Radioactive gas treatment device, nuclear facility ventilation system and nuclear facility pressure relief method

Abstract

The invention relates to the technical field of nuclear facility safety, and discloses a radioactive gas treatment device, a nuclear facility ventilation system and a nuclear facility pressure relief method.The radioactive gas treatment device comprises a box body and a partition plate, an absorption medium is arranged in the box body, an air inlet and an air outlet are formed in the box body, the partition plate is arranged in the box body, and one end of the partition plate is connected with the inner top wall of the box body; one end of the box body is provided with an air inlet, the other end of the box body is located in the absorption medium, and a gap is reserved between the other end of the box body and the inner bottom wall of the box body. When overpressure exists in a high-radioactivity area, high-temperature smoke containing dust particles such as radioactive aerosol enters the absorption medium through the air inlet, and the dust particles such as the aerosol in the smoke collide with liquid drops in the absorption medium in an inertial mode and are intercepted; the high-temperature flue gas is introduced into the absorption medium, so that the high-temperature flue gas is intercepted in the absorption medium, dust particles such as aerosol in the pressure relief gas can be effectively removed, the purposes of purification and dust removal are achieved, meanwhile, the temperature of the high-temperature flue gas is reduced when the high-temperature flue gas passes through the absorption medium, and diffusion of a large number of high-radioactive substances to a low-pollution area is effectively avoided.

Description

Technical Field

[0001] The present invention relates to the field of nuclear facility safety technology, and in particular to a radioactive gas processing device, a nuclear facility ventilation system and a nuclear facility pressure relief method. Background Art

[0002] The indoor areas of nuclear facility buildings are graded according to the degree of radioactive hazard of the radioactive materials in the area, from high to low, namely red zone, orange zone, green zone and white zone. Among them, the red zone rooms are areas where radioactive materials are directly stored, with strong external radiation and serious pollution. Under normal or accident conditions, the spread of radioactive materials in this area must be prevented. The ventilation system in the nuclear facility needs to ensure that the air flow direction is from non-contaminated areas to contaminated areas, from low-contaminated areas to high-contaminated areas, and a certain negative pressure is maintained between different areas.

[0003] For nuclear fuel cycle facilities, organic solvents such as tributyl phosphate and kerosene are widely used in the extraction process. The use of organic solvents and the handling of other radioactive materials put some red zone high-radioactive rooms at high risk of fire.

[0004] The current fire prevention method for high-radioactive areas is to install fire dampers on the air inlet and exhaust ducts in the area. Under normal conditions, the fire dampers on the air inlet and exhaust ducts remain open. If a fire occurs in the area, the fire dampers on all the air inlet ducts corresponding to the rooms in the radioactive area where the fire occurs are closed; at the same time, the temperature at the air inlet of the exhaust filter at the final stage of the exhaust duct is monitored. When the temperature reaches the set working temperature of the final exhaust filter, the fire dampers on all the exhaust ducts corresponding to the rooms in the radioactive area where the fire occurs are closed. At this time, the highly radioactive room is in a relatively closed state, which can give priority to the control of radioactive substances, thereby preventing the spread of radioactive substances to low-contamination areas to the greatest extent possible.

[0005] However, if a fire occurs in a high-radioactive area, a large amount of radioactive aerosols and smoke will be released at the same time. The aerosols and smoke will diffuse and deposit inside the room, and may even clog and damage the filters in the ventilation system. At the same time, the high-temperature expansion and smoke generated during the fire process will reduce the relative negative pressure value of the high-radioactive room to positive pressure. Because it is difficult to achieve absolute static sealing in a high-radioactive room in the physical sense, in this case, radioactive substances may diffuse disorderly to low-radioactive rooms through certain openings or structural gaps. Therefore, when a fire occurs in a high-radioactive area, it is necessary to relieve the pressure and filter the relieved gas to minimize the spread of radioactive substances to low-contaminated areas.

[0006] In the prior art, the pressure relief devices used in radiation areas usually focus on blocking direct radiation in the radiation area, and do not process the gas flowing out of the room during pressure relief, which causes radioactive substances to diffuse to low-contamination areas along with the gas during pressure relief. Summary of the invention

[0007] In view of this, the present invention provides a radioactive gas processing device, a nuclear facility ventilation system and a nuclear facility pressure relief method to solve the problem in the prior art that radioactive substances will diffuse to low-contamination areas along with the gas when the pressure relief device used in the radiation area is relieved.

[0008] In the first aspect, the present invention provides a radioactive gas processing device, which is used for the pressure relief gas processing in high fire risk and high radioactive areas of nuclear facilities, including a box body and a partition. The interior of the box body is a cavity, and an absorption medium is arranged in the cavity. The box body is provided with an air inlet and an air outlet. The air inlet is suitable for connecting the high radioactive area and the absorption medium, and the air outlet is suitable for connecting the cavity and the low radioactive area. The partition is arranged in the box body, one end of the partition is connected to the top wall of the box body, and the other end is located in the absorption medium, and a gap is left with the bottom wall of the box body. The partition divides the cavity into a first space and a second space, the air inlet is located in the first space, and the air outlet is located in the second space.

[0009] Beneficial effects: When a fire occurs in a high-radioactive area and the area is over-pressured, the high-temperature flue gas containing radioactive aerosols and other dust particles passes through the pressure relief pipe and the pressure relief port and enters the absorption medium through the air inlet. The aerosols and other dust particles in the flue gas collide and are intercepted by the inertia of the droplets in the absorption medium. The presence of the partition lengthens the flow of the flue gas in the absorption medium, further allowing the aerosols and other dust particles in the pressure relief gas to fully contact the absorption medium, so that they are trapped in the absorption medium, and the aerosols and other dust particles in the pressure relief gas can be effectively removed to achieve the purpose of purification and dust removal. At the same time, the temperature of the high-temperature flue gas will also drop when passing through the absorption medium. Most of the radioactive aerosols and other dust particles in the pressure relief gas will be removed after water washing and filtration, effectively avoiding the large-scale diffusion of high-radioactive substances to low-pollution areas, and at the same time avoiding high pressure from destroying the sealed boundary of the high-radioactive area.

[0010] In an optional embodiment, the radioactive gas processing device further includes an air inlet pipe, one end of which is an air inlet, and the other end of which is located in the absorption medium.

[0011] Beneficial effects: The air inlet pipe of the present invention is convenient for directly passing high-temperature flue gas containing radioactive aerosols and other dust particles into the absorption medium, so that the aerosols and other dust particles in the depressurized gas are fully in contact with the absorption medium and are retained in the absorption medium. The aerosols and other dust particles in the depressurized gas can be effectively removed to achieve the purpose of purification and dust removal. At the same time, the temperature of the high-temperature flue gas will also drop when passing through the absorption medium.

[0012] In an optional embodiment, a conical expansion opening is provided at one end of the air inlet pipe located in the absorption medium.

[0013] Beneficial effects: The present invention utilizes the diffusion effect of the conical expansion to disperse the high-temperature flue gas containing radioactive aerosols and other dust particles in the absorption medium, thereby improving the removal rate of aerosols and other dust particles.

[0014] In an optional embodiment, the radioactive gas processing device further includes a filter, and the filter is arranged in the second space and located between the air outlet and the absorption medium.

[0015] Beneficial effect: In the present invention, the depressurized gas after dust removal by the absorption medium water bath is filtered through a primary filter. After two-stage purification, most of the radioactive aerosols and other dust particles will be removed, effectively avoiding the diffusion of high-radioactive substances to low-contamination areas in large quantities, and at the same time avoiding high pressure from destroying the sealed boundary of the high-radioactive area.

[0016] In an optional embodiment, the radioactive gas processing device further comprises a baffle, which is arranged in the second space and located between the filter and the absorption medium.

[0017] In an optional embodiment, the radioactive gas processing device further includes a water supply pipe and a liquid level meter, the water supply pipe is arranged on the box body, and the liquid level meter is arranged on the box body.

[0018] Beneficial effect: The water supply pipe of the present invention can replenish the absorption medium into the box body, and the liquid level meter can observe the liquid level of the absorption medium in the box body in real time to control the replenishment amount. Finally, the height of the absorption medium should submerge the conical expansion port and be lower than the height of the water supply pipe.

[0019] In an optional embodiment, the radioactive gas processing device further includes a sewage pipe, and the sewage pipe is arranged at the bottom of the box body.

[0020] Beneficial effects: The present invention is provided with a sewage pipe, through which the treated absorption medium can be discharged after the pressure relief in the high-radioactive area is completed.

[0021] In a second aspect, the present invention also provides a nuclear facility ventilation system, including a high-radioactivity area, a low-radioactivity area and the above-mentioned radioactive gas processing device, wherein the air inlet is connected to the pressure relief port of the high-radioactivity area, and the air outlet is connected to the low-radioactivity area.

[0022] In an optional embodiment, the nuclear facility ventilation system further includes a pressure relief pipe, which connects the pressure relief port and the air inlet.

[0023] In a third aspect, the present invention further provides a nuclear facility pressure relief method, which is applied to the above-mentioned nuclear facility ventilation system. The pressure relief method comprises:

[0024] Obtain the pressure difference between high-radiation areas and low-radiation areas in the ventilation system of a nuclear facility;

[0025] Determine whether radioactive gas is transferred from high-radioactive area to low-radioactive area through radioactive gas processing device;

[0026] When the pressure difference between the high-radioactive area and the low-radioactive area in the ventilation system of the nuclear facility returns to the normal negative pressure value, the sewage pipe is opened to discharge the absorption medium in the radioactive gas treatment device;

[0027] Replenishing the absorbing medium into the radioactive gas processing device.

[0028] Since the nuclear facility depressurization method adopts the radioactive gas processing device and the nuclear facility ventilation system of the present invention, it has the same beneficial effects as the radioactive gas processing device, which will not be described in detail here. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] In order to more clearly illustrate the specific implementation methods of the present invention or the technical solutions in the prior art, the drawings required for use in the specific implementation methods or the description of the prior art will be briefly introduced below. Obviously, the drawings described below are some implementation methods of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0030] Figure 1 This is a schematic structural diagram of a radioactive gas processing device according to an embodiment of the present invention;

[0031] Figure 2 It is a schematic diagram of the change of the liquid level of the absorption medium when a radioactive gas treatment device according to an embodiment of the present invention is connected to a high radioactive area without depressurization;

[0032] Figure 3 A schematic diagram of the change in the liquid level of the absorption medium and the direction of the gas flow when the radioactive gas treatment device according to an embodiment of the present invention is depressurized;

[0033] Figure 4 A schematic structural diagram of a nuclear facility ventilation system according to an embodiment of the present invention;

[0034] Figure 5 The present invention is a flowchart of a nuclear facility pressure relief method according to an embodiment of the present invention.

[0035] Description of reference numerals:

[0036] 1. Box; 2. Absorption medium; 3. Air inlet; 4. Air outlet; 5. Partition; 6. Air inlet pipe; 7. Conical expansion; 8. Filter; 9. Baffle; 10. Water supply pipe; 11. Liquid level gauge; 12. Drain pipe; 13. Air outlet pipe;

[0037] 100. Radioactive gas processing device; 200. High radioactive area; 201. Pressure relief port; 202. Pressure relief pipe; 300. Low radioactive area; 400. Air supply pipe; 500. Exhaust pipe. DETAILED DESCRIPTION

[0038] In order to make the purpose, technical solution and advantages of the embodiments of the present invention clearer, the technical solution in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative work are within the scope of protection of the present invention.

[0039] Combine the following Figures 1 to 5 , describing an embodiment of the present invention.

[0040] According to an embodiment of the present invention, on the one hand, Figures 1 to 4 As shown, a radioactive gas treatment device 100 is provided, which is applied to the treatment of pressure relief gas in high fire risk and high radioactive areas of nuclear facilities, and comprises a box body 1 and a partition 5. The interior of the box body 1 is a cavity, and an absorption medium 2 is arranged in the cavity. An air inlet 3 and an air outlet 4 are arranged on the box body 1. The air inlet 3 is suitable for connecting the high radioactive area 200 and the absorption medium 2, and the air outlet 4 is suitable for connecting the cavity and the low radioactive area 300. The partition 5 is arranged in the box body 1, and one end of the partition 5 is connected to the top wall of the box body 1, and the other end is located in the absorption medium 2, and a gap is left with the bottom wall of the box body 1. The partition 5 divides the cavity into a first space and a second space. The air inlet 3 is located in the first space, and the air outlet 4 is located in the second space.

[0041] Specifically, in this embodiment, the box body 1 is not specifically limited. For example, in this embodiment, the box body 1 is made of radiation protection material, the box body 1 is a cubic structure, the interior of the box body 1 is a cavity, the partition 5 is vertically arranged in the box body 1, one end of the partition 5 is fixed at the middle position of the top wall of the box body 1, and a gap is left between the bottom of the partition 5 and the bottom wall of the box body 1. The partition 5 divides the box body 1 into two spaces.

[0042] In this embodiment, an absorption medium 2 for absorbing dust particles such as aerosols in the flue gas is provided in the box 1. The absorption medium 2 is not specifically limited in this embodiment. For example, in this embodiment, the absorption medium 2 is water, and the filling height of the absorption medium 2 is above the bottom of the partition 5. The air inlet 3 is located on the side wall of the box 1 where the first space is located. The air inlet 3 is connected to the absorption medium 2 and is used to pass the flue gas in the high-radioactive area 200 into the absorption medium 2. The air outlet 4 is located on the side wall of the box 1 where the second space is located, and the air outlet 4 is located above the absorption medium 2.

[0043] In this embodiment, Figure 1 As shown, when the air inlet 3 of the radioactive gas treatment device 100 is not connected to the high radioactive area 200, the liquid level of the absorption medium 2 in the first space and the second space in the box 1 is the same; Figure 2 As shown, when the air inlet 3 of the radioactive gas treatment device 100 is connected to the high radioactive area 200, the pressure in the low radioactive area 300 connected to the air outlet 4 is greater than that in the high radioactive area 200. At this time, the liquid level of the absorption medium 2 in the first space in the box body 1 is higher than the liquid level of the absorption medium 2 in the second space.

[0044] In the present invention, when a fire occurs in the high radioactive area 200 and the area is over-pressured, the high-temperature flue gas containing radioactive aerosols and other dust particles enters the absorption medium 2 through the air inlet 3. The aerosols and other dust particles in the flue gas collide and are intercepted by the inertia of the droplets in the absorption medium 2. The existence of the partition 5 lengthens the flow of the flue gas in the absorption medium 2, further allowing the aerosols and other dust particles in the decompression gas to fully contact with the absorption medium 2, so that they are trapped in the absorption medium 2, and the aerosols and other dust particles in the decompression gas can be effectively removed to achieve the purpose of purification and dust removal. At the same time, the temperature of the high-temperature flue gas will also drop when passing through the absorption medium 2. After washing and filtering, most of the radioactive aerosols and other dust particles in the decompression gas will be removed, effectively avoiding the diffusion of high-radioactive substances to low-pollution areas in large quantities, and avoiding high pressure from destroying the sealed boundary of the high-radioactive area 200.

[0045] In one embodiment, Figures 1 to 3 As shown, the radioactive gas processing device 100 further includes an air inlet pipe 6 , one end of which is an air inlet 3 , and the other end of which is located in the absorption medium 2 .

[0046] Specifically, in this embodiment, the air inlet pipe 6 is "L"-shaped, one end of which extends into the absorption medium 2, and the other end is the air inlet 3, which is located above the absorption medium 2, passes through the side wall of the box body 1 and extends outside the box body 1, and is connected to the high radioactive area 200.

[0047] The air inlet pipe 6 of the present invention is arranged to facilitate the direct introduction of high-temperature flue gas containing radioactive aerosols and other dust particles into the absorption medium 2, so that the aerosols and other dust particles in the depressurized gas are fully in contact with the absorption medium 2 and are retained in the absorption medium 2. The aerosols and other dust particles in the depressurized gas can be effectively removed to achieve the purpose of purification and dust removal. At the same time, the temperature of the high-temperature flue gas will also decrease when passing through the absorption medium 2.

[0048] In one embodiment, Figure 1 and Figure 2 As shown, one end of the air inlet pipe 6 located in the absorption medium 2 is provided with a conical expansion opening 7 .

[0049] Specifically, in this embodiment, the opening size of one end of the conical expansion port 7 connected to the air inlet pipe 6 is smaller than the opening size of the other end, and the high-temperature flue gas containing dust particles such as radioactive aerosols is diffused outward from the outlet at the end of the air inlet pipe 6 through the conical expansion port 7, so that the high-temperature flue gas containing dust particles such as radioactive aerosols is fully in contact with the absorption medium 2.

[0050] In this embodiment, the radioactive gas treatment device 100 further includes an air outlet pipe 13 , one end of the air outlet pipe 13 is an air outlet 4 , and the other end is located at a side of the box body 1 .

[0051] The present invention utilizes the diffusion effect of the conical expansion 7 to disperse the high-temperature flue gas containing dust particles such as radioactive aerosols in the absorption medium 2, thereby improving the removal rate of dust particles such as aerosols.

[0052] In one embodiment, Figures 1 to 3 As shown, the radioactive gas processing device 100 further includes a filter 8 , which is disposed in the second space and located between the air outlet 4 and the absorption medium 2 .

[0053] Specifically, in this embodiment, the filter 8 is not specifically limited. For example, in this embodiment, the filter 8 adopts a high-efficiency air filter (HEPA, High Efficiency Particulate Air Filte). The high-efficiency air filter can effectively capture dust particles such as aerosols, and has the advantages of high filtration efficiency and can be used continuously for a long time.

[0054] In the present invention, the depressurized gas after dust removal by the absorption medium 2 in the water bath is filtered through the primary filter 8. After two-stage purification, most of the dust particles such as radioactive aerosols will be removed, effectively avoiding the diffusion of high-radioactive substances to low-contamination areas in large quantities, and at the same time avoiding high pressure from destroying the sealed boundary of the high-radioactive area 200.

[0055] In one embodiment, Figures 1 to 3 As shown, the radioactive gas processing device 100 further includes a baffle 9 , which is disposed in the second space and located between the filter 8 and the absorption medium 2 .

[0056] Specifically, in this embodiment, the baffle 9 includes a plurality of "S"-shaped blades with a multi-fold structure, which are used to prevent the absorption medium 2 liquid in the box 1 from entering the filter 8. The depressurized gas passes through the gaps between the blades, and the blade spacing and arrangement can be adjusted according to the flow rate of the depressurized gas.

[0057] In one embodiment, Figures 1 to 3 As shown, the radioactive gas processing device 100 further includes a water supply pipe 10 and a liquid level meter 11 . The water supply pipe 10 is arranged on the box body 1 , and the liquid level meter 11 is arranged on the box body 1 .

[0058] Specifically, in this embodiment, the water supply pipe 10 is arranged on the box body 1, the water supply pipe 10 is located below the baffle 9, the setting height of the water supply pipe 10 is higher than the liquid level of the absorption medium 2, and a valve is arranged on the water supply pipe 10. The liquid level meter 11 is arranged on the outer wall of the box body 1. When replenishing water, the valve on the water supply pipe 10 is opened, and the absorption medium 2 is added into the box body 1 through the water supply pipe 10. During the water replenishment process, the height of the absorption medium 2 can be observed through the liquid level meter 11.

[0059] The present invention is provided with a water supply pipe 10 to replenish the absorption medium 2 into the box body 1, and the liquid level meter 11 can observe the liquid level of the absorption medium 2 in the box body 1 in real time to control the replenishment amount. Finally, the height of the absorption medium 2 should submerge the conical expansion port 7 and be lower than the height of the water supply pipe 10.

[0060] In one embodiment, Figures 1 to 3 As shown, the radioactive gas processing device 100 further includes a sewage pipe 12 , which is disposed at the bottom of the box body 1 .

[0061] Specifically, in this embodiment, a valve is provided on the sewage pipe 12. After the pressure relief of the highly radioactive room is completed, the valve on the sewage pipe 12 is opened to discharge sewage through the sewage pipe 12, and the sewage is connected to the radioactive sewage treatment and discharge system.

[0062] The present invention is provided with a sewage pipe 12 , and after the high radioactive area 200 is depressurized, the treated absorption medium 2 can be discharged through the sewage pipe 12 .

[0063] According to an embodiment of the present invention, on the other hand, Figure 4 As shown, a nuclear facility ventilation system is also provided, including a high-radioactivity area 200, a low-radioactivity area 300 and the above-mentioned radioactive gas processing device 100, the air inlet 3 is connected to the pressure relief port 201 of the high-radioactivity area 200, and the air outlet 4 is connected to the low-radioactivity area 300.

[0064] Specifically, in this embodiment, the high radioactivity area 200 is a room with high fire risk and high radioactivity in a nuclear fuel cycle facility.

[0065] In this embodiment, the high radioactive area 200 and the radioactive gas processing device 100 are located inside the low radioactive area 300, the air inlet 3 is connected to the pressure relief port 201 of the high radioactive area 200, and the air outlet 4 is connected to the low radioactive area 300. When a fire occurs in the high radioactive area 200 and the area is over-pressured, the high-temperature flue gas containing radioactive aerosols and other dust particles enters the absorption medium 2 through the air inlet 3, and the aerosols and other dust particles in the flue gas are inertially collided and intercepted with the droplets in the absorption medium 2. The existence of the partition 5 lengthens the flow of the flue gas in the absorption medium 2, further allowing the aerosols and other dust particles in the pressure relief gas to fully contact with the absorption medium 2, so that they are trapped in the absorption medium 2, and the aerosols and other dust particles in the pressure relief gas can be effectively removed to achieve the purpose of purification and dust removal. At the same time, the temperature of the high-temperature flue gas will also decrease when passing through the absorption medium 2. The purified gas is discharged from the air outlet 4 to the low radioactive area 300, and then discharged to the ventilation system through the exhaust pipe 500 in the low radioactive area 300, and then discharged to the atmosphere after filtration.

[0066] After two-stage purification by water washing and filter 8, most of the radioactive aerosols and other dust particles in the depressurized gas will be removed, effectively avoiding the large-scale diffusion of highly radioactive substances to low-contaminated areas, and preventing high pressure from destroying the sealed boundary of the highly radioactive area 200.

[0067] The pressure difference between the high-radioactivity area 200 and the low-radioactivity area 300 is established by the air volume matching design and valve regulation of other ventilation systems. In this embodiment, the negative pressure value between the high-radioactivity area 200 and the low-radioactivity area 300 is between 100Pa and 300Pa. The negative pressure difference is established during the initial commissioning of the ventilation system. When a fire occurs in the high-radioactivity area 200, the area is over-pressurized, and the pressure difference becomes positive. The smoke enters the radioactive gas treatment device 100 from the high-radioactivity area 200 for pressure relief, and the original negative pressure state is restored after the pressure relief is completed.

[0068] In this embodiment, the high radioactive region 200 is provided with an air supply pipe 400 and an exhaust pipe 500, which are arranged on opposite sides of the high radioactive region 200, one end of the air supply pipe 400 is connected to the high radioactive region 200, and the other end is connected to the air supply system, one end of the exhaust pipe 500 is connected to the high radioactive region 200, and the other end is connected to the exhaust system, fire dampers are installed on the air supply pipe 400 and the exhaust pipe 500, when a fire occurs in the high radioactive region 200, the fire dampers on all the air supply pipes 400 corresponding to the high radioactive region 200 are closed; at the same time, the temperature at the air inlet 3 of the exhaust filter 8 at the final stage in the exhaust system is monitored, when the temperature reaches the set working temperature of the final exhaust filter 8, the fire dampers on all the exhaust pipes 500 corresponding to the high radioactive region 200 are closed, when the fire in the high radioactive region 200 is extinguished and the ventilation system resumes normal operation, the pressure difference returns to a negative value, and the fire damper is opened again. In one embodiment, the nuclear facility ventilation system further includes a pressure relief port 201 , and a pressure relief pipe 202 connects the pressure relief port 201 and the air inlet 3 .

[0069] Specifically, in this embodiment, one end of the pressure relief pipe 202 is connected to the pressure relief port 201, and the other end is connected to the air inlet 3. The pressure in the high radioactive area 200 is lower than the pressure in the low radioactive area 300 under normal ventilation conditions to ensure that the pressure relief pipe 202 is in a negative pressure state.

[0070] According to an embodiment of the present invention, on the other hand, Figure 5 As shown, a nuclear facility pressure relief method is also provided, which is applied to the above-mentioned nuclear facility ventilation system, and the pressure relief method includes:

[0071] Obtaining the pressure difference between a high radioactive area 200 and a low radioactive area 300 in a ventilation system of a nuclear facility;

[0072] Determine whether the radioactive gas is input from the high radioactive area 200 to the low radioactive area 300 via the radioactive gas processing device 100;

[0073] When the pressure difference between the high-radioactive area 200 and the low-radioactive area 300 in the ventilation system of the nuclear facility returns to normal negative pressure, the sewage pipe 12 is opened, and the absorption medium 2 in the radioactive gas treatment device 100 is discharged;

[0074] The radioactive gas treatment device 100 is replenished with the absorption medium 2 .

[0075] Specifically, the nuclear facility depressurization method in this embodiment includes the following steps:

[0076] S1: A pressure detection device is provided in the high radioactive area 200 of the ventilation system of the nuclear facility, and the pressure detection device is used to detect the pressure difference between the high radioactive area 200 and the low radioactive area 300;

[0077] S2: Determine whether the radioactive gas is input from the high radioactive area 200 to the low radioactive area 300 via the radioactive gas processing device 100;

[0078] S3: If a fire occurs in the high-radioactive area 200, the pressure in the area is greater than that in the low-radioactive area 300, and the high-temperature flue gas containing dust particles such as radioactive aerosols enters the absorption medium 2 through the pressure relief pipe 202 until the pressure relief is completed and the pressure in the high-radioactive area 200 is less than that in the low-radioactive area 300;

[0079] S4: Open the valve of the sewage pipe 12 on the radioactive gas treatment device 100, discharge the treated absorption medium 2 through the sewage pipe 12, and connect the sewage to the radioactive sewage treatment and discharge system;

[0080] S5: After the sewage is discharged, the valve on the water supply pipe 10 is opened, and clean water is added through the water supply pipe 10 to the water level state before the radioactive gas treatment device 100 works.

[0081] Although the embodiments of the present invention have been described in conjunction with the accompanying drawings, those skilled in the art may make various modifications and variations without departing from the spirit and scope of the present invention, and such modifications and variations are all within the scope defined by the appended claims.

Claims

1. A radioactive gas treatment device, used for the treatment of pressure relief gas in high fire risk and high radioactive areas of nuclear facilities, characterized in that: include: A box (1), wherein the interior of the box (1) is a cavity, an absorption medium (2) is arranged in the cavity, and an air inlet (3) and an air outlet (4) are arranged on the box (1), wherein the air inlet (3) is suitable for connecting a high-radioactivity area (200) and the absorption medium (2), and the air outlet (4) is suitable for connecting the cavity and a low-radioactivity area (300); A partition (5), wherein the partition (5) is arranged in the box body (1), one end of the partition (5) is connected to the inner top wall of the box body (1), and the other end is located in the absorption medium (2) and has a gap with the inner bottom wall of the box body (1), the partition (5) divides the cavity into a first space and a second space, the air inlet (3) is located in the first space, and the air outlet (4) is located in the second space.

2. The radioactive gas processing device according to claim 1, characterized in that: Also includes: An air inlet pipe (6), one end of which is the air inlet (3) and the other end of which is located in the absorption medium (2).

3. The radioactive gas processing device according to claim 2, characterized in that: One end of the air inlet pipe (6) located in the absorption medium (2) is provided with a conical expansion opening (7).

4. The radioactive gas processing device according to claim 1, characterized in that: Also includes: A filter (8), wherein the filter (8) is arranged in the second space and is located between the air outlet (4) and the absorption medium (2).

5. The radioactive gas processing device according to claim 4, characterized in that: Also includes: A baffle (9) is arranged in the second space and located between the filter (8) and the absorption medium (2).

6. The radioactive gas processing device according to claim 1, characterized in that: Also includes: A water supply pipe (10), wherein the water supply pipe (10) is arranged on the box body (1); A liquid level meter (11), wherein the liquid level meter (11) is arranged on the box body (1).

7. The radioactive gas processing device according to claim 1, characterized in that: Also includes: A sewage discharge pipe (12), wherein the sewage discharge pipe (12) is arranged at the bottom of the box body (1).

8. A nuclear facility ventilation system, characterized in that: include: Highly radioactive areas (200); Low radioactivity area (300); The radioactive gas processing device (100) according to any one of claims 1 to 7, wherein the air inlet (3) is connected to the pressure relief port (201) of the high-radioactivity area (200), and the air outlet (4) is connected to the low-radioactivity area (300).

9. The nuclear facility ventilation system according to claim 8, characterized in that: Also includes: A pressure relief pipe (202), wherein the pressure relief pipe (202) connects the pressure relief port (201) and the air inlet (3).

10. A method for depressurizing a nuclear facility, characterized in that: Applied to the nuclear facility ventilation system of claim 8 or 9, the pressure relief method comprises: Obtaining a pressure difference between a high-radioactivity area (200) and a low-radioactivity area (300) in a ventilation system of a nuclear facility; Determining whether radioactive gas is input from a high radioactive area (200) into a low radioactive area (300) via a radioactive gas processing device (100); When the pressure difference between the high-radioactivity area (200) and the low-radioactivity area (300) in the nuclear facility ventilation system returns to a normal negative pressure value, the sewage discharge pipe (12) is opened to discharge the absorption medium (2) in the radioactive gas processing device (100); The absorbing medium (2) is replenished into the radioactive gas processing device (100).

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