Radioactive gas detection device and detection method

Abstract

The present application discloses a radioactive gas detection device and a detection method. The radioactive gas detection device is used for detection of a radioactive gas containing a target nuclide, and comprises: an adsorption assembly, a sampling assembly, a monitoring assembly, a desorption assembly, a detection assembly, a first control valve set and a controller, wherein the sampling assembly, the adsorption assembly, and the monitoring assembly are sequentially communicated; the adsorption assembly is further communicated with the detection assembly; and the controller is configured to: when the monitoring assembly detects that the radioactive gas passing through the adsorption assembly contains the target nuclide, control the first control valve set to enable the adsorption assembly to be disconnected from the sampling assembly and the adsorption assembly to be disconnected from the monitoring assembly and enable the adsorption assembly to be communicated with the detection assembly, and control the detection assembly to perform a detection operation on the target nuclide released from the adsorption assembly to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection accuracy of the target nuclide in the radioactive gas.

Description

Radioactive gas detection devices and detection methods Technical Field

[0001] This application relates to the field of radioactive gas detection, and in particular to radioactive gas detection devices and detection methods. Background Technology

[0002] For industries that generate waste gas during production, gas emission standards are usually established to ensure that the emissions do not pollute the environment and achieve sustainable development. In the nuclear power sector, for example, airborne radioactive effluents undergo purification treatment, and the emitted airborne radioactive effluents need to be monitored. The measurements include the total amount emitted, the concentration emitted, and the content of the main nuclides. Only after the measurements meet the standards can the effluents be released into the atmosphere through the chimney.

[0003] In related technologies, when using detectors to detect trace nuclides, adsorbent materials, such as filter paper, containing the trace nuclides are often placed in the detector's detection window. The activity concentration of α / β particles released by the trace nuclides is then determined using α / β characteristic track analysis, thus enabling the detection of trace radioactive inert gas nuclides. However, during the detection process, it was found that when filter paper or other adsorbent materials are placed directly in the detector's detection window, only a portion of the particles entering the detector window can be detected; the remaining particles entering the environment cannot be counted, resulting in poor detection accuracy. Furthermore, the detector exhibits better detection accuracy when detecting target nuclides at preset concentrations; however, the detection accuracy deteriorates when the target nuclide concentration is too low. Summary of the Invention

[0004] This application aims to address at least one of the technical problems existing in the prior art. To this end, this application proposes a radioactive gas detection device capable of improving the detection accuracy of target nuclides in radioactive gases.

[0005] A detection method using the aforementioned radioactive gas detection device is also proposed.

[0006] The radioactive gas detection apparatus according to the first aspect of this application is used for detecting radioactive gases containing a target nuclide, including:

[0007] The adsorption component is capable of adsorbing the target nuclide in the radioactive gas;

[0008] A sampling component, connected to the adsorption component, is used to supply the radioactive gas to the adsorption component;

[0009] A monitoring component, connected to the adsorption component, is used to monitor the target nuclide in the radioactive gas after it has passed through the adsorption component;

[0010] A desorption component is used to cause the adsorption component to release the adsorbed target nuclide;

[0011] A detection component, connected to the adsorption component, is used to detect the content of the target nuclide released by the adsorption component;

[0012] The first control valve group is used to switch the on / off state between the adsorption component and the sampling component, between the adsorption component and the monitoring component, and between the adsorption component and the detection component;

[0013] Controller;

[0014] The controller is configured to: when the monitoring component detects that the radioactive gas after passing through the adsorption component contains the target nuclide, control the first control valve group to disconnect the adsorption component from the sampling component and from the monitoring component, and to connect the adsorption component to the detection component; and control the detection component to perform a detection operation on the target nuclide released from the adsorption component to obtain the content of the target nuclide.

[0015] The radioactive gas detection device according to the first aspect of this application has at least the following beneficial effects:

[0016] 1. The adsorption component adsorbs the target nuclide in the radioactive gas. When the adsorption component cannot completely absorb the target nuclide in the radioactive gas, the monitoring component will detect that the radioactive gas passing through the adsorption component contains the target nuclide. At this time, the controller controls the first control valve group to disconnect the adsorption component from the sampling component and from the monitoring component, and to connect the adsorption component to the detection component. The desorption component drives the adsorption component to release the adsorbed target nuclide, and the detection component detects the content of the target nuclide released by the adsorption component, so that the detection accuracy of the target nuclide is higher.

[0017] 2. By monitoring the changes in the concentration of radioactive gas passing through the adsorption component, it can be determined whether the adsorption component has completed adsorption. This ensures that the adsorption component can fully adsorb the target nuclide, with only trace amounts of the target nuclide escaping. The escaping target nuclide has a smaller impact on the overall detection accuracy of the target nuclide. Furthermore, sufficient target nuclide can meet the detection requirements of the detection component, making the detection of the detection component more accurate.

[0018] According to some embodiments of this application, the radioactive gas detection device further includes a transfer component for transferring the target nuclide released by the adsorption component to the detection component.

[0019] According to some embodiments of this application, the detection assembly includes: an equipment chamber, a detection chamber, a spacer membrane, a spacer plate, and a detection element. The equipment chamber and the detection chamber are interconnected through an incident window, and the detection chamber is connected to the adsorption assembly. The spacer membrane is disposed at the incident window. The spacer plate is disposed at the incident window and located on the side of the spacer membrane away from the equipment chamber. The spacer plate is capable of closing or opening the incident window. The detection element is disposed inside the equipment chamber.

[0020] The controller is configured to: control the spacer to close the incident window when the transfer component transfers the target nuclide released from the adsorption component to the detection chamber; and control the spacer to open the incident window and control the detector located in the equipment chamber to perform the detection operation after the adsorption component has completed the transfer operation.

[0021] According to some embodiments of this application, the detection component includes: a detection chamber, a detection element, a working component, and a working valve. The detection chamber is connected to the adsorption component, the detection element is disposed within the detection chamber, the working component is connected to the detection chamber and is used to introduce working gas into the detection chamber, and the working valve is used to control the on / off connection between the working component and the detection chamber.

[0022] The controller is configured to: control the working valve to make the working component and the detection chamber in a connected state when the transfer component performs the transfer operation or after the adsorption component completes the transfer operation, control the working component to introduce the working gas into the detection chamber, and control the detector located in the detection chamber to perform the detection operation.

[0023] According to some embodiments of this application, the transfer component, the adsorption component, and the detection component are connected in sequence. The transfer component is used to deliver a purge gas that does not react with the target nuclide to the detection component, so as to purge the target nuclide released by the adsorption component to the detection component.

[0024] And / or,

[0025] The transfer assembly includes a vacuum pumping assembly and a second control valve group. The vacuum pumping assembly is connected to the detection assembly, and the second control valve group is used to switch the on / off connection between the detection assembly and the vacuum pumping assembly, as well as the on / off connection between the detection assembly and the adsorption assembly.

[0026] The controller is configured to: when the transfer component performs a transfer operation, control the second control valve group to make the detection component and the vacuum component in a connected state, and to make the detection component and the adsorption component in a disconnected state, while the vacuum component performs a vacuum operation; when a preset negative pressure is formed in the detection component, control the second control valve group to make the detection component and the vacuum component in a disconnected state, and to make the detection component and the adsorption component in a connected state.

[0027] According to some embodiments of this application, the sampling component includes a gas storage device and a gas flow meter. The gas storage device is connected to the adsorption component and is used to store the radioactive gas. The gas flow meter is disposed in a pipe between the gas storage device and the adsorption component and is used to detect the total amount of radioactive gas entering the adsorption component.

[0028] or,

[0029] The sampling assembly includes a test pipe, an inlet pipe, an outlet pipe, and a gas flow meter. The test pipe is used to discharge the radioactive gas and has a first position and a second position distributed sequentially along the discharge direction. The inlet pipe connects the test pipe and the adsorption assembly at the first position, and the outlet pipe connects the test pipe and the monitoring assembly at the second position. The gas flow meter is located in the inlet pipe and is used to detect the total amount of radioactive gas entering the adsorption assembly.

[0030] According to some embodiments of this application, the adsorption assembly includes a shell and a porous adsorption element. The shell defines an adsorption cavity, which has a first connecting position and a second connecting position. The shell is connected to the sampling assembly at the first connecting position and to the monitoring assembly or the detection assembly at the second connecting position. The porous adsorption element is disposed in the adsorption cavity and is located between the first connecting position and the second connecting position along the delivery direction of the radioactive gas.

[0031] or,

[0032] The adsorption assembly includes a shell and a separation membrane. The shell defines a first cavity and a second cavity. The first cavity is connected to the sampling assembly, and the second cavity is connected to the monitoring assembly or the detection assembly. The separation membrane is disposed between the first cavity and the second cavity and connects the first cavity and the second cavity.

[0033] According to some embodiments of this application, the adsorption assembly includes a shell and a separation membrane, and the pressure in the second cavity is less than the pressure in the first cavity.

[0034] The detection method according to the second aspect of this application includes the following steps:

[0035] S1: Radioactive gas is conveyed through an adsorption assembly, which adsorbs the target nuclide in the radioactive gas;

[0036] S2: When the monitoring component detects that the radioactive gas passing through the adsorption component contains the target nuclide, the delivery of the radioactive gas is stopped, and the total amount of the delivered radioactive gas X1 and the content of the target nuclide adsorbed by the adsorption component X2 are obtained.

[0037] S3: Obtain the concentration of the target nuclide based on the total amount of radioactive gas X1 and the content of the target nuclide X2.

[0038] The detection method according to the second aspect of this application has at least the following beneficial effects: by monitoring whether the radioactive gas passing through the adsorption component contains the target nuclide, it is determined whether the adsorption component has completed adsorption. The adsorption component can adsorb a sufficient amount of target nuclide for detection. At the same time, fewer target nuclides pass through the monitoring component, resulting in higher detection accuracy and content accuracy of the target nuclide, thereby improving the detection accuracy of the target nuclide concentration in the radioactive gas.

[0039] According to some embodiments of this application, in S2, the target nuclide adsorbed by the adsorption component is released by heating, and the content X2 of the target nuclide released by the adsorption component is detected; wherein, the heating temperature range is 80℃~100℃.

[0040] Additional aspects and advantages of this application will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of this application. Attached Figure Description

[0041] The present application will be further described below with reference to the accompanying drawings and embodiments, wherein:

[0042] Figure 1 is a schematic diagram of the sampling component sampling the gas storage device in a radioactive gas detection device according to an embodiment of this application.

[0043] Figure 2 is a schematic diagram of the sampling component in a radioactive gas detection device according to an embodiment of this application, which samples the pipeline to be tested.

[0044] Figure 3 is a schematic diagram of the structure of a radioactive gas detection device according to an embodiment of this application when a porous adsorption element is used in the adsorption component.

[0045] Figure 4 is a schematic diagram of the structure of the adsorption component in a radioactive gas detection device according to an embodiment of this application when a separation membrane is used and a purge transfer is employed.

[0046] Figure 5 is a schematic diagram of the structure of a radioactive gas detection device according to an embodiment of this application, in which the detection component is a windowed detector and negative pressure transfer is used;

[0047] Figure 6 is a schematic diagram of the structure of a radioactive gas detection device according to an embodiment of this application, in which the detection component is a windowless detector and negative pressure transfer is used.

[0048] Reference numerals: Adsorption component 100; Housing 110; First chamber 111; Second chamber 112; Porous adsorption element 120; Separation membrane 130; Back pressure valve 140; Sampling component 200; Gas storage component 210; Gas flow meter 220; Test pipe 230; Inlet pipe 240; Outlet pipe 250; Monitoring component 300; Desorption component 400; Detection component 500; Equipment chamber 510; Detection chamber 520; Spare membrane 530; Spare plate 540; Detector 550; Working component 560; Working valve 570; First control valve group 600; First valve 610; Second valve 620; Third valve 630; Transfer component 700; Vacuum pumping component 710; Second control valve group 720. Detailed Implementation

[0049] The embodiments of this application are described in detail below. Examples of these embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain this application, and should not be construed as limiting this application.

[0050] In the description of this application, it should be understood that the orientation descriptions, such as up, down, etc., are based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing this application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of this application.

[0051] In the description of this application, "several" refers to one or more, and "multiple" refers to two or more. The use of "first" and "second" is for the purpose of distinguishing technical features only and should not be construed as indicating or implying relative importance, or implicitly indicating the number of technical features indicated, or implicitly indicating the order of the indicated technical features.

[0052] In the description of this application, unless otherwise expressly defined, terms such as "setup," "installation," and "connection" should be interpreted broadly, and those skilled in the art can reasonably determine the specific meaning of the above terms in this application in conjunction with the specific content of the technical solution.

[0053] In related technologies, when using detectors to detect trace nuclides, adsorbent materials, such as filter paper, containing the trace nuclides are often placed in the detector's detection window. The activity concentration of α / β particles released by the trace nuclides is then determined using α / β characteristic track analysis, thus enabling the detection of trace radioactive inert gas nuclides. However, during the detection process, it was found that when filter paper or other adsorbent materials are placed directly in the detector's detection window, only particles perpendicularly entering the window can be detected; other particles entering the environment cannot be counted, resulting in poor detection accuracy. Furthermore, the detector exhibits better accuracy when detecting target nuclides at preset concentrations; however, its accuracy deteriorates when the target nuclide concentration is too low.

[0054] Referring to Figures 1 to 6, a first aspect of this application provides a radioactive gas detection device for detecting radioactive gases containing a target nuclide. The radioactive gas detection device includes: an adsorption component 100, a sampling component 200, a monitoring component 300, a desorption component 400, a detection component 500, a first control valve group 600, and a controller. The sampling component 200, the adsorption component 100, and the monitoring component 300 are connected in sequence. The adsorption component 100 is also connected to the detection component 500.

[0055] It should be noted that radioactive gas refers to gas containing radioactive nuclides, which are atoms that emit radioactivity. The target nuclide is one or more radioactive nuclides within the radioactive gas.

[0056] In this embodiment, the adsorption component 100 can adsorb the target nuclide in the radioactive gas. Specifically, the adsorption component 100 has a porous material inside. The porous material has a highly ordered network structure with a large specific surface area, providing suitable adsorption and storage space, which enhances the adsorption capacity of the porous material for nuclide molecules. Furthermore, the porous material can selectively adsorb and store the desired nuclide, thus separating the nuclide from other molecules. In other words, the pores of the porous material can just accommodate the target nuclide. When the radioactive gas passes through the porous material of the adsorption component 100, the target nuclide is embedded in the pores of the porous material, while the remaining gas passes through the porous material, thereby realizing the extraction of the target nuclide from the radioactive gas.

[0057] The sampling component 200 is connected to the adsorption component 100 and is used to provide radioactive gas to the adsorption component 100. The radioactive gas is stably provided by the sampling component 200, so that the radioactive gas passes stably through the adsorption component 100 and the target nuclide is continuously embedded in the pores of the porous material.

[0058] The monitoring component 300 is connected to the adsorption component 100 and is used to monitor the target nuclide in the radioactive gas after passing through the adsorption component 100. The monitoring component 300 can monitor the presence of the target nuclide in the radioactive gas in real time. The monitoring component 300 can be a mass spectrometer, chromatograph, or other similar equipment. When the monitoring component 300 detects the presence of the target nuclide in the radioactive gas after passing through the adsorption component 100, the adsorption component 100 has completed adsorption.

[0059] It should be noted that the adsorption component 100 has three states when adsorbing the target nuclide: not fully adsorbed, basically fully adsorbed, and fully adsorbed.

[0060] The "not fully adsorbed" state refers to a situation where the adsorption component 100 can completely adsorb the target nuclide from the passing radioactive gas, but sufficient pores still exist in the porous material. In this state, the monitoring component 300 cannot detect the target nuclide, and the content of the target nuclide adsorbed in the adsorption component 100 cannot be determined. If detection is performed in this state, the content of the target nuclide may be low, leading to a decrease in the detection accuracy of the detection component 500.

[0061] The basic adsorption full state refers to the state where the adsorption component 100 can adsorb the vast majority of the target nuclides in the passing radioactive gas, with only a very small portion of the nuclides passing through the adsorption component 100. In the basic adsorption full state, the monitoring component 300 detects the target nuclide, and the detected target nuclide content continuously increases. When the monitoring component 300 detects the target nuclide, the adsorption component 100 has just entered the basic adsorption full state. The target nuclide content in the adsorption component 100 meets the accuracy requirements of the detection component 500, with only a trace amount of target nuclide loss, resulting in higher detection accuracy.

[0062] A fully adsorbed state means that all pores of the porous material in the adsorption component 100 are embedded with the target nuclide, and no target nuclide is adsorbed when radioactive gas passes through. In a fully adsorbed state, the target nuclide content detected by the monitoring component 300 remains stable. However, during the process from when the monitoring component 300 detects the target nuclide until its content stabilizes, some target nuclides pass through the monitoring component 300 and are expelled, leading to a decrease in the target nuclide content and severely affecting detection accuracy.

[0063] Therefore, in this embodiment, the monitoring component 300 monitors whether the radioactive gas passing through the adsorption component 100 contains nuclides. When a nuclide is present, it is determined that the adsorption component 100 is in a state of near-full adsorption. At this time, the adsorption component 100 adsorbs an appropriate amount of the target nuclide, and the content of the target nuclide can reach the accuracy detection range of the detection component 500. The detection accuracy of the detection component 500 is higher, and the target nuclide is detected as soon as it passes through the monitoring component 300. The amount of target nuclide escaping is lower, and the content of the target nuclide is more accurate. This improves the accuracy of the content of the target nuclide and the detection accuracy, making the calculated concentration of the target nuclide in the radioactive gas more accurate.

[0064] The desorption component 400 is used to cause the adsorption component 100 to release the adsorbed target nuclide. Specifically, the adsorption component 100 embeds the target nuclide in its pores. When the desorption component 400 heats the target nuclide, the porous material expands due to heat, further increasing the pore size. The target nuclide can no longer be embedded in the pores, resulting in its de-embedding and separation from the porous material. In other words, under the heating action of the desorption component 400, the adsorption component 100 will release the adsorbed target nuclide. Furthermore, the desorption component 400 can directly heat the adsorption component 100, or it can be used to manually transfer the porous material within the adsorption component 100 and then heat the porous material separately.

[0065] The detection component 500 is connected to the adsorption component 100 and is used to detect the content of the target nuclide released by the adsorption component 100. Specifically, the detection component 500 has a detection surface, and the detection component 500 detects the target nuclide through a separate cavity. The target nuclide in the cavity can emit particles in multiple directions, including particles emitted towards the detection surface, which can be perpendicular to the detection surface or tilted towards the detection surface. When the target nuclide is dispersed in the cavity of the detection component, the detection surface can detect particles emitted in different directions within the cavity, thereby detecting a greater number of particles and improving the detection accuracy of the detection component 500.

[0066] The first control valve group 600 is used to switch the on / off connections between the adsorption component 100 and the sampling component 200, between the adsorption component 100 and the monitoring component 300, and between the adsorption component 100 and the detection component 500. The first control valve group 600 includes a first valve 610 located between the adsorption component 100 and the sampling component 200, a second valve 620 located between the adsorption component 100 and the monitoring component 300, and a third valve 630 located between the adsorption component 100 and the detection component 500. The second valve 620 may also be located at the tail end of the monitoring component 300 along the radioactive gas delivery direction. Furthermore, the second valve 620 and the third valve 630 can be integrated into a three-way valve, controlling the on / off connections between the adsorption component 100 and the sampling component 200, and between the adsorption component 100 and the detection component 500, through the same three-way valve.

[0067] The controller is electrically connected to the first valve 610, the second valve 620, and the third valve 630 to control the opening and closing of the valves. The controller is configured to: when the monitoring component 300 detects that the radioactive gas after passing through the adsorption component 100 contains the target nuclide, control the first control valve group 600 to disconnect the adsorption component 100 from the sampling component 200 and from the monitoring component 300; specifically, when the monitoring component 300 detects that the radioactive gas after passing through the adsorption component 100 contains the target nuclide, the adsorption component 100 is in a basically fully adsorbed state. At this time, the controller controls the first valve 610 and the second valve 620 to close, the sampling component 200 no longer delivers radioactive gas through the adsorption component 100 to determine the total amount of radioactive gas delivered, and the radioactive gas no longer flows out of the monitoring component 300 to avoid loss of the target nuclide. The adsorption component 100 and the detection component 500 are connected, and the detection component 500 is controlled to perform a detection operation on the target nuclide released from the adsorption component 100 to obtain the content of the target nuclide. Based on the content of the target nuclide and the total amount of radioactive gas, the concentration of the target nuclide in the radioactive gas can be calculated.

[0068] It is understandable that when the adsorption component 100 adsorbs the target nuclide in the radioactive gas, and the adsorption component 100 cannot completely absorb the target nuclide in the radioactive gas, that is, when the adsorption component 100 is in a basically fully adsorbed state, the monitoring component 300 will detect that the radioactive gas passing through the adsorption component 100 contains the target nuclide. At this time, the controller controls the first control valve group 600 to disconnect the adsorption component 100 from the sampling component 200 and from the monitoring component 300, and to connect the adsorption component 100 to the detection component 500. The desorption component 400 then drives the adsorption... The adsorption component 100 releases the adsorbed target nuclide, and the detection component 500 detects the content of the target nuclide released by the adsorption component 100, thus improving the detection accuracy of the target nuclide. The monitoring component 300 monitors the change in the concentration of radioactive gas passing through the adsorption component 100 to determine whether the adsorption component 100 has completed adsorption, ensuring that the adsorption component 100 can fully adsorb the target nuclide with only trace amounts escaping. The escaping target nuclide has a smaller impact on the overall detection accuracy of the target nuclide. Furthermore, the sufficient target nuclide can meet the detection requirements of the detection component 500, making the detection of the detection component 500 more accurate.

[0069] Referring to Figures 4, 5, and 6, in some embodiments of this application, the radioactive gas detection device further includes a transfer component 700, which is used to transfer the target nuclide released by the adsorption component 100 to the detection component 500. It is understood that the transfer component 700 can transfer the target nuclide released by the adsorption component 100 to the cavity within the detection component 500 via negative pressure transfer or purge transfer, facilitating the detection component 500's detection of the target nuclide.

[0070] Referring to Figures 4, 5 and 6, in some specific embodiments of this application, the transfer component 700 includes transfer methods such as purge transfer, negative pressure transfer and combinations thereof.

[0071] When the transfer component 700 is purging and transferring, as shown in FIG4, the transfer component 700, the adsorption component 100 and the detection component 500 are connected in sequence. The transfer component 700 is used to deliver purge gas that does not react with the target nuclide to the detection component 500, so as to purge the target nuclide released by the adsorption component 100 to the detection component 500.

[0072] Specifically, the purging process of the transfer component 700 can be such that the transfer component 700 purges while the desorption component 400 simultaneously heats the adsorption component 100 to achieve the transfer of the target nuclide. Alternatively, the desorption component 400 can first heat the adsorption component 100, and then the transfer component 700 can purge. In this embodiment, the purge gas that does not react with the target nuclide can be an inert gas or other gas that does not react with the target nuclide. The transfer component 700 includes a purge gas source, through which purge gas is continuously input, so that the target nuclide released by the adsorption component 100 is purged into the cavity of the detection component 500.

[0073] When the transfer component 700 is transferring under negative pressure, as shown in Figures 5 and 6, the transfer component 700 includes a vacuuming component 710 and a second control valve group 720. The vacuuming component 710 is connected to the detection component 500, and the second control valve group 720 is used to switch the connection between the detection component 500 and the vacuuming component 710, as well as between the detection component 500 and the adsorption component 100. The controller is configured to: when the transfer component 700 performs a transfer operation, control the second control valve group 720 to keep the detection component 500 and the vacuuming component 710 connected, and keep the detection component 500 and the adsorption component 100 disconnected, while the vacuuming component 710 performs a vacuuming operation; when a preset negative pressure is formed in the detection component 500, control the second control valve group 720 to keep the detection component 500 and the vacuuming component 710 disconnected, and keep the detection component 500 and the adsorption component 100 connected.

[0074] Specifically, before the negative pressure transfer, a negative pressure needs to be pre-established within the cavity of the detection component 500, and the target nuclide in the adsorption component 100 needs to undergo pre-de-intercalation. During this process, the adsorption component 100 and the detection component 500 remain disconnected. Then, when the preset negative pressure is established within the detection component 500, the preparation is complete. The second control valve group 720 controls the connection between the adsorption component 100 and the detection component 500. Under the action of the negative pressure, the target nuclide released by the adsorption component 100 will be adsorbed into the cavity of the detection component 500 for subsequent detection. In this embodiment, the vacuum pump component 710 is a vacuum pump, and the preset negative pressure is a set value. The designer can design it according to needs, as long as it can ensure that the target nuclide can be extracted into the cavity of the detection component 500 by the negative pressure. A vacuum gauge can be installed inside the detection component 500 to display the negative pressure value inside the detection component 500. The vacuum gauge can be networked with the controller for easy automation control. The second control valve group 720 includes a fourth valve located between the adsorption component 100 and the detection component 500.

[0075] In addition, when the transfer component 700 is under negative pressure and the detection component 500 is connected to the adsorption component 100, a certain amount of purge gas can be continuously introduced to fully remove the target nuclides released by the adsorption component 100.

[0076] Referring to Figure 5, it should be noted that the detection assembly 500 includes a windowed detector and a windowless detector. In the windowed detector, the incident window is covered by a spacer 530. When the transfer assembly 700 evacuates the detection chamber 520, the spacer 530 is affected by the negative pressure and will deform towards the detection chamber 520, which may easily lead to damage to the spacer 530. At the same time, when the transfer assembly 700 purges the detection chamber 520, the spacer 530 will also be disturbed by the air, which may easily lead to damage to the spacer 530. To prevent damage to the spacer membrane 530, in some specific embodiments of this application, the detection assembly 500 includes: an equipment chamber 510, a detection chamber 520, a spacer membrane 530, a spacer plate 540, and a detector 550. The equipment chamber 510 and the detection chamber 520 are interconnected through an entrance window, and the detection chamber 520 is connected to the adsorption assembly 100. The spacer membrane 530 is disposed at the entrance window; the spacer plate 540 is disposed at the entrance window and located on the side of the spacer membrane 530 away from the equipment chamber 510, and the spacer plate 540 can close or open the entrance window; the detector 550 is disposed inside the equipment chamber 510. The controller is configured to: control the spacer plate 540 to close the entrance window when the transfer assembly 700 transfers the target nuclide released from the adsorption assembly 100 to the detection chamber 520; and control the spacer plate 540 to open the entrance window and control the detector 550 located in the equipment chamber 510 to perform a detection operation after the adsorption assembly 100 has completed the transfer operation.

[0077] Specifically, referring to Figure 5, the detection component 500 is a windowed detector, the detector element 550 is located in the equipment chamber 510, and the target nuclide is located inside the detection chamber 520. When the transfer component 700 evacuates the detection chamber 520 or purges the target nuclide released by the adsorption component 100, the spacer plate 540 closes the entrance window to reduce the influence of the transfer component 700 on the spacer membrane 530. Simultaneously, after the transfer component 700 stops evacuating and the detection chamber 520 is connected to the adsorption component 100, the spacer plate 540 opens the entrance window, allowing the detector element 550 to perform the detection operation. Alternatively, when the transfer component 700 stops purging, the spacer plate 540 opens the entrance window, allowing the detector element 550 to perform the detection operation. In this embodiment, the target nuclide continuously decays, emitting particles in various directions during the decay process. Among these, some particles are emitted towards the detector element 550, which can be perpendicular to or inclined towards the detector element 550. When the target nuclide diffuses within the detection chamber 520, the particle can directly pass through the entrance window into the equipment chamber 510 and be detected by the detector 550. The detector 550 can detect particles emitted in different directions within the detection chamber 520, thereby detecting a greater number of particles and improving the detection accuracy of the detector 550. The detection chamber 520 is a sealed chamber, and its inner wall has a reflective layer that facilitates particle reflection. The equipment chamber 510 is also a sealed chamber. The detector 550 is a microstructured gas detector, and the spacer membrane 530 is a membrane that allows particles to pass through, such as a PT membrane. The transfer assembly 700 also includes a drive source, which is connected to the spacer 540 to drive the spacer 540 to open or close the entrance window. The drive source can be a motor-driven telescopic structure or telescopic rod, or a motor-driven spacer 540 to rotate. After the spacer 540 moves, it can be located on one side of the entrance window, or the entrance window can be located on the bottom surface of the detection chamber 520, with the spacer 540 rotating to the side of the detection chamber 520. The drive source is signal-connected to a controller, which controls the drive source to drive the spacer 540 to open or close the entrance window. Furthermore, the spacer 540 can also open only part of the entrance window.

[0078] It is understandable that by detecting the target nuclide through a separate detection chamber 520, the detector 550 can detect a larger number of particles, resulting in higher detection accuracy. Simultaneously, with the spacer 540 covering the entrance window and positioned on the side of the spacer membrane 530 away from the detection chamber 520, the spacer 540 supports the spacer membrane 530 or seals the entrance window during vacuuming or purging of the transfer assembly 700, thus protecting the spacer membrane 530 from damage.

[0079] Referring to FIG6, in some specific embodiments of this application, the detection component 500 includes: a detection chamber 520, a detection element 550, a working component 560, and a working valve 570. The detection chamber 520 is connected to the adsorption component 100, the detection element 550 is disposed within the detection chamber 520, the working component 560 is connected to the detection chamber 520 and is used to introduce working gas into the detection chamber 520, and the working valve 570 is used to control the connection and disconnection between the working component 560 and the detection chamber 520. The controller is configured to: when the transfer component 700 performs a transfer operation or after the adsorption component 100 completes a transfer operation, control the working valve 570 to keep the working component 560 and the detection chamber 520 in a connected state, control the working component 560 to introduce working gas into the detection chamber 520, and control the detection element 550 located in the detection chamber 520 to perform a detection operation.

[0080] Specifically, referring to Figure 6, the detection component 500 is a windowless detector, and the detector element 550 is directly disposed within the detection chamber 520, detecting the target nuclide within the detection chamber 520. After the working gas is introduced into the detection chamber 520, the detector element 550 detects the target nuclide. In this embodiment, the detection chamber 520 is a sealed chamber, the detector element 550 is a microstructure gas detector, and the working component 560 includes a working gas source, through which working gas is introduced into the detection chamber 520.

[0081] Referring to Figures 1 and 2, in some specific embodiments of this application, the sampling component 200 includes a sampling source, which may be a gas storage device 210 storing radioactive gas or a test pipe 230 discharging radioactive gas. The gas storage device 210 refers to an object that collects radioactive gas, such as a gas storage tank or a gas storage bag. The test pipe 230 extends to: a pipe that is discharging radioactive gas in real time, such as a chimney, an exhaust vent, or other test space.

[0082] When the sampling source is a gas storage device 210 containing radioactive gas, as shown in FIG1, the sampling assembly 200 includes a gas storage device 210 and a gas flow meter 220. The gas storage device 210 is connected to the adsorption assembly 100 and is used to store radioactive gas. The gas flow meter 220 is located in the pipeline between the gas storage device 210 and the adsorption assembly 100 and is used to detect the total amount of radioactive gas entering the adsorption assembly 100. The gas flow meter 220 is a gas mass flow meter (MFC).

[0083] Specifically, the radioactive gas stored in the gas storage unit 210 is introduced into the adsorption component 100 to adsorb the target nuclide in the radioactive gas. The gas flow meter 220 detects the total amount of radioactive gas delivered by the gas storage unit 210. When the monitoring component 300 detects the presence of the target nuclide in the radioactive gas passing through the adsorption component 100, the delivery of the gas from the gas storage unit 210 is stopped, and the total amount of radioactive gas recorded by the gas flow meter 220 is recorded. It should be noted that some target nuclides have long half-lives, providing a long detection time. These types of targets are suitable for detection using the gas storage unit 210 method, resulting in higher detection accuracy. Furthermore, the radioactive gas passing through the monitoring component 300 can be directly discharged for treatment or collected again.

[0084] When the sampling source is the test pipe 230 that discharges radioactive gas, as shown in FIG2, the sampling assembly 200 includes the test pipe 230, the inlet pipe 240, the outlet pipe 250 and the gas flow meter 220. The test pipe 230 is used to discharge radioactive gas and has a first position and a second position distributed sequentially along the discharge direction. The inlet pipe 240 is connected to the test pipe 230 and the adsorption assembly 100 at the first position, and the outlet pipe 250 is connected to the test pipe 230 and the monitoring assembly 300 at the second position. The gas flow meter 220 is installed in the inlet pipe 240 and is used to detect the total amount of radioactive gas entering the adsorption assembly 100.

[0085] Specifically, radioactive gas flowing in the test pipe 230 is introduced into the adsorption component 100 through a sampling pipe to adsorb the target nuclide in the radioactive gas. A gas flow meter 220 detects the total amount of radioactive gas delivered by the gas storage unit 210. When the monitoring component 300 detects the presence of the target nuclide in the radioactive gas passing through the adsorption component 100, sampling through the sampling pipe is stopped, and the total amount of radioactive gas recorded by the gas flow meter 220 is recorded. Real-time sampling is performed within the test pipe 230 through the inlet pipe 240. The radioactive gas with the adsorbed target nuclide is then discharged back into the test pipe 230 through the outlet pipe 250, and the outlet pipe 250 discharges the radioactive gas at a second location to avoid affecting the radioactive gas within the inlet pipe 240. It should be noted that some target nuclides have short half-lives and short detection times. If detection is performed through the gas storage device 210, the target nuclide may have already decayed during the gas transfer process, resulting in undetectable levels. Therefore, sampling and detection are performed directly during the emission of the target nuclide, leading to higher detection accuracy. Of course, directly sampling the test pipe 230 that emits radioactive gas is also suitable for scenarios where the target nuclide has a long half-life.

[0086] Referring to FIG3, in some specific embodiments of this application, the adsorption assembly 100 includes a housing 110 and a porous adsorption element 120. The housing 110 defines an adsorption cavity, which has a first connecting position and a second connecting position. The housing 110 is connected to the sampling assembly 200 at the first connecting position and to the monitoring assembly 300 or the detection assembly 500 at the second connecting position. The porous adsorption element 120 is disposed in the adsorption cavity and is located between the first connecting position and the second connecting position along the direction of radioactive gas transport.

[0087] The outer shell 110 is made of stainless steel, and its specific shape and size can be selected as needed. The porous adsorbent 120 includes granular materials and / or powdered materials such as metal-organic framework (MOF), non-metal-organic framework (COF), zeolite, molecular sieve, and activated carbon derivatives. In this embodiment, the outer shell 110 is a hollow cylinder. Granular or powdered materials are sequentially filled into the outer shell 110 along the axial direction of the cylinder to form the porous adsorbent 120. The outer shell 110 has a first connecting position and a second connecting position at both ends along the axial direction of the cylinder, respectively. Radioactive gas will pass through the porous adsorbent 120 along the axial direction of the cylinder and fully contact the porous adsorbent 120, so that the target nuclide is embedded in the pores of the porous adsorbent 120.

[0088] Referring to FIG4, in some other specific embodiments of this application, the adsorption component 100 includes a housing 110 and a separation membrane 130. The housing 110 defines a first cavity 111 and a second cavity 112. The first cavity 111 is connected to the sampling component 200, and the second cavity 112 is connected to the monitoring component 300 or the detection component 500. The separation membrane 130 is disposed between the first cavity 111 and the second cavity 112 and connects the first cavity 111 and the second cavity 112.

[0089] The outer shell 110 is also made of stainless steel, and its specific shape and size can be selected as needed. The separation membrane 130 is formed into a membrane shape from materials such as MOF and COF. In this embodiment, the outer shell 110 is also hollow cylindrical. The separation membrane 130 is located in the middle of the hollow cylinder along its axial direction, dividing the hollow cylinder into a first cavity 111 and a second cavity 112 that are substantially the same. Of course, the position of the separation membrane 130 can also be arranged as needed. For example, it can be located at one-third of the axial direction of the hollow cylinder, dividing the hollow cylinder into a first cavity 111 with one-third the size and a second cavity 112 with two-thirds the size, or a second cavity 112 with one-third the size and a first cavity 111 with two-thirds the size.

[0090] Furthermore, the desorption component 400 heats the porous adsorbent material. Specifically, this can be done by heating the outer shell 110 to intermittently heat the porous adsorbent 120 or the separation membrane 130, or by having the heating part of the desorption component 400 located inside the outer shell 110 to directly heat the porous adsorbent 120 or the separation membrane 130. The radioactive gas detection device also includes an activation component, which activates the porous adsorbent 120 or the separation membrane 130 to improve the adsorption effect of the porous adsorbent 120 or the separation membrane 130 on the target nuclide. The activation component is used to introduce a certain activation gas, such as nitrogen, into the adsorption component 100. After activation for a certain period of time, the activation component can remove impurities and moisture from the porous adsorbent 120 or the separation membrane 130, thereby improving the adsorption effect.

[0091] Referring to FIG4, in some specific embodiments of this application, the adsorption component 100 includes a housing 110 and a separation membrane 130, and the pressure in the second cavity 112 is less than the pressure in the first cavity 111.

[0092] It is worth understanding that by controlling the pressure in the second cavity 112 to be lower than the pressure in the first cavity 111, the radioactive gas in the first cavity 111 continuously moves toward the second cavity 112, and the target nuclide continuously embeds into the separation membrane 130, thereby improving the embedding efficiency of the target nuclide.

[0093] In this embodiment, the radioactive gas detection device further includes a back pressure valve 140, which is located between the adsorption component 100 and the monitoring component 300. The back pressure valve 140 is configured to adjust the pressure in the second chamber 112 to be lower than the pressure in the first chamber 111 when the pressure in the second chamber 112 is a preset pressure. Specifically, after radioactive gas is introduced for a period of time, both the first chamber 111 and the second chamber 112 are filled with radioactive gas, and the pressure between the first chamber 111 and the second chamber 112 is basically the same and continues to increase with the introduction of gas. However, the fact that the pressures in the first chamber 111 and the second chamber 112 are basically the same leads to a decrease in the efficiency of the target nuclide embedding into the separation membrane 130. Therefore, when the pressure in the second cavity 112 increases to the preset pressure, the preset pressure is greater than the external pressure, causing the back pressure valve 140 to open under the action of the pressure difference. The radioactive gas in the second cavity 112 will be discharged, which at the same time causes the pressure in the second cavity 112 to decrease and become lower than the pressure in the first cavity 111, thereby improving the efficiency of the target nuclide embedding separation membrane 130.

[0094] A second aspect of this application provides a detection method, the steps of which include:

[0095] S1: Radioactive gas is transported through adsorption component 100, and adsorption component 100 adsorbs the target nuclide in the radioactive gas;

[0096] S2: When the monitoring component 300 detects that the radioactive gas passing through the adsorption component 100 contains the target nuclide, the delivery of the radioactive gas is stopped, and the total amount of radioactive gas delivered X1 and the content of the target nuclide adsorbed by the adsorption component 100 X2 are obtained.

[0097] S3: Obtain the concentration of the target nuclide based on the total amount of radioactive gas X1 and the content of the target nuclide X2.

[0098] Specifically, when radioactive gas is transported through the adsorption component 100, the total amount of radioactive gas transported is counted in real time. For example, a gas flow meter 220 is installed before the radioactive gas enters the adsorption component 100. The gas flow meter 220 counts the radioactive gas passing through in real time. When the monitoring component 300 detects that the radioactive gas passing through the adsorption component 100 contains the target nuclide, the adsorption is stopped, and the total amount of radioactive gas input X1 is counted. Then, the adsorption component 100 releases the adsorbed target nuclide, and the detection component 500 detects the target nuclide released by the adsorption component 100 to obtain the content of the target nuclide X2. The target nuclide content X2 is divided by the total amount of radioactive gas X1 to obtain the concentration of the target nuclide in the radioactive gas, so as to determine whether the concentration of the target nuclide meets the emission requirements.

[0099] It is understandable that by monitoring the radioactive gas passing through the adsorption component 100, the monitoring component 300 can detect whether the target nuclide is present, and determine whether the adsorption component 100 has completed adsorption. The adsorption component 100 can adsorb a sufficient amount of target nuclide for detection. At the same time, the number of target nuclides passing through the monitoring component 300 is less, resulting in higher detection accuracy and content accuracy of the target nuclide, thereby improving the detection accuracy of the target nuclide concentration in the radioactive gas.

[0100] In some specific embodiments of this application, in S2, the target nuclide adsorbed by the adsorption component 100 is released by heating, and the content X2 of the target nuclide released by the adsorption component 100 is detected; wherein, the heating temperature range is 80℃~100℃.

[0101] It is understandable that heating causes the porous material in the adsorption component 100 to expand thermally, causing the target nuclide to be extracted from the pores of the porous material, thus separating the target nuclide from the porous material for detection. In this embodiment, the heating temperature is controlled between 80°C and 100°C, which reduces energy consumption and saves detection costs. The heating time is controlled between 1 hour and 2 hours, but the specific time can be extended or shortened depending on the amount of porous material.

[0102] The embodiments of this application have been described in detail above with reference to the accompanying drawings. However, this application is not limited to the above embodiments. Within the scope of knowledge possessed by those skilled in the art, various changes can be made without departing from the spirit of this application.

Claims

1. A radioactive gas detection device, used for detecting radioactive gases containing a target nuclide, characterized in that, include: The adsorption component is capable of adsorbing the target nuclide in the radioactive gas; A sampling component, connected to the adsorption component, is used to supply the radioactive gas to the adsorption component; A monitoring component, connected to the adsorption component, is used to monitor the target nuclide in the radioactive gas after it has passed through the adsorption component; A desorption component is used to cause the adsorption component to release the adsorbed target nuclide; A detection component, connected to the adsorption component, is used to detect the content of the target nuclide released by the adsorption component; The first control valve group is used to switch the on / off state between the adsorption component and the sampling component, between the adsorption component and the monitoring component, and between the adsorption component and the detection component; Controller; The controller is configured to: when the monitoring component detects that the radioactive gas after passing through the adsorption component contains the target nuclide, control the first control valve group to disconnect the adsorption component from the sampling component and from the monitoring component, and to connect the adsorption component to the detection component; and control the detection component to perform a detection operation on the target nuclide released from the adsorption component to obtain the content of the target nuclide.

2. The radioactive gas detection device according to claim 1, characterized in that: The radioactive gas detection device further includes a transfer component, which is used to transfer the target nuclide released by the adsorption component to the detection component.

3. The radioactive gas detection device according to claim 2, characterized in that: The detection assembly includes: an equipment chamber, a detection chamber, a spacer membrane, a spacer plate, and a detection element. The equipment chamber and the detection chamber are interconnected through an entrance window, and the detection chamber is connected to the adsorption assembly. The spacer membrane is disposed at the entrance window. The spacer plate is disposed at the entrance window and located on the side of the spacer membrane away from the equipment chamber. The spacer plate can close or open the entrance window. The detection element is disposed inside the equipment chamber. The controller is configured to: control the spacer to close the incident window when the transfer component transfers the target nuclide released from the adsorption component to the detection chamber; and control the spacer to open the incident window and control the detector located in the equipment chamber to perform the detection operation after the adsorption component has completed the transfer operation.

4. The radioactive gas detection device according to claim 2, characterized in that, The detection assembly includes: a detection chamber, a detection element, a working assembly, and a working valve. The detection chamber is connected to the adsorption assembly. The detection element is disposed inside the detection chamber. The working assembly is connected to the detection chamber and is used to introduce working gas into the detection chamber. The working valve is used to control the connection and disconnection between the working assembly and the detection chamber. The controller is configured to: control the working valve to make the working component and the detection chamber in a connected state when the transfer component performs the transfer operation or after the adsorption component completes the transfer operation, control the working component to introduce the working gas into the detection chamber, and control the detector located in the detection chamber to perform the detection operation.

5. The radioactive gas detection device according to claim 2, characterized in that: The transfer component, the adsorption component, and the detection component are connected in sequence. The transfer component is used to deliver purge gas that does not react with the target nuclide to the detection component, so as to purge the target nuclide released by the adsorption component to the detection component. And / or, The transfer assembly includes a vacuum pumping assembly and a second control valve group. The vacuum pumping assembly is connected to the detection assembly, and the second control valve group is used to switch the on / off connection between the detection assembly and the vacuum pumping assembly, as well as the on / off connection between the detection assembly and the adsorption assembly. The controller is configured to: when the transfer component performs a transfer operation, control the second control valve group to make the detection component and the vacuum component in a connected state, and to make the detection component and the adsorption component in a disconnected state, while the vacuum component performs a vacuum operation; when a preset negative pressure is formed in the detection component, control the second control valve group to make the detection component and the vacuum component in a disconnected state, and to make the detection component and the adsorption component in a connected state.

6. The radioactive gas detection device according to claim 1, characterized in that: The sampling assembly includes a gas storage unit and a gas flow meter. The gas storage unit is connected to the adsorption assembly and is used to store the radioactive gas. The gas flow meter is located in the pipeline between the gas storage unit and the adsorption assembly and is used to detect the total amount of radioactive gas entering the adsorption assembly. or, The sampling assembly includes a test pipe, an inlet pipe, an outlet pipe, and a gas flow meter. The test pipe is used to discharge the radioactive gas and has a first position and a second position distributed sequentially along the discharge direction. The inlet pipe connects the test pipe and the adsorption assembly at the first position, and the outlet pipe connects the test pipe and the monitoring assembly at the second position. The gas flow meter is located in the inlet pipe and is used to detect the total amount of radioactive gas entering the adsorption assembly.

7. The radioactive gas detection device according to claim 1, characterized in that: The adsorption assembly includes a shell and a porous adsorption element. The shell defines an adsorption cavity with a first connecting position and a second connecting position. The shell is connected to the sampling assembly at the first connecting position and to the monitoring assembly or the detection assembly at the second connecting position. The porous adsorption element is disposed in the adsorption cavity and is located between the first connecting position and the second connecting position along the direction of radioactive gas delivery. or, The adsorption assembly includes a shell and a separation membrane. The shell defines a first cavity and a second cavity. The first cavity is connected to the sampling assembly, and the second cavity is connected to the monitoring assembly or the detection assembly. The separation membrane is disposed between the first cavity and the second cavity and connects the first cavity and the second cavity.

8. The radioactive gas detection device according to claim 7, characterized in that: The adsorption assembly includes a shell and a separation membrane, and the pressure in the second cavity is lower than the pressure in the first cavity.

9. A detection method, characterized in that, The steps include: S1: Radioactive gas is conveyed through an adsorption assembly, which adsorbs the target nuclide in the radioactive gas; S2: When the monitoring component detects that the radioactive gas passing through the adsorption component contains the target nuclide, the delivery of the radioactive gas is stopped, and the total amount of the delivered radioactive gas X1 and the content of the target nuclide adsorbed by the adsorption component X2 are obtained. S3: Obtain the concentration of the target nuclide based on the total amount of radioactive gas X1 and the content of the target nuclide X2.

10. The detection method according to claim 9, characterized in that: In S2, the target nuclide adsorbed by the adsorption component is released by heating, and the content X2 of the target nuclide released by the adsorption component is detected. The heating temperature range is 80℃~100℃.

Images