Residual Heat Removal System of Marine Nuclear Power Platform

Abstract

The present invention relates to the technical field of nuclear reactor, and provides a residual heat removal system for a marine nuclear power platform, comprising: a heat exchange channel, a residual heat circulation loop and a bubble generating device; an inlet and an outlet are arranged on the heat exchange channel along the extending direction of the heat exchange channel, and the outlet is arranged above the inlet; a cooling fluid is configured to be introduced into the heat exchange channel; the residual heat circulation loop is configured to introduce a coolant of the reactor, and the coolant is used for coupled heat transfer with the cooling fluid; an air outlet of the bubble generating device is communicated with the heat exchange channel; bubbles generated by the bubble generating device are used for forming a mixture with the cooling fluid in the heat exchange channel, and the mixture is discharged through the outlet. By means of the bubbles generated by the bubble generating device, the heat exchange efficiency between the coolant and the cooling fluid is improved when the reactor is shut down, so that the residual heat of the reactor core can be quickly discharged.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear reactors, and particularly relates to a residual heat removal system for a marine nuclear power platform. Background Art

[0002] A marine nuclear power platform is an organic combination of nuclear power technology and modern ship technology. Its core is to convert controllable nuclear fission energy into heat energy and then electrical energy in sequence through a nuclear power device, which provides energy guarantee for marine resource development, remote islands, etc.; after the reactor in the marine nuclear power platform shuts down, although the fission chain reaction in the core has terminated, the delayed neutrons continue to cause partial nuclear fission, and due to the decay of fission products, neutron capture products, etc., a large amount of residual heat will still be generated in the core for a long time after shutdown. In order to ensure the safety of the core, it is necessary to remove the residual heat in time.

[0003] There is a heat exchange channel between the core heat source of the existing reactor and the marine heat sink, and low-temperature seawater in the marine heat sink is introduced into the heat exchange channel; after the reactor shuts down, the residual heat generated by the core is transferred to the seawater in the heat exchange channel, and the temperature of the seawater in the heat exchange channel rises and the density decreases. By using the driving force generated by the density difference between the high-temperature seawater and the low-temperature seawater, the circulation flow of seawater between the marine heat sink and the heat exchange channel is realized, so as to take away the residual heat generated by the core through the flow of seawater. The existing such circulation method depends on the temperature difference between the seawater in the heat exchange channel and the seawater in the marine heat sink. Especially in the initial stage of reactor shutdown, it takes a certain amount of time for the seawater in the heat exchange channel to heat up. At this time, the temperature difference between the seawater in the heat exchange channel and the seawater in the marine heat sink is small, the density difference is also small, the circulation of seawater is relatively slow, and the residual heat of the core is difficult to be quickly removed. Summary of the Invention

[0004] The present invention provides a residual heat removal system for a marine nuclear power platform to solve or improve the problem that the existing reactor has difficulty in quickly removing the residual heat of the core.

[0005] The present invention provides a residual heat removal system for a marine nuclear power platform, including: a heat exchange channel, a residual heat circulation loop, and a bubble generating device; an inlet and an outlet are provided on the heat exchange channel along the extending direction of the heat exchange channel, and the outlet is arranged above the inlet; the heat exchange channel is used for introducing a cooling fluid; the residual heat circulation loop is used for introducing a coolant of the reactor, and the coolant is used for coupled heat transfer with the cooling fluid; an air outlet of the bubble generating device is communicated with the heat exchange channel; the bubbles generated by the bubble generating device are used to form a mixture with the cooling fluid in the heat exchange channel, and the mixture is discharged through the outlet.

[0006] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, the bubble generating device includes a gas source and a nozzle assembly; the nozzle assembly includes nozzles, and a plurality of the nozzles are arranged circumferentially along the heat exchange channel; one end of each nozzle is communicated with the gas source, and an air outlet of the bubble generating device is formed at the other end of each nozzle.

[0007] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, a plurality of the nozzle assemblies are provided, and the plurality of nozzle assemblies are arranged at intervals along the extending direction of the heat exchange channel; an axis of each nozzle forms a preset angle with an axis of the heat exchange channel; the plurality of preset angles decrease in sequence along the extending direction of the heat exchange channel.

[0008] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, each nozzle is conical, and an inner diameter of one end of each nozzle is larger than an inner diameter of the other end of each nozzle.

[0009] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, the bubble generating device further includes: a control valve, a U-shaped pipe and a check valve; the gas source includes a gas storage tank, an air outlet of the gas storage tank is communicated with one end of the control valve, the other end of the control valve is communicated with one end of the U-shaped pipe, the other end of the U-shaped pipe is communicated with one end of the check valve, and the other end of the check valve is communicated with one ends of the plurality of nozzles; the control valve is used for controlling the conduction or blockage between the gas storage tank and the plurality of nozzles.

[0010] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, the heat exchange channel includes a shell-and-tube heat exchanger; the shell-and-tube heat exchanger includes a shell and a tube bundle; the tube bundle is arranged in the shell, and a heat exchange cavity is formed between an inner side wall of the shell and an outer side wall of the tube bundle; a liquid inlet of the heat exchange channel is communicated with one end of the tube bundle, and a liquid outlet of the heat exchange channel is communicated with the other end of the tube bundle; the residual heat circulation loop is communicated with the heat exchange cavity.

[0011] According to a residual heat removal system of an ocean nuclear power platform provided by the present invention, the residual heat circulation loop includes a coolant accommodation cavity, and a coolant in the coolant accommodation cavity is used for coupling heat transfer with a core of a reactor; the coolant accommodation cavity is provided with a first inlet and a first outlet, and the first inlet is communicated with the first outlet; the shell is provided with a second inlet and a second outlet, and the second inlet and the second outlet are respectively communicated with the heat exchange cavity; the first outlet is communicated with the second inlet, and the second outlet is communicated with the first inlet; the second inlet and the second outlet are arranged along the extending direction of the heat exchange channel, and the second inlet is arranged above the second outlet.

[0012] According to a residual heat removal system for a marine nuclear power platform provided by the present invention, a first solenoid valve is provided between the first outlet and the second inlet, and a second solenoid valve is provided between the second outlet and the first inlet.

[0013] According to a residual heat removal system for a marine nuclear power platform provided by the present invention, it further includes: an engine room and a main pump; a steam generator is provided in the engine room, one end of the steam generator is communicated with the first outlet, the other end of the steam generator is communicated with one end of the main pump, and the other end of the main pump is communicated with the first inlet; the steam generator is used to generate steam in the engine room.

[0014] According to a residual heat removal system for a marine nuclear power platform provided by the present invention, it further includes: a safety shell; the shell-and-tube heat exchanger, the residual heat circulation loop, the bubble generating device, the core of the reactor, the engine room and the main pump are arranged in the safety shell.

[0015] In a residual heat removal system for a marine nuclear power platform provided by the present invention, by setting a bubble generating device, the cooling fluid enters the heat exchange channel through the liquid inlet, and after the reactor shuts down, the bubble generating device is turned on; the residual heat generated by the core of the reactor is gradually transferred to the coolant, and the temperature of the coolant gradually rises. The high-temperature coolant flows into the residual heat circulation loop, and the heat of the high-temperature coolant is gradually transferred to the cooling fluid. The coolant with reduced temperature returns to the residual heat circulation loop and flows towards the core; as the temperature of the cooling fluid gradually rises, its density gradually decreases, so that the cooling fluid near the liquid outlet and the cooling fluid near the liquid inlet form a density difference. Based on the driving force generated by the density difference between the fluids, the cooling fluid with a smaller density flows upward and is discharged through the liquid outlet, so that the cooling fluid establishes a density difference through heat exchange, thereby realizing the natural circulation of the cooling fluid. This natural circulation formed by heat exchange takes a long time; in the present invention, the bubbles generated by the bubble generating device are injected into the heat exchange channel, and the average density of the mixture formed by the bubbles and the cooling fluid in the heat exchange channel decreases, so that the mixture has a tendency to flow upward. Furthermore, the average density of the fluid near the liquid outlet is smaller, and the average density of the fluid near the liquid inlet is larger, thus quickly establishing a density difference between the fluid at the liquid outlet and the fluid at the liquid inlet. Under the action of the driving force generated by the density difference, the cooling fluid in the heat exchange channel realizes rapid flow, avoiding the need for a long-time heat exchange method to establish the density difference of the cooling fluid at the initial stage of reactor shutdown, and realizing the rapid start of the natural circulation of the cooling fluid in the heat exchange channel at the initial stage of shutdown, improving the heat exchange efficiency between the cooling fluid and the high-temperature coolant, and ensuring the safety and reliability of the reactor. Description of the Drawings

[0016] To more clearly illustrate the technical solutions in the present invention or the prior art, the following briefly introduces the attached drawings required for the description of the embodiments or the prior art. Obviously, the attached drawings in the following description are some embodiments of the present invention. For those of ordinary skill in the art, without creative efforts, other attached drawings can also be obtained based on these drawings.

[0017] Figure 1 is a schematic structural diagram of the residual heat removal system of the marine nuclear power platform provided by the present invention;

[0018] Figure 2 is provided by the present invention Figure 1 is an enlarged schematic structural diagram at A;

[0019] Figure 3 is one of the schematic structural diagrams of the nozzle assembly provided by the present invention;

[0020] Figure 4 is another schematic structural diagram of the nozzle assembly provided by the present invention;

[0021] Figure 5 is a schematic structural diagram of the nozzle provided by the present invention;

[0022] Reference numerals:

[0023] 1: heat exchange channel; 2: bubble generating device; 21: gas storage tank;

[0024] 22: nozzle assembly; 221: nozzle; 23: control valve;

[0025] 24: U-shaped tube; 25: check valve; 3: shell-and-tube heat exchanger;

[0026] 4: reactor; 41: reactor core; 51: first solenoid valve;

[0027] 52: second solenoid valve; 6: engine room; 7: main pump;

[0028] 8: safety housing. Detailed implementation manners

[0029] To make the objectives, technical solutions, and advantages of the present invention clearer, the following clearly and completely describes the technical solutions in the present invention with reference to the attached drawings in the present invention. Obviously, the described embodiments are some, but not all, of the embodiments of the present invention. All other embodiments obtained by those of ordinary skill in the art based on the embodiments in the present invention without creative efforts belong to the scope of protection of the present invention.

[0030] In the description of the embodiments of the present invention, it should be noted that the orientation or positional relationship indicated by the terms "center", "longitudinal", "transverse", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc. is based on the orientation or positional relationship shown in the drawings. It is only for the convenience of describing the embodiments of the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be construed as a limitation on the embodiments of the present invention. In addition, the terms "first", "second", and "third" are only used for descriptive purposes and should not be construed as indicating or implying relative importance.

[0031] In the description of the embodiments of the present invention, it should be noted that unless otherwise clearly specified and limited, the terms "connected" and "coupled" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be directly connected or indirectly connected through an intermediate medium. For those of ordinary skill in the art, the specific meanings of the above terms in the embodiments of the present invention can be understood according to specific circumstances.

[0032] The following Figures 1 to 5 describes a residual heat removal system for a marine nuclear power platform provided by the present invention.

[0033] As Figures 1 to 5 shown, the residual heat removal system shown in this embodiment includes: a heat exchange channel 1, a residual heat circulation loop, and a bubble generating device 2.

[0034] An inlet and an outlet are provided on the heat exchange channel 1 along the extension direction of the heat exchange channel 1, and the outlet is provided above the inlet; a cooling fluid is configured to flow through the heat exchange channel 1; the residual heat circulation loop is configured to flow through the coolant of the reactor, and the coolant is used for coupled heat transfer with the cooling fluid; the gas outlet of the bubble generating device 2 is communicated with the heat exchange channel; the bubbles generated by the bubble generating device are used to form a mixture with the cooling fluid in the heat exchange channel, and the mixture is discharged through the outlet.

[0035] Specifically, in the residual heat removal system shown in this embodiment, by setting up a bubble generating device, the cooling fluid enters the heat exchange channel 1 through the liquid inlet. After the reactor shuts down, the bubble generating device 2 is turned on; the residual heat generated by the core 41 of the reactor 4 is gradually transferred to the coolant, and the temperature of the coolant gradually rises. The high-temperature coolant flows into the residual heat circulation loop, and the heat of the high-temperature coolant is gradually transferred to the cooling fluid. The coolant with reduced temperature returns to the residual heat circulation loop and flows towards the core 41; as the temperature of the cooling fluid gradually rises, its density gradually decreases, so that the cooling fluid near the liquid outlet forms a density difference with the cooling fluid near the liquid inlet. Based on the driving force generated by the density difference between the fluids, the cooling fluid with a smaller density flows upward and is discharged through the liquid outlet, so that the cooling fluid establishes a density difference through heat exchange, thereby realizing the natural circulation of the cooling fluid. This natural circulation formed by heat exchange takes a long time; in this embodiment, the bubbles generated by the bubble generating device 2 are injected into the heat exchange channel, and the average density of the mixture formed by the bubbles and the cooling fluid in the heat exchange channel decreases, so that the mixture has a tendency to flow upward. Furthermore, the average density of the fluid near the liquid outlet is smaller, and the average density of the fluid near the liquid inlet is larger, so that a density difference is quickly established between the fluid at the liquid outlet and the fluid at the liquid inlet. Under the action of the driving force generated by the density difference, the cooling fluid in the heat exchange channel 1 realizes rapid flow, avoiding the need for a heat exchange method that takes a long time to establish the density difference of the cooling fluid at the initial stage of reactor shutdown, and realizing the rapid start of the natural circulation of the cooling fluid in the heat exchange channel 1 at the initial stage of shutdown, improving the heat exchange efficiency between the cooling fluid and the high-temperature coolant, and ensuring the safety and reliability of the reactor 4.

[0036] It should be noted here that the residual heat removal system of the marine nuclear power platform shown in this embodiment can be applied to the marine nuclear power platform, which is used to provide energy for the development of marine resources and remote islands; among them, the cooling fluid is seawater and the coolant is light water; the heat exchange channel 1 is arranged along the depth direction of the seawater. Both the liquid inlet and the liquid outlet are arranged in the seawater, and the position of the liquid inlet is deeper, and the position of the liquid outlet is shallower, that is, the liquid outlet is located above the liquid inlet, so that the seawater with reduced density can smoothly flow upward to the liquid outlet, thereby realizing the natural circulation between the deep seawater and the shallow seawater through the heat exchange channel 1.

[0037] It should be noted that the extending direction of the heat exchange channel 1 described in this embodiment refers to the direction from the liquid inlet towards the liquid outlet. Based on the arrangement form of the heat exchange channel along the depth direction of the seawater, it can be understood that the extending direction of the heat exchange channel 1 is the vertical direction from bottom to top.

[0038] Among them, the definition of coupled heat transfer is the heat transfer between the solid wall and the fluids on both sides. In this embodiment, the coupled heat transfer is the heat transfer between seawater and light water through the side wall of the heat exchange channel. During the process of coupled heat transfer, seawater flows in the heat exchange channel 1, and light water flows in the waste heat recycling loop. Therefore, the flows of seawater and light water are independent of each other, and seawater and light water do not come into contact.

[0039] Preferably, as Figure 3 and Figure 4 shown, the bubble generating device 2 shown in this embodiment includes a gas source and a nozzle assembly 22; the nozzle assembly 22 includes nozzles 221, and there are multiple nozzles 221, which are arranged circumferentially along the heat exchange channel 1; one end of the nozzle 221 is communicated with the gas source, and the gas outlet of the bubble generating device 2 is formed at the other end of the nozzle 221.

[0040] Specifically, after the reactor shuts down, the gas output by the gas source is sprayed into the liquid outlet through the nozzles 221. Based on the arrangement form of the multiple nozzles 221, multiple bubbles can be generated simultaneously by the multiple nozzles 221 to form a bubble group at the liquid outlet. The bubble group dissolves into the seawater near the liquid outlet, reducing the density of the seawater at the liquid outlet. The seawater with a smaller density continues to flow upward, driving the seawater with a larger density at the liquid inlet to flow towards the liquid outlet, realizing the natural circulation of seawater based on the density difference.

[0041] Preferably, as Figure 2 and Figure 3 shown, there are multiple nozzle assemblies 22 shown in this embodiment, and the multiple nozzle assemblies 22 are arranged at intervals along the extension direction of the heat exchange channel 1; the axis of the nozzle 221 forms a preset angle with the axis of the heat exchange channel 1; the multiple preset angles decrease in sequence along the extension direction of the heat exchange channel 1.

[0042] Specifically, the preset angle shown in this embodiment is an acute angle. By setting the preset angle as an acute angle, the spraying direction of the bubble group is approximately the same as the flow direction of the seawater, so that the bubble group can play a certain traction role on the seawater during the spraying process, further increasing the flow rate of the seawater, thereby improving the heat exchange efficiency between the seawater and the light water.

[0043] In one embodiment, as Figure 2As shown, there are two nozzle assemblies 22, and correspondingly two groups of bubble swarms are ejected; the preset angle α formed by the nozzles of the upper nozzle assembly 22 is smaller, so the ejection distance of the upper bubble swarm is far, and the preset angle β formed by the nozzles of the lower nozzle assembly 22 is larger, so the ejection distance of the lower bubble swarm is closer. Therefore, the lower bubble swarm is denser. The dense bubble swarm can significantly reduce the average density of seawater, thereby significantly increasing the density difference between the seawater at the liquid inlet and the seawater at the liquid outlet, enhancing the driving force of the natural circulation of seawater, and further accelerating the flow of seawater in the heat exchange channel 1.

[0044] Preferably, as Figure 5 shown, the nozzle 221 shown in this embodiment is conical, and the inner diameter of one end of the nozzle 221 is larger than the inner diameter of the other end of the nozzle 221.

[0045] Specifically, along the direction of gas flow, the cross-sectional area for the gas to pass through in the nozzle 221 gradually decreases, so the flow rate of the gas in the nozzle 221 gradually increases, increasing the initial velocity of the bubbles ejected from the nozzle 221, and further enhancing the traction effect of the bubble swarm on the seawater flow, thereby increasing the flow rate of seawater in the heat exchange channel.

[0046] Preferably, as Figure 1 shown, the bubble generating device 2 shown in this embodiment further includes: a control valve 23, a U-shaped tube 24 and a check valve 25; the gas source includes a gas storage tank 21, the air outlet of the gas storage tank 21 is communicated with one end of the control valve 23, the other end of the control valve 23 is communicated with one end of the U-shaped tube 24, the other end of the U-shaped tube 24 is communicated with one end of the check valve 25, and the other end of the check valve 25 is communicated with one end of a plurality of nozzles 221; the control valve 23 is used to control the conduction or blockage between the gas storage tank 21 and the plurality of nozzles 221.

[0047] Specifically, the control valve 23 shown in this embodiment is preferably a normally open solenoid valve. During the normal operation of the reactor 4, the normally open solenoid valve is in the energized state. At this time, the normally open solenoid valve is closed, and the gas storage tank 21 and the plurality of nozzles 221 are blocked; after the reactor 4 shuts down, the normally open solenoid valve is in the de-energized state. At this time, the normally open solenoid valve is opened, and the gas storage tank 21 and the plurality of nozzles 221 are communicated. The gas storage tank 21 provides gas for the plurality of nozzles 221, and bubbles are ejected from the plurality of nozzles 221; after the gas storage tank 21 supplies gas for a period of time, the pressure in the gas storage tank 21 gradually decreases, and the U-shaped tube 24 and the check valve 25 can prevent seawater from flowing back into the gas storage tank 21, wherein the U-shaped opening of the U-shaped tube 24 is arranged downward; at the same time, the seawater in the heat exchange channel 1 has gradually established a density difference through heat exchange. Therefore, at this time, the natural circulation of seawater can be completed without the auxiliary effect of the bubble generating device 2.

[0048] Preferably, as Figure 1As shown in the figure, the heat exchange channel 1 shown in this embodiment includes a shell-and-tube heat exchanger 3; the shell-and-tube heat exchanger 3 includes a shell and a tube bundle; the tube bundle is arranged inside the shell, and a heat exchange cavity is formed between the inner side wall of the shell and the outer side wall of the tube bundle; the liquid inlet of the heat exchange channel 1 is communicated with one end of the tube bundle, and the liquid outlet of the heat exchange channel 1 is communicated with the other end of the tube bundle; the waste heat circulation loop is communicated with the heat exchange cavity.

[0049] Specifically, seawater at a lower temperature flows into the tube bundle, light water at a higher temperature flows into the heat exchange cavity, and the seawater at a lower temperature completes coupled heat transfer with the light water at a higher temperature through the side wall of the tube bundle.

[0050] Preferably, as Figure 1 shown in the figure, the waste heat circulation loop shown in this embodiment includes a coolant accommodation cavity, and the coolant in the coolant accommodation cavity is used for coupled heat transfer with the core 41 of the reactor 4; the coolant accommodation cavity is provided with a first inlet and a first outlet, and the first inlet is communicated with the first outlet; the shell is provided with a second inlet and a second outlet, and the second inlet and the second outlet are respectively communicated with the heat exchange cavity; the first outlet is communicated with the second inlet, and the second outlet is communicated with the first inlet; the second inlet and the second outlet are arranged along the extending direction of the heat exchange channel 1, and the second inlet is arranged above the second outlet.

[0051] Specifically, the waste heat of the core 41 heats the light water in the coolant accommodation cavity, and the high-temperature light water sequentially enters the heat exchange cavity through the first outlet and the second inlet. After the high-temperature light water exchanges heat with the seawater, its temperature decreases, and the low-temperature light water sequentially returns to the coolant accommodation cavity through the second outlet and the first inlet to realize the recycling of the light water; among them, based on the fact that the density of the high-temperature light water is less than that of the low-temperature light water, the high-temperature light water has a tendency to flow upward. By arranging the second inlet above the second outlet, it is convenient for the high-temperature light water to flow smoothly into the second inlet and the low-temperature light water to flow smoothly out of the second outlet.

[0052] Preferably, as Figure 1 shown in the figure, a first solenoid valve 51 is arranged between the first outlet and the second inlet, and a second solenoid valve 52 is arranged between the second outlet and the first inlet.

[0053] Specifically, the first solenoid valve 51 and the second solenoid valve 52 shown in this embodiment are preferably normally open solenoid valves. During the normal operation of the reactor 4, the normally open solenoid valves are energized, the normally open solenoid valves are closed, the connection between the first outlet and the second inlet is blocked, and the connection between the second outlet and the first inlet is blocked. At this time, the waste heat circulation loop is in a blocked state; after the reactor 4 shuts down, the normally open solenoid valves are de-energized, the normally open solenoid valves are opened, so that the connection between the first outlet and the second inlet is conducted, and the connection between the second outlet and the first inlet is conducted, thereby conducting the waste heat circulation loop.

[0054] Preferably, as Figure 1As shown in the figure, the residual heat removal system of the marine nuclear power platform shown in this embodiment further includes: a machine room 6 and a main pump 7; a steam generator is provided in the machine room 6, one end of the steam generator is communicated with the first outlet, the other end of the steam generator is communicated with one end of the main pump 7, and the other end of the main pump 7 is communicated with the first inlet; the steam generator is used to form steam in the machine room 6.

[0055] Specifically, the residual heat removal system of the marine nuclear power platform shown in this embodiment is applied to a pressurized water reactor. The relatively high-temperature light water flows into the steam generator, and the steam generated by the steam generator is used to drive the impeller to rotate to generate electricity. The cooled light water returns to the coolant cavity through the first inlet under the action of the main pump 7 to realize the recycling of the light water.

[0056] Preferably, as Figure 1 shown, a first normally closed solenoid valve is provided between the first outlet and the machine room 6 shown in this embodiment, a check valve is provided between the machine room 6 and the main pump 7, and a second normally closed solenoid valve is provided between the main pump 7 and the first inlet.

[0057] Specifically, during the normal operation of the reactor 4, the first normally closed solenoid valve and the second normally closed solenoid valve are energized, the first normally closed solenoid valve and the second normally closed solenoid valve are opened, the first outlet and the machine room 6 are conducted, and the main pump 7 and the first inlet are conducted; after the reactor 4 shuts down, the first normally closed solenoid valve and the second normally closed solenoid valve are de-energized, the first normally closed solenoid valve and the second normally closed solenoid valve are closed, the first outlet and the machine room 6 are blocked, the main pump 7 and the first inlet are blocked, the main pump 7 stops working, and the check valve can prevent the light water from flowing through the main pump 7 to the machine room 6. At this time, both the first solenoid valve 51 and the second solenoid valve 52 are in a conducting state, and the light water flows through the first solenoid valve 51 to the heat exchange cavity, and the light water in the heat exchange cavity flows through the second solenoid valve 52 to the coolant cavity.

[0058] Preferably, as Figure 1 shown, the residual heat removal system of the marine nuclear power platform shown in this embodiment further includes: a safety housing 8; a shell-and-tube heat exchanger 3, a residual heat circulation loop, a bubble generating device 2, the core 41 of the reactor 4, the machine room 6 and the main pump 7 are arranged in the safety housing 8.

[0059] Specifically, the inside of the safety housing 8 is completely isolated from the external environment of the safety housing 8. The safety housing 8 can not only protect various equipment inside the safety housing 8, but also prevent the leakage of radioactive substances in the reactor.

[0060] Finally, it should be noted that the above embodiments are only used to illustrate the technical solutions of the present invention, rather than to limit it; although the present invention has been described in detail with reference to the foregoing embodiments, those of ordinary skill in the art should understand that they can still modify the technical solutions described in the foregoing embodiments, or perform equivalent replacements for some of the technical features; and these modifications or replacements do not make the essence of the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the embodiments of the present invention.

Claims

1. A residual heat removal system for a marine nuclear power platform, characterized in that, Comprising: A heat exchange channel, an inlet and an outlet are provided on the heat exchange channel along the extending direction of the heat exchange channel, the outlet is arranged above the inlet; a cooling fluid is used to be introduced into the heat exchange channel; A waste heat recycling loop, the waste heat recycling loop is used to introduce the coolant of the reactor, and the coolant is used to couple and transfer heat with the cooling fluid; A bubble generating device, an air outlet of the bubble generating device is communicated with the heat exchange channel; the bubbles generated by the bubble generating device are used to form a mixture with the cooling fluid in the heat exchange channel, and the mixture is discharged through the outlet; The bubble generating device includes a gas source and a nozzle assembly; the nozzle assembly includes nozzles, a plurality of the nozzles are arranged circumferentially along the heat exchange channel; one end of the nozzle is communicated with the gas source, and the air outlet of the bubble generating device is formed at the other end of the nozzle; a plurality of the nozzle assemblies are arranged at intervals along the extending direction of the heat exchange channel; the axis of the nozzle forms a preset angle with the axis of the heat exchange channel; a plurality of the preset angles decrease in sequence along the extending direction of the heat exchange channel; the nozzle is conical, and the inner diameter of one end of the nozzle is larger than the inner diameter of the other end of the nozzle.

2. The waste heat discharge system of the marine nuclear power platform according to claim 1, wherein The bubble generating device further includes: a control valve, a U-shaped pipe and a check valve; The gas source includes a gas storage tank, an air outlet of the gas storage tank is communicated with one end of the control valve, the other end of the control valve is communicated with one end of the U-shaped pipe, the other end of the U-shaped pipe is communicated with one end of the check valve, and the other end of the check valve is communicated with one ends of a plurality of the nozzles; The control valve is used to control the conduction or blockage between the gas storage tank and a plurality of the nozzles.

3. The waste heat discharge system of the marine nuclear power platform according to any one of claims 1 to 2, wherein The heat exchange channel includes a shell-and-tube heat exchanger; The shell-and-tube heat exchanger includes a shell and a tube bundle; the tube bundle is arranged in the shell, and a heat exchange cavity is formed between the inner side wall of the shell and the outer side wall of the tube bundle; The inlet of the heat exchange channel is communicated with one end of the tube bundle, and the outlet of the heat exchange channel is communicated with the other end of the tube bundle; the waste heat recycling loop is communicated with the heat exchange cavity.

4. The waste heat discharge system of the marine nuclear power platform according to claim 3, wherein The waste heat recycling loop includes a coolant accommodation cavity, and the coolant in the coolant accommodation cavity is used to couple and transfer heat with the reactor core; The coolant accommodation cavity is provided with a first inlet and a first outlet, the first inlet is communicated with the first outlet; the shell is provided with a second inlet and a second outlet, the second inlet and the second outlet are respectively communicated with the heat exchange cavity; the first outlet is communicated with the second inlet, and the second outlet is communicated with the first inlet; The second inlet and the second outlet are arranged along the extending direction of the heat exchange channel, and the second inlet is arranged above the second outlet.

5. The residual heat removal system of the marine nuclear power platform according to claim 4, wherein a first solenoid valve is provided between the first outlet and the second inlet, and a second solenoid valve is provided between the second outlet and the first inlet.

6. The residual heat removal system of the marine nuclear power platform according to claim 4, wherein it further comprises: an engine room and a main pump; a steam generator is provided in the engine room, one end of the steam generator is communicated with the first outlet, the other end of the steam generator is communicated with one end of the main pump, and the other end of the main pump is communicated with the first inlet; the steam generator is used for generating steam in the engine room.

7. The residual heat removal system of the marine nuclear power platform according to claim 6, wherein it further comprises: a safety housing; the shell-and-tube heat exchanger, the waste heat circulation loop, the bubble generating device, the core of the reactor, the engine room and the main pump are arranged in the safety housing.

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