat exchange process, and the next half of the heat exchange steps are repeated heat exchange, which wastes time and resources. Technical issues

[0004] (1) Technical problems to be solved: In response to the deficiencies of the prior art, the present invention provides a heat exchange recovery device for a nuclear power plant, which is capable of allowing high-temperature liquid to exchange heat in a surrounding manner around the heat exchange tubes, increasing the contact time between the high-temperature liquid and the vertical heat exchange tubes, and changing the contact mode between the high-temperature liquid and the vertical heat exchange tubes, thereby improving the heat exchange efficiency of a single heat exchange tube and thus improving the overall heat exchange efficiency; trapezoidal heat exchange cavities of the same shape but staggered are connected by external connecting pipes, which can realize progressive heat exchange layer by layer; the overall heat exchange efficiency and heat exchange form can be adjusted according to the temperature of the input liquid, so that complete heat exchange can be achieved for liquids with higher temperatures, and repeated heat exchange can be reduced for liquids with lower temperatures. The invention solves the problem that in traditional heat exchange devices, the liquid flow rate is fast and the high-temperature liquid is simply in parallel contact flow when flowing through the surface of the heat exchange tube, resulting in low heat exchange efficiency; secondly, the traditional heat exchange device has the same heat exchange rate and heat exchange form for liquids with different temperatures flowing in, and it is difficult to completely heat exchange high-temperature liquids of different temperatures. For liquids with higher temperatures, the temperature of the liquid may still be very high after one round of heat exchange, that is, the heat exchange is incomplete, and a second repeated heat exchange is required, which wastes resources and time; for liquids with lower temperatures, the heat exchange may be completely completed after half of the heat exchange process, and the subsequent half of the heat exchange steps are repeated heat exchange, which wastes time and resources. Technical Solutions

[0005] (II) Technical Solution: To achieve the above-mentioned heat exchange of high-temperature liquid around the heat exchange tube, improve the heat exchange efficiency of a single heat exchange tube and thus improve the overall heat exchange efficiency, realize progressive heat exchange, and adjust the overall heat exchange efficiency and heat exchange form according to the heat of the input liquid to achieve the purpose of completely absorbing the heat of liquids at different temperatures without waste. The present invention provides the following technical solution: A nuclear power plant heat exchange recovery device, comprising an outer shell with a trapezoidal cross-section, an internal heat exchange tube, and a variable-section water distribution assembly that adjusts the water-facing cross-section by rotation or deformation of its own width. The closed side and open side of the outer shell are respectively processed with a water inlet and a water outlet. The closed side of the inner shell is provided with a variable-section water distribution assembly that blocks water from the water inlet. The inner heat exchange tube is disposed in the outer shell. The overall shape of the inner heat exchange tube is V-shaped and adapts to the gradient opening direction of the outer shell, that is, the V-shaped top end of the internal heat exchange tube is installed on the shorter side of the outer shell, and the V-shaped open end of the internal heat exchange tube is installed on the longer side of the outer shell.

[0006] Preferably, the variable-section water diversion assembly includes a rotating handle, a ratchet, a semicircular iron plate, a traction rope and a traction rod. The semicircular iron plate faces the water inlet, and the two ends of the semicircular iron plate are connected to the traction rod through a traction rope. A ratchet is installed on the top of the traction rod, and a rotating handle is installed on the upper end of the ratchet. The rotating handle can drive the traction rod and the ratchet to rotate.

[0007] Preferably, the variable-section water-dividing component may be in the form of a cylindrical column with an arbitrary cross-section.

[0008] Preferably, at least two outer shells are provided, and a single outer shell is divided by a partition processed inside the shell, and the partition divides the shell into several trapezoids of the same shape, and the longer side of the trapezoid is interconnected with the shorter side of another trapezoid, and adjacent outer shells are installed with external connecting pipes distributed side by side corresponding to the water inlet and the water outlet.

[0009] Preferably, the number of the water outlets and the water inlet on the outer shell is the same, and they are evenly arranged and distributed longitudinally, and the water outlets and the water inlet correspond to each other one by one.

[0010] Preferably, a buckle is installed on the outer edge of the ratchet, and a column is installed on the lower part of the buckle.

[0011] Preferably, the internal heat exchange tube includes a vertical heat exchange pipe, a heat exchange water inlet and a heat exchange water outlet. The vertical heat exchange pipe of the internal heat exchanger is composed of a whole connected S-shaped coil. The heat exchange water inlet is located at the upper end of the outer shell, and the heat exchange water outlet is located at the lower end of the outer shell. Beneficial effects

[0012] (III) Beneficial effects: Compared with the prior art, the present invention provides a nuclear power plant heat exchange type recovery device, which has the following beneficial effects:

[0013] This nuclear power plant heat recovery device utilizes an outer shell, water inlet, water outlet, internal heat exchange tubes, a variable-section water distribution assembly, and clips. Based on the Karman vortex street principle, under certain conditions, when a steady flow passes over an object, two rows of line vortices rotating in opposite directions are periodically shed on both sides of the object. Initially, these two rows of line vortices maintain their own motion, but then they interfere with each other, attracting each other, and the interference becomes increasingly stronger, forming a nonlinear vortex street. According to this principle, we will input the high-temperature hot water that needs to be exchanged into the outer shell at a uniform and equal amount and at a uniform speed through the water inlets evenly arranged on the outer shell to exchange with the internal heat exchange tube. Since the water inlet is processed on the shorter side of the trapezoid inside the outer shell, the high-temperature hot water that needs to be exchanged with heat will come into contact with the variable-section water distribution component after entering the inner shell. Under the action of the Karman vortex street principle, these flowing high-temperature liquids will form periodic double-row line vortices with opposite rotation directions and arranged in a regular pattern at the rear when bypassing the variable-section water distribution component. These vortices will surround the vertical tube part of the internal heat exchange tube to fully exchange heat with the internal heat exchange tube, and then flow out through the water outlet. Compared with traditional direct flow heat exchange, this heat exchange method can be in contact with the heat exchange tube for a longer time in the same heat exchange stroke, thereby achieving the effect of increasing the heat exchange efficiency of the internal heat exchange tube.

[0014] 2. A heat exchange recovery device for a nuclear power plant uses a variable cross-section water distribution component, a rotating handle, a ratchet, a semicircular iron sheet, a traction rope, a traction rod, and a buckle in coordination with each other. When the temperature of the liquid to be heat exchanged is high or low, according to the Karman vortex street principle: the frequency of the Karman vortex street refers to the number of times the vortices in the Karman vortex street fall off. When the flow velocity passing through the surface of an object changes, a Karman vortex street is formed with a certain frequency. This frequency depends on factors such as the properties of the fluid, the magnitude of the flow velocity, and the shape and size of the surface of the object. At this time, the traction rod can be rotated by rotating the handle, and the traction rope connected to the traction rod can be used to shrink the semicircular iron sheet inward to reduce the contact area with the high-temperature liquid, thereby affecting the frequency and time of vortex formation in the back. According to the liquids of different temperatures, the appropriate contact area is adjusted so that the liquids of different temperatures can be completely heat exchanged after a round of heat exchange, thereby solving the problem of incomplete heat exchange for higher temperature liquids and repeated heat exchange for lower temperature liquids, resulting in waste.

[0015] 3. This heat exchange recovery device for a nuclear power plant uses an outer shell and a partition to cooperate with each other. The partition divides the internal space of the outer shell into several isosceles trapezoids of the same shape. The shape of the trapezoid is the same as the overall shape of a series of vortices generated by the Karman vortex street when the high-temperature liquid is heat exchanged. In addition, holes are processed on the short and long sides of each trapezoid respectively. These corresponding holes connect the long and short sides of each individual trapezoid to form a gradient heat exchange space that is progressive and independent of each other. This can achieve layer-by-layer gradient heat exchange for the high-temperature liquid, making the heat exchange form and the control of the heat exchange temperature more convenient. For liquids with higher temperatures, it reduces incomplete heat exchange, and for liquids with lower temperatures, it reduces repeated heat exchange, making heat exchange for liquids of different temperatures more reasonable. BRIEF DESCRIPTION OF THE DRAWINGS

[0016] FIG1 is a schematic structural diagram of a heat exchange type heat recovery device for a nuclear power plant;

[0017] FIG2 is a schematic structural diagram of a basic working unit of a heat exchange type heat recovery device for a nuclear power plant;

[0018] FIG3 is a schematic diagram of the internal structure of several basic units arranged in parallel in a heat exchange type heat recovery device for a nuclear power plant;

[0019] FIG4 is a top view of the internal structure of several basic units arranged in parallel in a heat exchange type heat recovery device for a nuclear power plant;

[0020] FIG5 is a schematic diagram of the outer shell structure of several basic units arranged in parallel in a heat exchange recovery device for a nuclear power plant;

[0021] FIG6 is a schematic diagram of a structure of a connected internal heat exchange tube of a heat exchange recovery device of a nuclear power plant;

[0022] FIG7 is a schematic structural diagram of a variable cross-section water distribution component of a heat exchange recovery device for a nuclear power plant;

[0023] FIG8 is an enlarged schematic diagram of the structure of location A of a heat exchange recovery device for a nuclear power plant;

[0024] FIG9 is a schematic diagram of heat exchange of a Karman vortex street model of a heat exchange type recovery device for a nuclear power plant;

[0025] FIG10 is a schematic diagram of the structure of the second variable-section water distribution component of the heat exchange recovery device of a nuclear power plant.

[0026] In the figure: 1 outer shell, 11 partition, 12 water outlet, 13 water inlet, 2 external connecting pipe, 3 internal heat exchange pipe, 31 heat exchange outlet, 32 heat exchange inlet, 33 vertical heat exchange pipe, 4 variable cross-section water distribution component, 41 rotating handle, 42 ratchet, 43 semicircular iron sheet, 44 traction rope, 45 traction rod, 5 buckle, 51 column. Modes for Carrying Out the Invention

[0027] The following will clearly and completely describe the technical solutions in the embodiments of the present invention in conjunction with the accompanying drawings. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without making creative efforts are within the scope of protection of the present invention.

[0028] Example 1: Please refer to Figures 1-6, a heat exchange recovery device for heat energy in a nuclear power plant, which is mainly used to recover the heat energy generated by the nuclear power plant. The device transfers heat from the high-temperature fluid to the low-temperature fluid through the internal heat exchange tube 3 to achieve heat recovery and utilization. Specifically, the high-temperature fluid enters from the water inlet 13, flows through the internal heat exchange tube 3, transfers heat to the low-temperature fluid, and then flows out from the water outlet 12. The low-temperature fluid enters from the heat exchange water inlet 32 ​​on the other side, absorbs heat, and flows out from the heat exchange water outlet 31. The device includes an outer shell 1, an internal heat exchange tube 3 with a variable cross-section water distribution component 4 and a clip 5. The outer shell 1 is respectively processed with a water inlet 13 and a water outlet 12. The number of the water outlet 12 and the water inlet 13 on the outer shell 1 is the same, and they are evenly arranged in the longitudinal direction, and the water outlet 12 corresponds to the water inlet 13 one by one. This longitudinal arrangement of the water outlets 12 allows the high-temperature liquid that needs to be heat exchanged to enter the device at a relatively uniform flow rate and flow rate for heat exchange. Furthermore, the simultaneous input of equal amounts of high-temperature liquid on the same vertical plane can better guarantee and maintain the flow rate and flow rate of the high-temperature liquid within the same vertical plane, ensuring that the high-temperature liquid on each horizontal cross-section within the device can undergo a surround heat exchange in the form of a Karman vortex street on the vertical heat exchange pipes 33 of the internal heat exchange tubes 3. The outer shell 1 is machined with a water inlet 13 and a water outlet 12 that are arranged side by side. These water inlet 13 and water outlet 12 can input the liquid that needs to be heat exchanged into the device, and after the heat exchange is completed, the liquid is discharged through the water outlet 12.

[0029] When several outer shells 1 are connected to each other, a partition 11 is processed inside the outer shell 1. The partition 11 divides the shell into eight trapezoids of the same shape, and an external connecting pipe 2 is connected between each single working unit. The trapezoidal shape is designed to conform to the liquid flow situation in the Karman vortex street. When a steady flow passes around certain objects under certain conditions, double rows of line vortices with opposite rotation directions and regular arrangement will periodically fall off on both sides of the object. After nonlinear action, a Karman vortex street is formed. The distribution of this Karman vortex street on both sides of the object is in the form of gradually spreading out, so the overall shape is trapezoidal. The trapezoidal shape design can make the high-temperature liquid more smoothly present the form of the Karman vortex street for heat exchange and will not hinder the flow of the high-temperature liquid. The longer side of the trapezoid is interconnected with the shorter side of the other trapezoid. This trapezoidal arrangement can save more space.

[0030] Internal heat exchange tubes 3 are installed within the space separated by partitions 11. These tubes are V-shaped, with the V-shaped tops of the tubes 3 mounted on the shorter sides of the trapezoidal compartments, and the V-shaped open ends of the tubes 3 mounted on the longer sides. External connecting pipes 2 are installed on the outer shell 1, arranged side by side with the water inlet 13 and water outlet 12. The internal heat exchanger includes vertical heat exchange pipes 33, a heat exchange water inlet 32, and a heat exchange water outlet 31. The vertical heat exchange pipes 33 of the internal heat exchanger are arranged in an alternating V-shape, with the heat exchange water inlet 32 ​​located at the upper end of the outer shell 1 and the heat exchange water outlet 31 at the lower end. This installation and processing method ensures that the arrangement of the vertical heat exchange pipes 33 of the internal heat exchange tubes 3 conforms to the formation of a Karman vortex street during heat exchange. The vertical heat exchange pipes 33 are the main heat exchange portion, and the generated vortices mainly surround the vertical heat exchange pipes 33, performing long-term heat exchange. After passing through an object, the Karman vortex street will periodically shed a double row of linear vortices with opposite rotation directions and regular arrangement. The arrangement of these vortices spreads from the center to both sides and is staggered with each other. This installation method ensures that there is a vertical heat exchange pipe 33 at the location where each vortex is generated, ensuring that each vortex has an internal heat exchange pipe 3 to transfer heat, and also ensuring that there is a vortex around each vertical heat exchange pipe 33 for heat exchange.

[0031] Referring to Figures 7-9 , the V-shaped top of the internal heat exchange tube 3 is mounted with a variable-section water distribution assembly 4. This assembly includes a rotating handle 41, a ratchet 42, a semicircular iron plate 43, a traction rope 44, and a traction rod 45. The semicircular iron plate 43 faces the water inlet 13, and the two ends of the semicircular iron plate 43 are connected to the traction rod 45 via a traction rope 44. The traction rod 45 is topped with a ratchet 42, and a rotating handle 41 is mounted above the ratchet 42. Rotating the handle 41 drives the traction rod 45 and the ratchet 42 to rotate.

[0032] In the Karman vortex street, vortices will fall off. Vortex shedding refers to the formation of a series of rotating vortices by the fluid flowing through the surface of an object. These vortices will continuously be generated and shed as the fluid flows. When the flow rate changes, the shedding frequency of the vortices will also change accordingly, thus forming a Karman vortex street. The shedding of vortices is related to factors such as the properties of the fluid, the size of the flow rate, the shape and size of the surface of the object, etc. Based on this principle, we install a semicircular iron sheet 43 that can change its shape at the front end of the internal heat exchange tube 3 to act as a flow barrier in the formation of the Karman vortex street. When the temperature of the high-temperature liquid flowing in is too high or too low, we need to control the temperature conversion size in each heat exchange cavity while keeping the stroke unchanged. At this time, we can control the temperature of the input high-temperature liquid and the difference between the temperature of the predetermined temperature to be lowered, and then rotate the rotating handle 41 to drive the traction rope 44 on the traction rod 45 to shrink toward the middle, further driving the semicircular iron sheet 43 to gather toward the middle, thereby changing the contact area between the semicircular iron sheet 43 and the fluid. According to the principle of Karman vortex street, the shape and size of the surface of an object can affect the shedding speed of the vortex. A smaller cylindrical diameter will result in a higher vortex shedding frequency, while a larger diameter will result in a lower vortex shedding frequency. In addition, the surface roughness of the object will also affect the shedding speed of the vortex. The rougher the surface, the easier it is to form a vortex, thereby accelerating the shedding of the vortex. Due to the change in the shape of the semicircular iron sheet 43, the shedding speed of the vortex will also change, that is, change the contact time between the vortex and the vertical heat exchange tube, and ultimately change the time and efficiency of the heat exchange. When the temperature of the input liquid is high, under the condition of a certain heat exchange stroke, it is necessary to cool down faster, so the semicircular iron sheet 43 can be placed in a completely relaxed state, that is, the state with the largest contact area. At this time, the frequency of vortex shedding is the lowest, which allows the higher temperature liquid to surround the vertical heat exchange tube for a longer time, increasing the heat exchange time and frequency, and improving the heat exchange efficiency, so as to reduce a lot of temperature within a limited stroke; when the temperature of the input liquid is low, under the condition of a certain heat exchange stroke, it is necessary to cool down more slowly, so the semicircular iron sheet 43 can be tightened by rotating the handle 41 to reduce the contact area. At this time, the frequency of vortex shedding is high, which allows the lower temperature liquid to stay on the vertical heat exchange tube for a shorter time, so as to prevent repeated heat exchange in the final heat exchange and reduce waste. The outer edge of the ratchet 42 is equipped with a buckle 5, and the lower part of the buckle 5 is equipped with a column 51. When the contact area of ​​the semicircular iron sheet 43 needs to be adjusted, the semicircular iron sheet 43 is adjusted to an appropriate shape by rotating the handle 41 and then locked by the buckle 5 to ensure that the shape of the semicircular iron sheet 43 does not change.

[0033] Embodiment 2: Please refer to Figure 10. The variable-section water-dividing assembly 4 can be a cylindrical column with an arbitrary cross-section shape. In addition to changing the frontal area of ​​the iron sheet, a second embodiment is provided for changing the shedding speed and frequency of the vortex street by changing the contact area with the water flow. The variable-section water-dividing assembly 4 is set as a column with an arbitrary cross-section. When the frontal area needs to be changed, the variable-section water-dividing assembly 4 is rotated so that different directions of the column with an arbitrary cross-section face the water flow, thereby changing the frontal area in contact with the water flow, further changing the shedding speed and frequency of the vortex street, and ultimately changing the speed and efficiency of heat exchange.

[0034] Working Principle: The working principle of this nuclear power plant heat exchange recovery device is designed based on the Karman vortex street principle. Specifically, when the device is working, cooling water is introduced into the heat exchange water inlet 32. The cooling water exchanges heat with the heat energy generated by the nuclear power plant through the internal heat exchange tube 3, thereby converting the heat energy into the internal energy of the cooling water, and then discharged through the heat exchange outlet 31. In this process, the high-temperature liquid flowing into the interior of the device will form a Karman vortex street effect behind the variable-section water distribution component 4 due to the obstruction of the variable-section water distribution component 4. Vortexes will form one by one behind the iron sheet. The center position of these vortexes is exactly located at the position of the vertical heat exchange tube, thereby generating strong vortices on the surface of the vertical heat exchange tube, so that the high-temperature liquid undergoes a longer and more complete surrounding heat exchange on the surface of the vertical heat exchange tube, thereby enhancing the heat exchange efficiency between the high-temperature liquid and the internal heat exchange tube 3 and improving the effect of heat energy recovery. At the same time, for liquids with higher or lower temperatures, the contact area of ​​the semicircular iron sheet 43 can be adjusted to affect the time of vortex generation and shedding, further control the contact time between the liquid and the vertical heat exchange tube, control the heat exchange efficiency, reduce incomplete heat exchange and repeated heat exchange, and reduce waste.

[0035] It should be noted that, in this document, relational terms such as first and second, etc., are used only to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any actual relationship or order between these entities or operations. Moreover, the terms "comprises," "comprising," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or device comprising a series of elements includes not only those elements, but also other elements not explicitly listed, or elements inherent to such process, method, article, or device. In the absence of further limitations, an element defined by the phrase "comprising a ..." does not exclude the presence of other identical elements in the process, method, article, or device comprising the element.

[0036] While embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that various changes, modifications, substitutions, and variations may be made to these embodiments without departing from the principles and spirit of the invention, and that the scope of the invention is defined by the appended claims and their equivalents.

Claims

1. A heat exchange recovery device for a nuclear power plant, characterized in that: The invention comprises an outer shell (1) with a trapezoidal cross section, an internal heat exchange tube (3), and a variable cross-section water distribution component (4) that adjusts the water-facing cross section by rotating or deforming its width. The closed side and the open side of the outer shell (1) are respectively processed with a water inlet (13) and a water outlet (12). The closed side inside the outer shell is provided with a variable cross-section water distribution component (4) that blocks water from the water inlet. The internal heat exchange tube (3) is arranged inside the outer shell (1). The overall shape of the internal heat exchange tube (3) is V-shaped and is adapted to the gradient opening arrangement of the outer shell (1), that is, the V-shaped top end of the internal heat exchange tube (3) is installed on the shorter side of the outer shell (3), and the V-shaped open end of the internal heat exchange tube (3) is installed on the longer side of the outer shell (3).

2. A heat exchange type heat recovery device for a nuclear power plant according to claim 1, characterized in that: The variable cross-section water-dividing assembly (4) comprises a rotating handle (41), a ratchet (42), a semicircular iron sheet (43), a traction rope (44) and a traction rod (45); the semicircular iron sheet (43) faces the water inlet (13); two ends of the semicircular iron sheet (43) are connected to the traction rod (45) via the traction rope (44); a ratchet is mounted on the top of the traction rod (45); a rotating handle (41) is mounted on the upper end of the ratchet; the rotating handle (41) can drive the traction rod (45) and the ratchet to rotate.

3. A heat exchange type heat recovery device for a nuclear power plant according to claim 1, characterized in that: The variable cross-section water distribution component (4) may be in the shape of a cylindrical column with a cross-section in any shape.

4. A heat exchange type heat recovery device for a nuclear power plant according to claim 1, characterized in that: At least two outer shells (1) are provided, and a single outer shell (1) is divided by a partition (11) processed inside the shell, and the partition (11) divides the shell into a plurality of trapezoids of the same shape, and the longer side of the trapezoid is connected to the shorter side of another trapezoid. Adjacent outer shells (1) are installed with external connection pipes (2) arranged side by side corresponding to the water inlet (13) and the water outlet (12).

5. A heat exchange type recovery device for heat energy in a nuclear power plant according to claim 3, characterized in that: The number of water outlets (12) and water inlets (13) on the outer shell (1) is the same and they are evenly arranged and distributed in the longitudinal direction, and the water outlets (12) and water inlets (13) correspond to each other one by one.

6. A heat exchange type heat recovery device for a nuclear power plant according to claim 2, characterized in that: A buckle (5) is mounted on the outer edge of the ratchet wheel, and a column (51) is mounted on the lower part of the buckle (5).

7. A heat exchange type heat recovery device for a nuclear power plant according to claim 1, characterized in that: The internal heat exchange pipe (3) comprises a vertical heat exchange pipe (33), a heat exchange water inlet (32) and a heat exchange water outlet (31); the vertical heat exchange pipe (33) of the internal heat exchanger is composed of a whole connected S-shaped coil; the heat exchange water inlet (32) is located at the upper end of the outer shell (1), and the heat exchange water outlet (31) is located at the lower end of the outer shell (1).

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