Containment pressure suppression filtration and venting system for floating nuclear power platform

Abstract

The application provides a containment pressure-suppression filtration discharge system for a floating nuclear power platform, comprising a containment, a first discharge valve, a first discharge pipeline, a first nozzle, a first-stage pressure-suppression water tank, a second-stage pressure-suppression water tank, an expansion tank, a second discharge valve, a filtration cabin, a second nozzle, an air cooler, a radiation monitor, a passive residual heat removal water tank, a first stop valve and a second stop valve. The application can realize efficient removal of airborne radioactive substances (aerosol, inorganic iodine and organic iodine) by setting multiple radioactive removal means in series, including two-stage bubbling water washing, static mixer cutting bubbles, high-efficiency metal fiber filtration, silver zeolite filtration and the like, and reduce the radioactive influence of containment overpressure discharge on the environment under severe accident conditions. The air cooler arranged on the filtration discharge pipeline condenses the discharge steam, and the condensate returns to the filtration cabin by means of gravity difference, so that the long-term passive effective operation of the water washer can be realized.

Description

Technical Field

[0001] This invention belongs to the field of dedicated safety facilities and radiation protection technology for nuclear power plants, and specifically relates to a containment pressure suppression and filtration emission system for floating nuclear power platforms. Background Technology

[0002] As the compartment in an offshore nuclear power platform that houses high-energy, high-radioactivity equipment and pipelines such as reactors and primary loop systems, the containment vessel is the last safety barrier to prevent the release of radioactive materials into the external environment after a breach accident. Therefore, ensuring its integrity is of great importance.

[0003] For marine nuclear power plants and floating power plants, the free volume of the containment vessel is much smaller than that of a nuclear power plant containment vessel due to overall resource constraints. When a rupture occurs in the primary loop of the containment vessel, a large amount of high-temperature, high-pressure coolant flashes and is released into the containment vessel, causing a rapid increase in pressure. If the pressure cannot be reduced quickly, the containment pressure will rise rapidly within tens of seconds and exceed its design pressure. Given the extremely high mass-energy release rate in the initial stage of a containment rupture accident, relying solely on the spray system and passive containment cooling system is insufficient to meet the pressure reduction requirements of the containment vessel.

[0004] Currently, the mainstream containment filtration and emission systems in nuclear power plants mainly consist of two stages: wet Venturi scrubbing and dry metal fiber filtration. With prolonged operation of the filtration and emission system, the high-temperature, high-pressure emission steam and the decay heat of radioactive materials remaining in the scrubbing solution continuously heat the solution. Once the scrubbing solution reaches its saturation temperature, its volume will decrease or even evaporate completely, severely impacting the operating efficiency of the filtration and emission system.

[0005] Therefore, improving a containment pressure suppression and filtration emission system for floating nuclear power platforms to meet the needs of rapid depressurization of the containment and efficient removal of radioactive materials after an accident, and solving the problem of reduced washing liquid after long-term operation of existing nuclear power filtration emission devices, has become an urgent technical problem to be solved. Summary of the Invention

[0006] This invention provides a containment pressure suppression and filtration emission system for floating nuclear power platforms, which can meet the needs of rapid depressurization of the containment and efficient removal of radioactive materials after an accident on a floating nuclear power platform, and solve the problem of reduced washing liquid after long-term operation of existing nuclear power filtration emission devices.

[0007] In this embodiment of the invention, a containment pressure suppression and filtration discharge system for a floating nuclear power platform is provided. The system comprises: a containment, a first discharge valve, a first discharge pipe, a first nozzle, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, an expansion chamber, a second discharge valve, a filtration chamber, a second nozzle, an air cooler, a radioactivity monitor, a passive residual heat discharge tank, a first shut-off valve, and a second shut-off valve.

[0008] The containment vessel is connected to the first-stage pressure-suppressing water chamber via the first discharge valve, the first discharge pipe, and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are connected via the second discharge pipe and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are respectively loaded with a mixed solution for absorbing iodine in the exhaust gas. The first shut-off valve is provided between the first-stage pressure-suppressing water chamber and the expansion chamber and the containment vessel.

[0009] The expansion chamber and the filtration chamber are connected via the second discharge valve. The filtration chamber includes a steam-water separator and a metal fiber filter layer for capturing the most penetrating aerosol particles that are difficult to remove by water washing. The filtration chamber is connected to the air cooler via a condensate return pipeline. The passive waste heat discharge tank is connected to the condensate return pipeline via the second shut-off valve.

[0010] The radioactive monitoring instrument is used to monitor the radioactive dose released into the environment and to monitor the system's ability to filter radioactive materials. A burst membrane structure is provided between the radioactive monitoring instrument and the air cooler.

[0011] When the pressure inside the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank is higher than the containment pressure, the first shut-off valve is opened to depressurize the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank. When the pressure inside the containment is higher than the pressure inside the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank, the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank perform pressure suppression and water washing functions.

[0012] Furthermore, the system is configured with at least a series of radioactive removal devices including a two-stage bubbling water washing structure, a static mixer bubble-cutting structure, a high-efficiency metal fiber filtration structure, and a silver zeolite filtration structure, for removing radioactive substances including aerosols, inorganic iodine, and organic iodine-borne substances.

[0013] Furthermore, the pipeline containing the rupture membrane structure is equipped with a parallel pipeline with a shut-off valve, which is used to manually open the shut-off valve on the parallel pipeline when the rupture membrane structure fails to open.

[0014] Furthermore, the opening pressure of the rupture membrane structure is the same as the opening pressure of the second discharge valve.

[0015] Furthermore, the system's discharge pipeline is equipped with a flow-limiting orifice plate to restrict the discharge flow rate. One end of the flow-limiting orifice plate is connected to the radioactivity monitor, and the other end is connected to the burst membrane structure.

[0016] Furthermore, the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank are respectively loaded with a mixed solution for absorbing iodine in the emitted gas, comprising:

[0017] The mixed solution is a mixture of sodium iodide hydroxide and sodium thiosulfate, which absorbs iodine in the emitted gas through a chemical reaction.

[0018] Furthermore, a silver zeolite filter for effectively removing methyl iodine from the exhaust gas is provided downstream of the metal fiber filter layer to reduce the radioactivity of the exhaust gas.

[0019] Furthermore, the excess condensate generated by the air-cooled filter discharge steam in the system flows into the passive waste heat discharge tank, which serves as a heat sink for the passive waste heat discharge system to remove the heat released from the primary loop and extend the effective operating time of the system.

[0020] Furthermore, the air cooler is arranged horizontally and inclined downwards, and the condensation rate of the air cooler is controlled by the regulating damper of the chimney duct above the air cooler.

[0021] Furthermore, the system also includes: a high-pressure drug replenishment device;

[0022] The high-pressure dosing device is used to add sodium hydroxide and sodium sulfate solutions to the filter chamber to compensate for the concentration changes of the washing liquid in the filter chamber caused by evaporation.

[0023] The beneficial effects of this invention are as follows:

[0024] As can be seen from the above scheme, the embodiments of the present invention provide a containment pressure suppression and filtration discharge system for floating nuclear power platforms, including: a containment, a first discharge valve, a first discharge pipe, a first nozzle, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, an expansion chamber, a second discharge valve, a filtration chamber, a second nozzle, an air cooler, a radioactivity monitor, a passive residual heat discharge tank, a first shut-off valve, and a second shut-off valve. When the pressure inside the first-stage pressure suppression water tank, the second-stage pressure suppression water tank, and the expansion chamber is higher than the containment pressure, the first shut-off valve is opened to release pressure. When the pressure inside the containment is higher than the pressure inside the first-stage pressure suppression water tank and the second-stage pressure suppression water tank, the first-stage pressure suppression water tank and the second-stage pressure suppression water tank perform pressure suppression and water washing functions. The technical solution of the present invention can meet the needs of rapid depressurization of the containment and efficient removal of radioactive materials after an accident on a floating nuclear power platform, and solve the problem of water washing liquid reduction that occurs after long-term operation of existing nuclear power filtration discharge devices. Attached Figure Description

[0025] Figure 1 This is a schematic diagram illustrating the structure of a containment pressure suppression and filtration emission system for a floating nuclear power platform, according to an embodiment of the present invention.

[0026] In the diagram, 1 is the containment vessel, 2 is the first discharge valve, 3 is the first discharge pipe, 4 is the first nozzle, 5 is the first-stage pressure-suppressing water chamber, 6 is the second-stage pressure-suppressing water chamber, 7 is the expansion chamber, 8 is the second discharge valve, 9 is the filtration chamber, 10 is the second nozzle, 11 is the static mixer, 12 is the steam-water separator, 13 is the metal fiber filter layer, 14 is the first shut-off valve, 19 / 21 / 23 / 25 are the second shut-off valves, 15 is the silver zeolite filter, 16 is the air cooler, 17 is the chimney duct, 18 is the regulating damper, 18 is the condensate return pipe, 20 is the passive residual heat discharge tank, 22 is the high-pressure replenishment device, 24 is the rupture membrane, 26 is the flow-limiting orifice plate, and 27 is the radioactivity monitor. Detailed Implementation

[0027] To make the objectives, technical solutions, and advantages of this invention clearer, the technical solutions of the embodiments of this invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some, not all, of the embodiments of this invention. Based on the embodiments of this invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of this invention.

[0028] like Figure 1 As shown, Figure 1 This is a schematic diagram illustrating the structure of a containment pressure suppression and filtration emission system for a floating nuclear power platform, according to an embodiment of the present invention.

[0029] Figure 1Among them, a containment pressure suppression and filtration discharge system for a floating nuclear power platform is characterized in that the system includes: a containment, a first discharge valve, a first discharge pipe, a first nozzle, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, an expansion chamber, a second discharge valve, a filtration chamber, a second nozzle, an air cooler, a radioactivity monitor, a passive residual heat discharge tank, a first shut-off valve, and a second shut-off valve.

[0030] The containment vessel is connected to the first-stage pressure-suppressing water chamber via the first discharge valve, the first discharge pipe, and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are connected via the second discharge pipe and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are respectively loaded with a mixed solution for absorbing iodine in the exhaust gas. The first shut-off valve is provided between the first-stage pressure-suppressing water chamber and the expansion chamber and the containment vessel.

[0031] The expansion chamber and the filtration chamber are connected via the second discharge valve. The filtration chamber includes a steam-water separator and a metal fiber filter layer for capturing the most penetrating aerosol particles that are difficult to remove by water washing. The filtration chamber is connected to the air cooler via a condensate return pipeline. The passive waste heat discharge tank is connected to the condensate return pipeline via the second shut-off valve.

[0032] The radioactive monitoring instrument is used to monitor the radioactive dose released into the environment and to monitor the system's ability to filter radioactive materials. A burst membrane structure is provided between the radioactive monitoring instrument and the air cooler.

[0033] When the pressure inside the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank is higher than the containment pressure, the first shut-off valve is opened to depressurize the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank. When the pressure inside the containment is higher than the pressure inside the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank, the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank perform pressure suppression and water washing functions.

[0034] In this embodiment of the invention, after a LOCA accident occurs in the containment, when the pressure inside the containment reaches the opening pressure of the first discharge valve, the first discharge valve automatically opens. The steam-air mixture inside the containment enters the first pressure-suppressing water chamber through the nozzle via bubbling. By utilizing the efficient heat exchange of direct contact condensation through bubbling, the pressure of the containment is rapidly reduced, thereby reducing the pressure peak of the containment in the early stage of the accident. The containment pressure-suppressing filtration and discharge system adopts a two-stage bubbling water washing method, which increases the submersion depth of the pressure-suppressing nozzle, significantly increasing the residence time of gas in the liquid phase and effectively improving the removal efficiency of gaseous radioactive materials.

[0035] In this embodiment of the invention, the pipeline containing the rupture membrane structure is provided with a parallel pipeline equipped with a shut-off valve, which is used to manually open the shut-off valve on the parallel pipeline when the rupture membrane structure fails to open.

[0036] In one embodiment of the present invention, the opening pressure of the rupture membrane structure is the same as the opening pressure of the second discharge valve. When the pressure in the first-stage pressure-suppressing tank, the second-stage pressure-suppressing tank, and the expansion tank reaches the opening pressure of the second discharge valve, the second discharge valve and the rupture membrane structure open sequentially, thereby achieving the filtration and discharge of high-temperature and high-pressure gases inside the containment, the first-stage pressure-suppressing tank, the second-stage pressure-suppressing tank, and the expansion tank. The pipeline containing the rupture membrane structure is connected in parallel. If the rupture membrane structure fails to open, the second shut-off valve on the parallel pipeline can be manually opened.

[0037] In one embodiment of the present invention, the system's discharge pipeline is provided with a flow-limiting orifice plate for limiting the discharge flow rate. One end of the flow-limiting orifice plate is connected to the radioactivity monitor, and the other end is connected to the burst membrane structure.

[0038] In one embodiment of the present invention, the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank are respectively loaded with a mixed solution for absorbing iodine in the emitted gas, comprising:

[0039] The mixed solution is a mixture of sodium iodide hydroxide and sodium thiosulfate, which absorbs iodine in the emitted gas through a chemical reaction.

[0040] In one embodiment of the present invention, a silver zeolite filter for effectively removing methyl iodine from the exhaust gas is disposed downstream of the metal fiber filter layer to reduce the radioactivity of the exhaust gas.

[0041] In one embodiment of the present invention, the air cooler is arranged horizontally and inclined downwards, and the condensation rate of the air cooler is controlled by a regulating damper in the chimney duct above the air cooler.

[0042] In one embodiment of the present invention, the system further includes: a high-pressure drug delivery device;

[0043] The high-pressure dosing device is used to add sodium hydroxide and sodium sulfate solutions to the filter chamber to compensate for the concentration changes of the washing liquid in the filter chamber caused by evaporation.

[0044] In this embodiment of the invention, a multi-stage bubbling depressurization water scrubbing scheme is employed, which can fully utilize the water resources in the depressurization tank to achieve rapid depressurization of the containment and efficient retention of airborne radioactive materials under limited resource conditions. The scheme utilizes existing compartments to install static mixers and metal fiber filter layers, which can further improve the filtration efficiency of airborne radioactive materials while reducing excessive overall resource consumption. By installing an air cooler on the filter discharge pipeline to condense the discharged vapors, the condensate returns to the filter compartment via gravity difference, enabling long-term passive and effective operation of the scrubber.

[0045] In this embodiment of the invention, excess condensate generated by the filtered exhaust steam through air cooling can flow into a passive waste heat discharge tank as a heat sink for the passive waste heat discharge system, carrying away the heat released from the primary loop, extending the effective operating time of the system, and mitigating the consequences of an accident. By setting up multiple radioactive removal methods in series, including two-stage bubbling water washing, static mixer bubble cutting, high-efficiency metal fiber filtration, and silver zeolite filtration, efficient removal of airborne radioactive materials (aerosols, inorganic iodine, and organic iodine) can be achieved, reducing the radioactive impact of containment overpressure emissions on the environment under severe accident conditions.

[0046] In another embodiment of the present invention, a containment pressure suppression and filtration discharge system for a floating nuclear power platform comprises: a containment 1, a first discharge valve 2, a second discharge valve 8, a first discharge pipe 3, a first nozzle 4, a second nozzle 10, a first-stage pressure suppression water tank 5, a second-stage pressure suppression water tank 6, an expansion chamber 7, a filtration chamber 9, a static mixer 11, a steam-water separator 12, a metal fiber filter layer 13, a silver zeolite filter 15, an air cooler 16, a chimney duct 17, a regulating damper 18, a condensate return pipe 19, a passive residual heat discharge tank 21, a high-pressure replenishment device 22, a rupture membrane structure 24, a flow-limiting orifice plate 26, a radioactivity monitor 27, a first shut-off valve 14, and second shut-off valves 19 / 21 / 23 / 25.

[0047] Under normal operating conditions, the first shut-off valve 14 and the second shut-off valves 19 / 21 / 23 / 25 are all closed. The entire containment pressure suppression filtration and venting system is purged with nitrogen to reduce the risk of hydrogen explosion within the system under accident conditions.

[0048] When a LOCA (Local Occurrence-Oriented Collapse) accident occurs in the primary circuit of containment 1, the containment pressure rises to the opening pressure of the first vent valve 2, which then opens. The high-temperature, high-pressure steam-air mixture inside containment 1 enters the first-stage pressure-reducing water chamber 5 through the first vent pipe 3 and the first nozzle 4. Utilizing the efficient heat exchange through direct contact condensation via bubbling, rapid depressurization of containment 1 is achieved, thereby reducing the initial pressure peak of the containment during the accident.

[0049] The first-stage pressure chamber 5 and the second-stage pressure chamber 6 contain a mixed solution of sodium hydroxide and sodium thiosulfate, which can absorb iodine in the exhaust gas through a chemical reaction. During the bubbling wash in the first-stage pressure chamber 5, the gas exiting the nozzle is in a high-speed jet state, and the liquid phase is entrained into the gas plume, forming a large number of entrained droplets. Aerosols are captured and removed by the entrained droplets through inertial collision, interception, Brownian diffusion, and other capture mechanisms, and radioactive iodine is absorbed by the entrained droplets. Simultaneously, the exhaust gas has a high vapor content, and vapor condensation significantly improves the aerosol removal efficiency. As the energy of the exhaust gas dissipates, the gas flow pattern changes from a jet to a bubble swarm. Radioactive materials diffuse and migrate within the bubbles to the bubble surface and are then retained by the liquid phase. After bubbling condensation in the first-stage pressure chamber, the exhaust gas mainly consists of non-condensable gases. The exhaust gas then enters the second-stage pressure chamber 6 for bubbling wash. The exhaust gas, after two stages of bubbling condensation and washing, enters the expansion chamber 7.

[0050] The opening pressure of the rupture membrane structure 24 downstream of the air cooler 16 is the same as the opening pressure of the second discharge valve 8. When the pressure in the first-stage pressure-suppressing water chamber 5, the second-stage pressure-suppressing water chamber 6, and the expansion chamber 7 reaches the opening pressure of the second discharge valve 8, the second discharge valve 8 and the rupture membrane 24 open sequentially, achieving the filtration and discharge of high-temperature and high-pressure gases in the containment 1, the first-stage pressure-suppressing water chamber 5, the second-stage pressure-suppressing water chamber 6, and the expansion chamber 7. The pipeline containing the rupture membrane structure 24 is equipped with parallel pipelines. When the rupture membrane fails to open, the second shut-off valve 25 on the parallel pipeline can be manually opened.

[0051] High-temperature, high-pressure gas enters filtration chamber 9, which contains a mixed solution of sodium hydroxide and sodium thiosulfate. The exhaust gas is bubbled into the washing liquid through nozzle 10. Under the action of static mixer 11, large bubbles are broken into smaller bubbles, thereby improving the washing efficiency of radioactive materials. After passing through the bottom washing filter, the exhaust gas passes through steam-water separator 12 to reach the metal fiber filter layer 13 located at the top of the chamber, achieving the capture of the most easily penetrating aerosol particles that are difficult to remove through washing. A silver zeolite filter 15 is installed downstream of the fiber filter layer to effectively remove methyl iodine from the exhaust gas, further reducing the radioactivity of the exhaust gas.

[0052] After passing through the silver zeolite filter 15, the exhaust gas enters the air cooler 16, which is horizontally inclined downwards. The exhaust gas is condensed by the air outside the tubes. The air flows vertically upwards, sweeping across the heat exchange tubes of the air cooler 16. Heated, the air density decreases, and it flows due to the suction force of the chimney duct 17. The condensate returns to the filter chamber 9 due to gravity difference. Simultaneously, sodium hydroxide and sodium sulfate solutions are added to the filter chamber via the high-pressure dosing device 22 to compensate for the concentration changes of the washing liquid in the filter chamber caused by evaporation. Excess condensate can flow into the passive waste heat discharge tank 21 to extend the effective operating time of the system and mitigate the consequences of an accident. The condensation rate of the air cooler can be controlled by the regulating damper 18 of the chimney duct 17.

[0053] A flow-limiting orifice plate 26 is installed on the filter discharge pipeline to limit the discharge flow rate, ensuring that the discharge flow rate is basically consistent with the system design flow rate for a period of time, thus guaranteeing the system's filtration efficiency. A radioactivity monitor 27 is used to monitor the radioactive dose released into the environment and can also be used to monitor the system's filtration capacity for radioactive materials.

[0054] With the commissioning of other dedicated safety systems, when the pressure in the first-stage pressure-reducing tank 5, the second-stage pressure-reducing tank 6, or the expansion tank 7 is higher than the pressure inside the containment 1, the first shut-off valve 14 is opened to depressurize the pressure-reducing tank and the expansion tank. When the pressure inside the containment 1 is again higher than the pressure in the first-stage pressure-reducing tank 5 and the second-stage pressure-reducing tank 6, the first-stage pressure-reducing tank 5 and the second-stage pressure-reducing tank 6 will once again perform pressure suppression and water washing functions.

[0055] In another embodiment of the present invention, the system is configured to include at least a series of radioactive removal devices comprising a two-stage bubbling water washing structure, a static mixer bubble-cutting structure, a high-efficiency metal fiber filtration structure, and a silver zeolite filtration structure, for removing radioactive substances including aerosols, inorganic iodine, and organic iodine-borne substances.

[0056] In the system, the filtered exhaust steam flows into the passive waste heat discharge tank through the excess condensate generated by the air cooling system. This tank serves as a heat sink for the passive waste heat discharge system, carrying away the heat released from the primary loop and extending the effective operating time of the system.

[0057] This invention provides a containment pressure suppression and filtration discharge system for floating nuclear power platforms, comprising: a containment vessel, a first discharge valve, a first discharge pipe, a first nozzle, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, an expansion chamber, a second discharge valve, a filtration chamber, a second nozzle, an air cooler, a radioactivity monitor, a passive residual heat discharge tank, a first shut-off valve, and a second shut-off valve. When the pressure inside the first-stage pressure suppression water tank, the second-stage pressure suppression water tank, and the expansion chamber is higher than the containment pressure, the first shut-off valve is opened to release pressure. When the pressure inside the containment is higher than the pressure inside the first-stage and second-stage pressure suppression water tanks, the first-stage and second-stage pressure suppression water tanks perform pressure suppression and flushing functions. This system can meet the needs of rapid depressurization of the containment vessel and efficient removal of radioactive materials after an accident on a floating nuclear power platform, and solves the problem of reduced flushing fluid after long-term operation of existing nuclear power plant filtration discharge devices.

[0058] This invention employs a series of multiple radioactive removal methods, including two-stage bubbling water washing, static mixer bubble cutting, high-efficiency metal fiber filtration, and silver zeolite filtration, to achieve highly efficient removal of airborne radioactive materials (aerosols, inorganic iodine, and organic iodine), reducing the radioactive impact of containment overpressure emissions on the environment under severe accident conditions. By installing an air cooler on the filtration discharge pipeline to condense the emitted vapors, the condensate returns to the filtration chamber via gravity difference, enabling long-term passive and effective operation of the water scrubber.

[0059] The above are preferred embodiments of the present invention. It should be noted that, for those skilled in the art, several improvements and modifications can be made without departing from the principle of the present invention, and these improvements and modifications should also be considered within the scope of protection of the present invention.

Claims

1. A containment pressure suppression and filtration emission system for a floating nuclear power platform, characterized in that, The system includes: a containment vessel, a first discharge valve, a first discharge pipe, a first nozzle, a first-stage pressure-suppressing water chamber, a second-stage pressure-suppressing water chamber, an expansion chamber, a second discharge valve, a filter chamber, a second nozzle, an air cooler, a radioactivity monitor, a passive waste heat discharge tank, a first shut-off valve, and a second shut-off valve. The containment vessel is connected to the first-stage pressure-suppressing water chamber via the first discharge valve, the first discharge pipe, and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are connected via the second discharge pipe and the first nozzle. The first-stage pressure-suppressing water chamber and the second-stage pressure-suppressing water chamber are respectively loaded with a mixed solution for absorbing iodine in the exhaust gas. The first shut-off valve is provided between the first-stage pressure-suppressing water chamber and the expansion chamber and the containment vessel. The expansion chamber and the filtration chamber are connected via the second discharge valve. The filtration chamber includes a steam-water separator and a metal fiber filter layer for capturing the most penetrating aerosol particles that are difficult to remove by water washing. The filtration chamber is connected to the air cooler via a condensate return pipeline. The passive waste heat discharge tank is connected to the condensate return pipeline via the second shut-off valve. The radioactive monitoring instrument is used to monitor the radioactive dose released into the environment and to monitor the system's ability to filter radioactive materials. A burst membrane structure is provided between the radioactive monitoring instrument and the air cooler. When the pressure inside the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank is higher than the containment pressure, the first shut-off valve is opened to depressurize the first-stage pressure-suppressing water tank, the second-stage pressure-suppressing water tank, and the expansion tank. When the pressure inside the containment is higher than the pressure inside the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank, the first-stage pressure-suppressing water tank and the second-stage pressure-suppressing water tank perform pressure suppression and water washing functions.

2. The containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, The system is configured to include at least a series of radioactive removal devices consisting of a two-stage bubbling water washing structure, a static mixer for cutting bubbles, a high-efficiency metal fiber filter structure, and a silver zeolite filter structure, for removing radioactive substances including aerosols, inorganic iodine, and organic iodine-borne substances.

3. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, The opening pressure of the rupture membrane structure is the same as the opening pressure of the second discharge valve. The pipeline where the rupture membrane structure is located is equipped with a parallel pipeline with a shut-off valve, which is used to manually open the shut-off valve on the parallel pipeline when the rupture membrane structure fails to open.

4. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, The system's discharge pipeline is equipped with a flow-limiting orifice plate to restrict the discharge flow rate. One end of the flow-limiting orifice plate is connected to the radioactivity monitor, and the other end is connected to the burst membrane structure.

5. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, The first-stage and second-stage pressure-suppressing water tanks are respectively loaded with a mixed solution for absorbing iodine in the emitted gas, including: The mixed solution is a mixture of sodium iodide hydroxide and sodium thiosulfate, which absorbs iodine in the emitted gas through a chemical reaction.

6. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, A silver zeolite filter is installed downstream of the metal fiber filter layer to effectively remove methyl iodine from the exhaust gas, thereby reducing the radioactivity of the exhaust gas.

7. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, In the system, the filtered exhaust steam flows into the passive waste heat discharge tank through the excess condensate generated by the air cooling system. This tank serves as a heat sink for the passive waste heat discharge system, carrying away the heat released from the primary loop and extending the effective operating time of the system.

8. A containment pressure suppression and filtration discharge system for a floating nuclear power platform according to any one of claims 1 to 7, characterized in that, The air cooler is arranged horizontally and inclined downwards, and the condensation rate of the air cooler is controlled by the regulating damper of the chimney duct above the air cooler.

9. A containment pressure suppression and filtration emission system for a floating nuclear power platform according to claim 1, characterized in that, The system also includes: a high-pressure drug delivery device; The high-pressure dosing device is used to add sodium hydroxide and sodium sulfate solutions to the filter chamber to compensate for the concentration changes of the washing liquid in the filter chamber caused by evaporation.

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