Nuclear reactor safety devices and nuclear reactor equipment

Abstract

This invention discloses a nuclear reactor safety device and nuclear reactor equipment. The nuclear reactor includes a pressure vessel containing a reactor core, and the pressure vessel is located within a containment vessel. The nuclear reactor safety device includes a sealed chamber, a delivery assembly, and a control unit. The sealed chamber is located outside the containment vessel. The input end of the delivery assembly is connected to the pressure vessel, and the output end of the delivery assembly is connected to the sealed chamber. The control unit is located within the delivery assembly and is used to control the on / off state of the delivery assembly. Specifically, when the reactor core is in a normal state, the control unit controls the delivery assembly to be in a disconnected state; when the reactor core is in a leaking state, the control unit controls the delivery assembly to be in a connected state. This method directly delivers radioactive gas from the pressure vessel to the sealed chamber, reducing the amount of radioactive material entering the containment vessel or other containment devices, improving the safety of the containment vessel, and reducing the release of radioactive material caused by containment leakage or subsequent failure.

Description

Technical Field

[0001] This application relates to the field of nuclear reactor technology, and more particularly to a nuclear reactor safety device and nuclear reactor equipment. Background Technology

[0002] Following a severe accident in a nuclear reactor, a large amount of high-temperature steam and a gas-liquid mixture are generated. Simultaneously, the reactor core fuel melts, and radioactive fission products from the fuel are released into the pressure vessel's interior. The steam and gas-liquid mixture become the primary carriers of radioactive materials, releasing them into the containment vessel. Leaks can occur when the pressure difference between the inside and outside of the containment vessel is positive. If the concentration of the mixture within the containment vessel is also high, radioactive materials will be released into the external environment along with the leaking gases. Later, the containment vessel's seal may be further compromised. If the concentration of radioactive materials in a large area of ​​the containment vessel is already high, even more severe releases can occur, causing serious environmental impacts. Summary of the Invention

[0003] This application aims to address at least one of the technical problems existing in the prior art or related technologies.

[0004] Therefore, a first aspect of the present invention provides a nuclear reactor safety device.

[0005] A second aspect of the present invention provides a nuclear reactor apparatus.

[0006] In view of the above, according to the first aspect of the technical solution of this application, a nuclear reactor safety device is proposed. The nuclear reactor includes a pressure vessel, and a reactor core is disposed inside the pressure vessel. The pressure vessel is located within a containment structure. The nuclear reactor safety device includes a sealed chamber, a delivery assembly, and a control component. The sealed chamber is located outside the containment structure. The input end of the delivery assembly is connected to the pressure vessel, and the output end of the delivery assembly is connected to the sealed chamber. The control component is located within the delivery assembly and is used to control the on / off state of the delivery assembly. Specifically, when the reactor core is in a normal state, the control component controls the delivery assembly to be in a disconnected state; when the reactor core is in a leaking state, the control component controls the delivery assembly to be in a connected state.

[0007] In some of the technical solutions provided in this application, optionally, the conveying assembly includes: a conveying pipeline and a blower, the input end of the conveying pipeline is connected to a pressure vessel, the output end of the conveying pipeline is connected to a sealed chamber, and the blower is connected to the conveying pipeline, and the blower is used to blow the gas from the input end of the conveying pipeline to the output end of the conveying pipeline.

[0008] Optionally, in some of the technical solutions provided in this application, a basket is provided inside the pressure vessel, which divides the pressure vessel into a first chamber and a second chamber. The delivery pipeline includes a first delivery pipeline and a second delivery pipeline. The two ends of the first delivery pipeline are used to connect the first chamber and the sealed chamber, and the two ends of the second delivery pipeline are used to connect the second chamber and the sealed chamber.

[0009] Optionally, in some of the technical solutions provided in this application, the conveying pipeline may further include a third conveying pipeline, wherein the output end of the first conveying pipeline and the output end of the second conveying pipeline are both connected to the input end of the third conveying pipeline, and the output end of the third conveying pipeline is connected to the sealing chamber.

[0010] Optionally, in some of the technical solutions provided in this application, the nuclear reactor safety device also includes a radioactive monitoring device. The radioactive monitoring device is located on the outer surface of the pressure vessel and is used to monitor the gas radiation value of the gas leaking into the pressure vessel. When the gas radiation value is greater than or equal to the radiation threshold, the reactor core is in a leaking state, and when the gas radiation value is less than the radiation threshold, the reactor core is in a normal state.

[0011] Optionally, in some of the technical solutions provided in this application, the nuclear reactor safety device includes a spray device located inside a sealed chamber, which is used to spray a cooling alkaline solution into the sealed chamber.

[0012] Optionally, in some of the technical solutions provided in this application, the nuclear reactor safety device also includes a heat exchange device, which is located inside the sealed chamber and is used to absorb heat inside the sealed chamber.

[0013] Optionally, in some of the technical solutions provided in this application, the nuclear reactor safety device may also include a discharge assembly, which is connected to the sealed chamber. The inlet of the discharge assembly is connected to the interior of the sealed chamber, and the outlet of the discharge assembly is connected to the exterior of the sealed chamber.

[0014] In some technical solutions provided in this application, optionally, the emission components include: an emission pipeline, a cooling and pressure reducing component, and / or a dehumidifier, and / or an aerosol filter, and / or a gas filter. Both the inlet and outlet are located in the emission pipeline. The cooling and pressure reducing component is located within the emission pipeline and is used to reduce the temperature and pressure within the emission pipeline. The dehumidifier is located within the emission pipeline and is used to intercept mist droplets within the emission pipeline. The aerosol filter is located within the emission pipeline and is used to intercept aerosol particles within the emission pipeline. The gas filter is located within the emission pipeline and has multiple filter holes for absorbing inert gases within the emission pipeline.

[0015] The second aspect of this application provides a nuclear reactor device, which includes a pressure vessel and a nuclear reactor safety device provided by any of the first aspects of this application, wherein the input end of the delivery component of the nuclear reactor safety device is connected to the pressure vessel.

[0016] Compared with the prior art, the present invention has at least the following beneficial effects:

[0017] Because the melting process of reactor core fuel takes time, and the radioactive materials in the fuel are released gradually, the concentration of radioactive materials in the radioactive gas varies greatly in different locations. Since the concentration of radioactive materials in the pressure vessel is high, the radioactive gas from the pressure vessel is directly transferred to a sealed chamber with better sealing capabilities than the containment vessel. The sealed chamber absorbs the high concentration of radioactive gas, effectively reducing the amount of radioactive material entering the containment vessel or other containment devices, improving the efficiency of radioactive gas handling, expanding the capacity to contain radioactive gas, enhancing the safety of the containment vessel, and reducing the release of radioactive materials into the environment due to containment leaks or subsequent failures. Attached Figure Description

[0018] Various other advantages and benefits will become apparent to those skilled in the art upon reading the following detailed description of preferred embodiments. The accompanying drawings are for illustrative purposes only and are not intended to limit the scope of this application. Furthermore, the same reference numerals denote the same parts throughout the drawings. In the drawings:

[0019] Figure 1 One of the structural schematic diagrams of a nuclear reactor safety device provided in this application for use in nuclear reactor equipment;

[0020] Figure 2 A second schematic diagram of the structure of a nuclear reactor safety device for use in a nuclear reactor facility, provided in this application;

[0021] Figure 3 A schematic diagram of the structure of an emission assembly according to an embodiment of this application;

[0022] Figure 4 A schematic flowchart illustrating the steps of a control method for a nuclear reactor safety device according to an embodiment of this application.

[0023] in, Figures 1 to 4 The correspondence between the reference numerals and component names in the attached drawings is as follows:

[0024] 10 Nuclear reactor safety devices, 100 Sealed chamber, 200 Conveyor assembly, 210 Conveyor pipeline, 211 First conveyor pipeline, 212 Second conveyor pipeline, 213 Third conveyor pipeline, 220 Fan, 300 Control components, 400 Radioactivity monitoring device, 500 Spray system, 600 Heat exchanger, 700 Emission assembly, 710 Emission pipeline, 711 Inlet, 712 Outlet, 720 Cooling and depressurization assembly, 730 Aerosol filter, 740 Gas filter, 750 Dehumidifier, 741 Filter pore, 20 Pressure vessel, 21 First chamber, 22 Second chamber, 30 Containment vessel, 40 Suspended platform. Detailed Implementation

[0025] To better understand the above technical solutions, the technical solutions of the embodiments of this application will be described in detail below with reference to the accompanying drawings and specific embodiments. It should be understood that the embodiments of this application and the specific features in the embodiments are detailed descriptions of the technical solutions of the embodiments of this application, rather than limitations on the technical solutions of this application. In the absence of conflict, the embodiments of this application and the technical features in the embodiments can be combined with each other.

[0026] The first aspect of this application provides a nuclear reactor safety device 10, such as... Figure 1 and Figure 2 As shown, the nuclear reactor includes a pressure vessel 20, within which a reactor core is housed. The pressure vessel 20 is located within a containment building 30. The nuclear reactor safety device 10 includes a sealed chamber 100, a delivery assembly 200, and a control unit 300. The sealed chamber 100 is located outside the containment building 30. The input end of the delivery assembly 200 is connected to the pressure vessel 20, and the output end of the delivery assembly 200 is connected to the sealed chamber 100. The control unit 300 is located within the delivery assembly 200 and is used to control the on / off state of the delivery assembly 200. Specifically, when the reactor core is in a normal state, the control unit 300 controls the delivery assembly 200 to be in a disconnected state; when the reactor core is in a leaking state, the control unit 300 controls the delivery assembly 200 to be in a connected state.

[0027] In this embodiment, the nuclear reactor includes a pressure vessel 20, which houses the nuclear reactor core. In the event of a serious accident and leakage in the nuclear reactor, the core fuel will melt, and some of the radioactive fission products in the core fuel will be released into the internal space of the pressure vessel 20 and adhere to the water vapor and gas-liquid mixture to become radioactive gas. The pressure vessel 20 is covered by a containment vessel 30, which is used to contain the radioactive gas and aerosol leaked from the pressure vessel 20.

[0028] The containment 30 is provided with a sealed chamber 100. The sealed chamber 100 is airtight and can contain radioactive gas, thus isolating the radioactive gas from the external environment and preventing the radioactive gas from spreading into the external environment.

[0029] The two ends of the delivery assembly 200 are connected to the pressure vessel 20 and the sealed chamber 100, respectively. The delivery assembly 200 is equipped with a control element 300 that can switch the on / off state. When the nuclear reactor is operating normally, it is in the normal state, and the control element 300 controls the delivery assembly 200 to be in the off state, separating the pressure vessel 20 and the sealed chamber 100 from each other, so as to prevent gas in the pressure vessel 20 from flowing into the sealed chamber 100 and affecting the normal operation of the pressure vessel 20.

[0030] To prevent leakage, the nuclear reactor is equipped with three barriers. The first barrier is the reactor core (fuel assembly), namely the fuel pellets and cladding. The second barrier is the pressure vessel 20, and the third barrier is the containment building 30. When the nuclear reactor experiences a significant breach of the first barrier and is in a state of leakage and release of radioactive materials, the reactor core is in a leaking state. When the amount of radioactive gas in the pressure vessel 20 reaches a certain level, the control unit 300 controls the delivery assembly 200 to be in a connected state, so that the pressure vessel 20 is connected to the sealed chamber 100. The radioactive gas in the pressure vessel 20 enters the sealed chamber 100 through the delivery assembly 200.

[0031] It should be noted that because the melting process of the reactor core fuel takes time, and the radioactive materials in the fuel are released gradually, the concentration of radioactive materials in the radioactive gas varies greatly in different locations. Since the concentration of radioactive materials in pressure vessel 20 is high, the radioactive gas in pressure vessel 20 is directly transferred to the sealed chamber 100, which has a better sealing capacity than the containment vessel. The sealed chamber 100 absorbs the high concentration of radioactive gas, effectively reducing the amount of radioactive material entering containment vessel 30 or other containment devices, improving the efficiency of radioactive gas handling, expanding the capacity to contain radioactive gas, enhancing the safety of containment vessel 30, and reducing the release of radioactive materials into the environment due to leakage or later failure of containment vessel 30.

[0032] For example, control element 300 may be a valve.

[0033] For example, while ensuring an effective volume, the sealed chamber 100 can be configured with an irregular shape. The volume of the sealed chamber 100 is greater than or equal to 50 times the volume of the pressure vessel 20, and less than the volume of the containment vessel 30. This ensures that the sealed chamber 100 has sufficient capacity to contain radioactive gases while reducing the containment burden on the sealed chamber 100 and lowering its relative volumetric leakage rate. Due to fewer penetrations and structural material gaps, the sealed chamber 100 has good airtightness characteristics. Under the same pressure differential, the relative volumetric leakage rate of the sealed chamber 100 is lower than that of the containment vessel 30, thus ensuring the safety and reliability of the sealed chamber 100.

[0034] For example, the sealed container 100 can serve as a storage facility, and can store high levels of radioactive solid waste, provided that sufficient free space is provided.

[0035] In some embodiments provided in this application, such as Figure 1 and Figure 2 As shown, optionally, the conveying assembly 200 includes: a conveying pipeline 210 and a blower 220. The input end of the conveying pipeline 210 is connected to the pressure vessel 20, and the output end of the conveying pipeline 210 is connected to the sealed chamber 100. The blower 220 is connected to the conveying pipeline 210 and is used to blow the gas from the input end of the conveying pipeline 210 to the output end of the conveying pipeline 210.

[0036] In this embodiment, the two ends of the delivery pipeline 210 are connected to the pressure vessel 20 and the sealed chamber 100, respectively, so that the radioactive gas in the pressure vessel 20 can be discharged into the sealed chamber 100 through the delivery pipeline 210. A blower 220 is installed in the delivery pipeline 210, which blows the gas from the input end of the delivery pipeline 210 to the output end of the delivery pipeline 210, providing power for the radioactive gas in the pressure vessel 20 to be blown into the sealed chamber 100. This shortens the discharge time of the radioactive gas in the pressure vessel 20 and improves the efficiency of radioactive gas discharge.

[0037] For example, a fan 220 is installed in the middle of the delivery pipeline 210. The fan 220 can be installed between the containment 30 and the sealed chamber 100. The fan 220 is connected to its own power supply and the plant power supply respectively. The fan 220 can work normally in a high temperature and high humidity environment.

[0038] In one possible embodiment, when the control unit 300 controls the conveying assembly 200 to be in the connected state, the fan 220 is in the on state, providing pressure head for diversion.

[0039] In another possible embodiment, when the pressure difference between the pressure vessel 20 and the sealed chamber 100 is greater than or equal to the pressure difference threshold, the blower 220 is turned on to draw flow into the sealed chamber 100.

[0040] In some embodiments provided in this application, such as Figure 1 and Figure 2 As shown, optionally, the pressure vessel 20 is provided with a basket 40, which divides the pressure vessel 20 into a first chamber 21 and a second chamber 22. The delivery pipeline 210 includes a first delivery pipeline 211 and a second delivery pipeline 212. The two ends of the first delivery pipeline 211 are used to connect the first chamber 21 and the sealed chamber 100, and the two ends of the second delivery pipeline 212 are used to connect the second chamber 22 and the sealed chamber 100.

[0041] In this embodiment, the basket 40 installed inside the pressure vessel 20 divides the pressure vessel 20 into a first chamber 21 and a second chamber 22. The first chamber 21 is the core inlet front chamber, and the second chamber 22 is the core outlet rear chamber. The basket 40 contains the nuclear reactor core. When a nuclear reaction leaks, the radioactive gas flows toward the first chamber 21 or the second chamber 22.

[0042] The first delivery pipeline 211 and the second delivery pipeline 212 connect the first chamber 21 and the second chamber 22 to the sealed chamber 100 respectively. This ensures that in the event of a leak, the delivery device can quickly discharge the radioactive gas from the pressure vessel 20 regardless of which chamber the radioactive gas flows into, thereby improving the accuracy of the delivery device in discharging the radioactive gas and enhancing the emission effect of the radioactive gas from the pressure vessel 20.

[0043] For example, a fan 220 is provided on both the first conveying pipeline 211 and the second conveying pipeline 212.

[0044] In some embodiments provided in this application, such as Figure 2 As shown, optionally, the conveying pipeline 210 also includes a third conveying pipeline 213, the output end of the first conveying pipeline 211 and the output end of the second conveying pipeline 212 are both connected to the input end of the third conveying pipeline 213, and the output end of the third conveying pipeline 213 is connected to the sealing chamber 100.

[0045] In this embodiment, the output ends of the first delivery pipeline 211 and the second delivery pipeline 212 converge and are connected to the input end of the third delivery pipeline 213. This allows the radioactive gas in the first delivery pipeline 211 and the second delivery pipeline 212 to accumulate and then be delivered to the sealed chamber 100 through the third delivery pipeline 213. As a result, the gas delivery between the delivery pipeline 210 and the sealed chamber 100 can be achieved through only one pipeline, reducing the number of through-pieces connecting the sealed chamber 100, reducing the process difficulty of ensuring the airtightness of the sealed chamber 100, and improving the airtightness and safety of the sealed chamber 100.

[0046] For example, a fan 220 is provided on the third delivery pipeline 213.

[0047] In some embodiments provided in this application, such as Figure 1 and Figure 2 As shown, optionally, the nuclear reactor safety device 10 also includes a radioactivity monitoring device 400. The radioactivity monitoring device 400 is located on the outer surface of the pressure vessel 20. The radioactivity monitoring device 400 is used to monitor the gas radiation value of the gas leaking into the pressure vessel 20. When the gas radiation value is greater than or equal to the radiation threshold, the reactor core is in a leaking state. When the gas radiation value is less than the radiation threshold, the reactor core is in a normal state.

[0048] In this embodiment, since the pressure vessel 20 is in a high-temperature and high-pressure environment, it is not feasible to install a radioactive monitoring device 400. Therefore, the radioactive monitoring device 400 is installed inside the containment 30 and placed on the outer surface of the pressure vessel 20. The radioactive monitoring device 400 can perform non-destructive indirect measurement, allowing it to detect the radiation concentration of the gas inside the pressure vessel 20 even when placed on the outer surface. This enables the monitoring of the radiation value of the gas leaking from the reactor core into the pressure vessel and provides a signal indicating a high concentration of radioactive material within the pressure vessel 20. When the gas radiation value exceeds the radiation threshold, it indicates the presence of excessive radioactive material within the pressure vessel 20, and the reactor core (i.e., the fuel pellets and fuel cladding) is in a state of leakage and radioactive material release. With the reactor core in a leaking state, the control unit 300 controls the delivery assembly 200 to be in a connected state, and the delivery assembly 200 delivers the radioactive gas into the sealed chamber 100. When the gas radiation value is less than the radiation threshold, it indicates that the gas inside the pressure vessel 20 is within a controllable range, the fuel pellets and fuel cladding are temporarily intact, the reactor core is in a normal state, the release of radioactive environment from the nuclear reactor will not be too large, and the control component 300 controls the delivery assembly 200 to be in a disconnected state to ensure the normal operation of the pressure vessel 20.

[0049] The radiation value of the gas inside the pressure vessel 20 is detected by the radioactivity monitoring device 400, thereby determining the radiation status inside the pressure vessel 20. This achieves automated judgment of the radiation status and allows for the release of radioactive gas from the pressure vessel 20 in the early stages of a leak, improving the timeliness and accuracy of leak handling.

[0050] In some embodiments provided in this application, such as Figure 1 and Figure 2 As shown, optionally, the nuclear reactor safety device 10 includes a spray device 500, which is located inside the sealed chamber 100 and is used to spray a cooling alkaline solution into the sealed chamber 100.

[0051] In this embodiment, the sealed chamber 100 is equipped with a spray device 500 capable of spraying a cooling alkaline solution to reduce the temperature and pressure inside the sealed chamber 100 and decrease the volume of radioactive gas inside the sealed chamber 100. Furthermore, radioactive materials can be adsorbed onto droplets in the cooling alkaline solution, causing the radioactive materials to fall to the bottom of the sealed chamber 100 along with the cooling alkaline solution. The alkaline solution can more effectively remove radioactive materials from the radioactive gas, improving the safety and reliability of the sealed chamber 100.

[0052] In some embodiments provided in this application, such as Figure 1 and Figure 2As shown, optionally, the nuclear reactor safety device 10 also includes a heat exchange device 600, which is located inside the sealed chamber 100 and is used to absorb heat inside the sealed chamber 100.

[0053] In this embodiment, a heat exchange device 600 is provided inside the sealed chamber 100. The heat exchange device 600 can absorb the heat inside the sealed chamber 100 to reduce the temperature and pressure inside the sealed chamber 100, reduce the amount of radioactive gas inside the sealed chamber 100, reduce the energy of the radioactive gas inside the sealed chamber 100, and improve the safety of the sealed chamber 100.

[0054] For example, the heat exchange device 600 may be a coil heat exchanger.

[0055] In some embodiments provided in this application, such as Figure 1 and Figure 2 As shown, optionally, the nuclear reactor safety device 10 also includes an emission assembly 700, which is connected to the sealed chamber 100. The inlet 711 of the emission assembly 700 is in communication with the interior of the sealed chamber 100, and the outlet 712 of the emission assembly 700 is in communication with the exterior of the sealed chamber 100.

[0056] In this embodiment, a discharge assembly 700 is provided inside the sealed chamber 100. The inlet 711 and outlet 712 of the discharge assembly 700 are respectively connected to the internal and external environments of the sealed chamber 100, so that the radioactive gas inside the sealed chamber 100 can enter the discharge assembly 700 through the inlet 711 and leave the sealed chamber 100 through the outlet 712. When the gas inside the sealed chamber 100 approaches its capacity limit, the discharge assembly 700 can discharge part of the gas, thereby improving the reliability and safety of the sealed chamber 100.

[0057] In some embodiments provided in this application, such as Figure 3 As shown, optionally, the emission assembly 700 includes: an emission pipe 710, a cooling and depressurization assembly 720, and / or a dehumidifier 750, and / or an aerosol filter 730, and / or a gas filter 740. Both the air inlet 711 and the air outlet 712 are located in the exhaust pipe 710. The cooling and pressure reducing component 720 is located inside the exhaust pipe 710 and is used to reduce the temperature and pressure inside the exhaust pipe 710. The dehumidifying component 750 is located inside the exhaust pipe 710 and is used to intercept mist droplets inside the exhaust pipe 710. The aerosol filter 730 is located inside the exhaust pipe 710 and is used to intercept dust and particles inside the exhaust pipe 710. The gas filter 740 is located inside the exhaust pipe 710 and has multiple filter holes 741, which are used to absorb inert gases inside the exhaust pipe 710.

[0058] In this embodiment, both the air inlet 711 and the air outlet 712 are located in the discharge pipe 710, through which the gas in the sealed chamber 100 is discharged.

[0059] The discharge pipe 710 is equipped with a cooling and depressurization component 720, which includes a heat exchanger that can absorb heat in the discharge pipe 710. Alternatively, the cooling and depressurization component 720 includes an exhaust fan that can accelerate the airflow speed in the discharge pipe 710 to reduce the temperature and pressure in the discharge pipe 710 and improve the safety of the gas in the discharge pipe 710.

[0060] The discharge pipe 710 is equipped with a dehumidifier 750, which contains a moisture-absorbing material. Through physical absorption of droplets, the radioactive gas within the discharge pipe 710 can pass through the dehumidifier 750 and continue flowing. Radioactive media droplets and tritium entrained in the radioactive gas can be intercepted by the moisture-absorbing material, reducing the amount of droplets and tritium discharged to the outside and improving the safety of the gas discharged from the discharge assembly 700. For example, the dehumidifier 750 can be a calcium oxide filter.

[0061] An aerosol filter 730 is provided inside the emission pipe 710. The aerosol filter 730 has micropores, the size of which is smaller than the size of dust and particles. This allows radioactive gas in the emission pipe 710 to pass through the aerosol filter 730 and continue to flow. Radioactive aerosol particles mixed in the radioactive gas can be intercepted by the micropores, reducing the amount of radioactive material discharged into the outside and improving the safety of the gas discharged from the emission assembly 700. For example, the aerosol filter 730 can be a bag filter or a sand pile filter.

[0062] The discharge pipe 710 is equipped with a gas filter 740, which has multiple filter holes 741. The filter holes 741 can absorb and contain some of the radioactive inert gas in the discharge pipe 710, reducing the amount of radioactive material discharged to the outside and improving the safety of the gas discharged by the discharge assembly 700. For example, the gas filter 740 can be a porous gas retention bed.

[0063] A second aspect of this application provides a nuclear reactor apparatus, which includes a pressure vessel 20 and a nuclear reactor safety device 10 provided in any of the first aspects of this application above. The input end of the delivery assembly 200 of the nuclear reactor safety device 10 is connected to the pressure vessel 20.

[0064] In this embodiment, it should be noted that the nuclear reactor equipment includes the nuclear reactor safety device 10 provided in any of the above embodiments of this application, and therefore has all the beneficial technical effects of the nuclear reactor safety device 10. To avoid repetition, it will not be described in detail here.

[0065] The nuclear reactor includes a pressure vessel 20, which contains a nuclear reactor core. The input end of the delivery assembly 200 is connected to the pressure vessel 20, which directly delivers radioactive gas from the pressure vessel 20 to the sealed chamber 100.

[0066] In a specific embodiment, Figure 4 As shown, firstly, based on the radioactivity monitored by the radioactivity monitoring device 400 near the outer surface of the pressure vessel 20, the containment of radioactive materials by the fuel cladding and fuel pellets inside the pressure vessel 20 under the current severe accident conditions is determined. This ensures the radioactivity monitoring device 400 remains usable during the severe accident process. Simultaneously, based on its real-time measurement data, the release of radioactive materials from the pressure vessel 20 into the containment vessel 30 under the current accident development is assessed. Since the release of radioactive materials varies significantly at different times depending on the progress of the accident, the concentration of radioactive materials in the steam and water-gas mixture varies considerably. Upon obtaining a high concentration signal, the valves of the first delivery pipeline 211 outside the basket 40 and the second delivery pipeline 212 inside the basket 40 are opened to guide the high-level radioactive material into the sealed chamber 100.

[0067] Secondly, when the radioactivity level is high, to reduce the release of highly radioactive materials from the pressure vessel 20 into the containment 30 and leakage to the external environment through penetrations or other parts of the containment 30, the valves of the first delivery pipeline 211 and the second delivery pipeline 212 are opened, allowing the highly radioactive materials from the pressure vessel 20 to be diverted into the sealed chamber 100 via the blower 220. During this process, the blower 220 is ensured to have high temperature and humidity resistance characteristics to ensure normal operation during severe accidents.

[0068] Finally, after the highly radioactive material is introduced into the sealed chamber 100, to prevent the chamber from overheating and overpressured due to a large amount of high-temperature, high-pressure water vapor and steam-water mixture, the spray device 500 in the sealed chamber 100 can be activated. Simultaneously, a coil-type heat exchanger can be used to reduce the volume requirement of the sealed chamber 100. If necessary, the emission assembly 700 can be operated. The emission assembly 700 is equipped with a cooling and depressurization assembly 720, an aerosol filter 730, and a gas filter 740, which can further remove airborne radioactivity. When the sealed chamber 100 is full and there is a need for further capacity, some gas is discharged from the emission assembly 700. During the discharge process, the filters can further reduce the amount of radioactive material ultimately released into the environment.

[0069] This invention reduces the release of radioactive materials into the external environment through leakage from the containment vessel 30 after a serious accident by forcing the flow of water vapor and steam-water mixture with high radioactive material concentration inside the pressure vessel 20 into an additional radioactive containment device (i.e., sealed chamber 100) with fewer penetrations and extremely low leakage levels.

[0070] In this invention, the terms "first," "second," and "third" are used for descriptive purposes only and should not be construed as indicating or implying relative importance; the term "multiple" refers to two or more unless otherwise explicitly defined. The terms "install," "connect," "link," and "fix" should be interpreted broadly. For example, "connect" can be a fixed connection, a detachable connection, or an integral connection; "link" can be a direct connection or an indirect connection through an intermediate medium. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.

[0071] In the description of this invention, it should be understood that the terms "upper," "lower," "left," "right," "front," "rear," etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are only for the convenience of describing this invention and simplifying the description, and do not indicate or imply that the device or unit referred to must have a specific orientation or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0072] In the description of this specification, the terms "one embodiment," "some embodiments," "specific embodiment," etc., refer to a specific feature, structure, material, or characteristic described in connection with that embodiment or example, which is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples.

[0073] The above are merely preferred embodiments of the present invention and are not intended to limit the present invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A nuclear reactor safety device (10), characterized in that, The nuclear reactor includes a pressure vessel (20), a reactor core is disposed within the pressure vessel (20), the pressure vessel (20) is located within a containment vessel (30), and the nuclear reactor safety device (10) includes: A sealed chamber (100) is provided outside the containment vessel (30), the sealed chamber (100) is capable of containing radioactive gas, and the relative volumetric leakage rate of the sealed chamber (100) is less than the relative volumetric leakage rate of the containment vessel (30); A conveying assembly (200) has an input end for communication with the pressure vessel (20) and an output end for communication with the sealed chamber (100). A control element (300) is disposed on the conveying assembly (200), the control element (300) being used to control the on / off state of the conveying assembly (200); When the reactor core is in a normal state, the control unit (300) controls the conveying assembly (200) to be in a disconnected state; when the reactor core is in a leaking state, the control unit (300) controls the conveying assembly (200) to be in a connected state.

2. The nuclear reactor safety device (10) according to claim 1, characterized in that, The conveying assembly (200) includes: A delivery pipeline (210) is provided, the input end of which is connected to the pressure vessel (20), and the output end of which is connected to the sealed chamber (100). A blower (220) is connected to the conveying pipeline (210) and the blower (220) is used to blow the gas at the input end of the conveying pipeline (210) to the output end of the conveying pipeline (210).

3. The nuclear reactor safety device (10) according to claim 2, characterized in that, The pressure vessel (20) is equipped with a basket (40), which divides the pressure vessel (20) into a first chamber (21) and a second chamber (22). The delivery pipeline (210) includes: The first delivery pipeline (211) has two ends for connecting the first cavity (21) and the sealed chamber (100). The second delivery pipeline (212) has two ends for connecting the second cavity (22) and the sealed chamber (100).

4. The nuclear reactor safety device (10) according to claim 3, characterized in that, The delivery pipeline (210) also includes: The third conveying pipeline (213) is connected to the input end of the third conveying pipeline (213), and the output end of the first conveying pipeline (211) and the second conveying pipeline (212) are connected to the sealed chamber (100).

5. The nuclear reactor safety device (10) according to any one of claims 1 to 4, characterized in that, Also includes: A radioactive monitoring device (400) is installed on the outer surface of the pressure vessel (20). The radioactive monitoring device (400) is used to monitor the gas radiation value of the gas leaking into the pressure vessel (20). When the gas radiation value is greater than or equal to the radiation threshold, the core is in the leakage state. When the gas radiation value is less than the radiation threshold, the core is in the normal state.

6. The nuclear reactor safety device (10) according to any one of claims 1 to 4, characterized in that, Also includes: A spraying device (500) is provided inside a sealed chamber (100) and is used to spray a cooling alkaline solution into the sealed chamber (100).

7. The nuclear reactor safety device (10) according to any one of claims 1 to 4, characterized in that, Also includes: A heat exchange device (600) is disposed inside a sealed chamber (100) and is used to absorb heat from the sealed chamber (100).

8. The nuclear reactor safety device (10) according to any one of claims 1 to 4, characterized in that, Also includes: An exhaust assembly (700) is connected to the sealed chamber (100). The air inlet (711) of the exhaust assembly (700) is in communication with the interior of the sealed chamber (100), and the air outlet (712) of the exhaust assembly (700) is in communication with the exterior of the sealed chamber (100).

9. The nuclear reactor safety device (10) according to claim 8, characterized in that, The emission assembly (700) includes: The exhaust pipe (710) has both the air inlet (711) and the air outlet (712) located in it. A cooling and pressure reducing component (720) is disposed within the discharge pipe (710), the cooling and pressure reducing component (720) being used to reduce the temperature and pressure within the discharge pipe (710); and / or A dehumidifier (750) is disposed within the discharge pipe (710), the dehumidifier (750) being used to intercept mist droplets within the discharge pipe (710); and / or An aerosol filter (730) is disposed within the discharge pipe (710), the aerosol filter (730) being used to intercept aerosol particles within the discharge pipe (710); and / or A gas filter element (740) is disposed in the discharge pipe (710). The gas filter element (740) is provided with a plurality of filter holes (741), which are used to absorb inert gas in the discharge pipe (710).

10. A nuclear reactor device, characterized in that, include: Nuclear reactor safety device (10) as described in any one of claims 1 to 9. The input end of the delivery assembly (200) of the pressure vessel (20) and the nuclear reactor safety device (10) is connected to the pressure vessel (20).

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