Radioactive gas detection device and detection method

Abstract

The invention discloses a radioactive gas detection device and a detection method.The radioactive gas detection device is applied to detection of radioactive gas containing target nuclides 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, 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 control the first control valve group to enable the adsorption assembly and the sampling assembly as well as the adsorption assembly and the monitoring assembly to be in a disconnected state when the monitoring assembly monitors that the radioactive gas passing through the adsorption assembly contains target nuclide; the adsorption assembly and the detection assembly are in a communication state, and the detection assembly is controlled to execute detection operation on the target nuclide released from the adsorption assembly so as to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection precision of the target nuclide in the radioactive gas.

Description

Technical Field

[0001] The present invention relates to the field of radioactive gas detection, and in particular to a radioactive gas detection device and a detection method. Background Art

[0002] For industries that produce waste gas during the production process, gas emission standards are usually formulated to ensure that the emission of waste gas will not pollute the environment and achieve sustainable development. For example, in the nuclear power field, its airborne radioactive effluents need to be monitored after purification. The measurement content includes the total emission, emission concentration and the content of major radionuclides. After the measurement meets the standard, it must be released into the atmosphere through the chimney.

[0003] In the related art, when using a detector to detect trace nuclides, an adsorbent material adsorbed with trace nuclides, such as filter paper, is often placed in the detection window of the detector, and the activity concentration of α / β particles released by the trace nuclides is determined using the α / β characteristic track analysis method to detect the concentration of trace radioactive noble gas nuclides. However, during the detection process, it was found that when the filter paper or other adsorbent material is directly placed in the detection window of the detector for detection, only a portion of the particles injected into the detector window can be detected, and the remaining particles injected into the environment cannot be calculated, resulting in poor detection accuracy. In addition, when the detector detects a target nuclide with a preset content, the detection accuracy of the detector is better, and when the target nuclide content is too low, the detection accuracy of the detector is poor. Summary of the invention

[0004] The present invention aims to solve at least one of the technical problems existing in the prior art. To this end, the present invention provides a radioactive gas detection device that can improve the detection accuracy of target nuclides in radioactive gases.

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

[0006] The radioactive gas detection device according to the first embodiment of the present invention is applied to the detection of radioactive gas containing target nuclides, and includes: an adsorption component capable of adsorbing target nuclides in the radioactive gas; A sampling component, connected to the adsorption component, and used to provide the radioactive gas to the adsorption component; A monitoring component, connected to the adsorption component, for monitoring the target nuclide in the radioactive gas after passing through the adsorption component; A desorption component, used to make the adsorption component release the adsorbed target nuclide; A detection component, connected to the adsorption component, for detecting the content of the target nuclide released by the adsorption component; A first control valve group, used for switching on and off 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; Wherein, 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 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.

[0007] The radioactive gas detection device according to the first embodiment of the present invention has at least the following beneficial effects: 1. The adsorption component adsorbs the target nuclides in the radioactive gas. When the adsorption component cannot completely absorb the target nuclides in the radioactive gas, the monitoring component will detect that the radioactive gas passing through the adsorption component contains the target nuclides. 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 connect the adsorption component to the detection component. The desorption component drives the adsorption component to release the adsorbed target nuclides, and the detection component detects the content of the target nuclides released by the adsorption component, so that the detection accuracy of the target nuclides is higher. 2. The monitoring component monitors the change in the concentration of the radioactive gas passing through the adsorption component to determine whether the adsorption of the adsorption component is completed, so that the adsorption component can fully adsorb the target nuclide, and only a trace amount of the target nuclide escapes. The escaped target nuclide has a smaller impact on the detection accuracy of the overall target nuclide; and sufficient target nuclides can meet the detection needs of the detection component, making the detection of the detection component more accurate.

[0008] According to some embodiments of the present invention, the radioactive gas detection device further includes a transfer component, and the transfer component is used to transfer the target nuclide released by the adsorption component to the detection component.

[0009] According to some embodiments of the present invention, the detection assembly includes: an equipment chamber, a detection chamber, a spacer membrane, a spacer plate and a detection member, the equipment chamber and the detection chamber are connected to each other through an incident window, and the detection chamber is connected to the adsorption assembly; the spacer membrane is arranged at the incident window; the spacer plate is arranged at the incident window and is located at a side of the spacer membrane away from the equipment chamber, and the spacer plate can close or open the incident window; the detection member is arranged in the equipment chamber; Wherein, the controller is configured to: when the transfer component transfers the target nuclide released from the adsorption component to the detection room, control the partition plate to close the incident window; after the adsorption component completes the transfer operation, control the partition plate to open the incident window, and control the detection component located in the equipment room to perform the detection operation.

[0010] According to some embodiments of the present invention, the detection assembly comprises: a detection chamber, a detection member, a working assembly and a working valve, the detection chamber is connected to the adsorption assembly, the detection member is arranged in the detection chamber, the working assembly is connected to the detection chamber and is used to pass the working gas into the detection chamber, and the working valve is used to control the connection and disconnection between the working assembly and the detection chamber; Wherein, the controller is configured to: when the transfer component performs the transfer operation or after the adsorption component completes the transfer operation, control the working valve to make the working component and the detection chamber in a connected state, control the working component to pass the working gas into the detection chamber, and control the detection component located in the detection chamber to perform the detection operation.

[0011] According to some embodiments of the present invention, the transfer component, the adsorption component and the detection component are sequentially connected, and the transfer component is used to deliver a purge gas that does not react with the target nuclide to the detection component to purge the target nuclide released by the adsorption component to the detection component; and / or, The transfer component includes a vacuum component and a second control valve group, the vacuum component is connected to the detection component, and the second control valve group is used to switch the connection between the detection component and the vacuum component and the connection between the detection component and the adsorption component; Wherein, the controller is configured as follows: when the transfer component performs a transfer operation, the second control valve group is controlled to make the detection component and the vacuum component in a connected state, and the detection component and the adsorption component in a disconnected state, and the vacuum component performs a vacuum operation; when a preset negative pressure is formed in the detection component, the second control valve group is controlled to make the detection component and the vacuum component in a disconnected state, and the detection component and the adsorption component in a connected state.

[0012] According to some embodiments of the present invention, the sampling assembly includes a gas storage component and a gas flow meter, the gas storage component is connected to the adsorption component and is used to store the radioactive gas; the gas flow meter is arranged in a pipeline between the gas storage component and the adsorption component and is used to detect the total amount of the radioactive gas entering the adsorption component; or, The sampling component includes a pipeline to be tested, a sample inlet pipeline, a sample outlet pipeline and a gas flow meter. The pipeline to be tested is used to discharge the radioactive gas and has a first position and a second position distributed in sequence along the discharge direction. The sample inlet pipeline connects the pipeline to be tested and the adsorption component at the first position, and the sample outlet pipeline connects the pipeline to be tested and the monitoring component at the second position. The gas flow meter is arranged on the sample inlet pipeline and is used to detect the total amount of the radioactive gas entering the adsorption component.

[0013] According to some embodiments of the present invention, the adsorption component includes a shell and a porous adsorption member, the shell defines an adsorption chamber, the adsorption chamber has a first communication position and a second communication position, the shell is connected to the sampling component at the first communication position, the shell is connected to the monitoring component or the detection component at the second communication position, the porous adsorption member is arranged in the adsorption chamber, and is arranged between the first communication position and the second communication position along the transport direction of the radioactive gas; or, The adsorption component includes an outer shell and a separation membrane, the outer shell defines a first cavity and a second cavity, the first cavity is connected to the sampling component, the second cavity is connected to the monitoring component or the detection component, and the separation membrane is arranged between the first cavity and the second cavity and connects the first cavity and the second cavity.

[0014] According to some embodiments of the present invention, 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.

[0015] According to the detection method of the second embodiment of the present invention, the steps include: S1: transporting radioactive gas through an adsorption component, wherein the adsorption component adsorbs target nuclides 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 X1 of the delivered radioactive gas and the content X2 of the target nuclide adsorbed by the adsorption component are obtained; S3: Obtaining the concentration of the target nuclide according to the total amount of radioactive gas X1 and the target nuclide content X2.

[0016] According to the detection method of the embodiment of the second aspect of the present invention, there are at least the following beneficial effects: the monitoring component monitors whether the radioactive gas passing through the adsorption component contains the target nuclide, and determines whether the adsorption component has completed adsorption. The adsorption component can adsorb a sufficient amount of the target nuclide for detection. At the same time, fewer target nuclides pass through the monitoring component, and the detection accuracy and content accuracy of the target nuclides are higher, thereby improving the detection accuracy of the target nuclide concentration in the radioactive gas.

[0017] According to some embodiments of the present invention, in S2, the target nuclide adsorbed by the adsorption component is released by heating, and the target nuclide content X2 released by the adsorption component is detected; wherein the heating temperature ranges from 80°C to 100°C.

[0018] Additional aspects and advantages of the present invention will be given in part in the following description and in part will be obvious from the following description, or will be learned through practice of the present invention. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] The present invention will be further described below with reference to the accompanying drawings and embodiments, wherein: Figure 1 This is a schematic structural diagram of a sampling assembly taking samples from a gas storage member in a radioactive gas detection device according to an embodiment of the present invention; Figure 2 This is a schematic diagram of the structure of a sampling assembly in a radioactive gas detection device according to an embodiment of the present invention for sampling a pipeline to be tested; Figure 3 It is a schematic structural diagram of a radioactive gas detection device according to an embodiment of the present invention when an adsorption component uses a porous adsorption member; Figure 4 It is a schematic structural diagram of a radioactive gas detection device in an embodiment of the present invention when an adsorption component uses a separation membrane and purge transfer; Figure 5 This is a schematic diagram of the structure of a radioactive gas detection device in an embodiment of the present invention when the detection component is a window detector and negative pressure transfer is used; Figure 6 This is a schematic structural diagram of a radioactive gas detection device in an embodiment of the present invention in which the detection component is a windowless detector and negative pressure transfer is used.

[0020] Figure Number: Adsorption assembly 100; housing 110; first cavity 111; second cavity 112; porous adsorption member 120; separation membrane 130; back pressure valve 140; Sampling assembly 200; gas storage element 210; gas flow meter 220; pipeline to be tested 230; sampling pipeline 240; sampling pipeline 250; Monitoring component 300; Desorption assembly 400; Detection assembly 500; equipment chamber 510; detection chamber 520; partition membrane 530; partition plate 540; detection member 550; working assembly 560; working valve 570; A first control valve group 600; a first valve 610; a second valve 620; a third valve 630; Transfer assembly 700 ; vacuum assembly 710 ; second control valve assembly 720 . DETAILED DESCRIPTION

[0021] Embodiments of the present invention are described in detail below, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present invention, and cannot be understood as limiting the present invention.

[0022] In the description of the present invention, it should be understood that descriptions involving orientation, such as orientation or positional relationship indicated as up, down, etc., are based on the orientation or positional relationship shown in the drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore should not be understood as a limitation on the present invention.

[0023] In the description of the present invention, "a number" refers to one or more than one, and "a plurality" refers to two or more than two. If there is a description of "first" or "second", it is only used for the purpose of distinguishing technical features, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features or implicitly indicating the order of the indicated technical features.

[0024] In the description of the present invention, unless otherwise clearly defined, terms such as setting, installing, connecting, etc. should be understood in a broad sense, and technicians in the relevant technical field can reasonably determine the specific meanings of the above terms in the present invention based on the specific content of the technical solution.

[0025] In the related art, when using a detector to detect trace nuclides, an adsorbent material adsorbed with trace nuclides, such as filter paper, is often placed in the detection window of the detector, and the activity concentration of α / β particles released by the trace nuclides is determined using the α / β characteristic track analysis method to detect the concentration of trace radioactive noble gas nuclides. However, during the detection process, it was found that when the filter paper or other adsorbent material is placed directly in the detection window of the detector for detection, only the particles vertically shot into the detector window can be detected, and the remaining particles shot into the environment cannot be calculated, resulting in poor detection accuracy. In addition, when the detector detects a target nuclide with a preset content, the detection accuracy of the detector is better, and when the target nuclide content is too low, the detection accuracy of the detector is poor.

[0026] Reference Figures 1 to 6 As shown, an embodiment of the first aspect of the present invention proposes a radioactive gas detection device, which is used for detecting radioactive gas containing target nuclides. 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, wherein 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.

[0027] It should be noted that radioactive gas refers to gas containing radioactive nuclides, which are atoms with radioactivity. Target nuclides are one or more radioactive nuclides in the radioactive gas.

[0028] 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 pore structure of the porous material is a highly ordered network structure with a large specific surface area, which provides a suitable adsorption and storage space, thereby enhancing the porous material's adsorption capacity for nuclide molecules; and the porous material can specifically adsorb and store the required nuclides, thereby separating the nuclides from other molecules. In other words, the pores of the porous material can just accommodate the target nuclides. When the radioactive gas passes through the porous material of the adsorption component 100, the target nuclides are embedded in the pores of the porous material, and the remaining gas passes through the porous material, thereby realizing the extraction of the target nuclides in the radioactive gas.

[0029] The sampling assembly 200 is connected to the adsorption assembly 100 and is used to provide radioactive gas to the adsorption assembly 100. The radioactive gas is stably provided through the sampling assembly 200, so that the radioactive gas stably passes through the adsorption assembly 100, and the target nuclides are continuously embedded in the pores of the porous material.

[0030] The monitoring component 300 is connected to the adsorption component 100 and is used to monitor the target nuclides in the radioactive gas after passing through the adsorption component 100; the monitoring component 300 can monitor in real time whether the target nuclides exist in the radioactive gas, and the monitoring component 300 is a mass spectrometer, chromatograph, etc. When the monitoring component 300 detects the presence of the target nuclides in the radioactive gas passing through the adsorption component 100, the adsorption of the adsorption component 100 has been completed.

[0031] It should be noted that the adsorption component 100 includes a partially adsorbed state, a substantially fully adsorbed state, and a completely fully adsorbed state when adsorbing the target nuclide.

[0032] The incomplete adsorption state means that the adsorption component 100 can completely adsorb the target nuclides in the passing radioactive gas, and there are still sufficient pores in the porous material. In the incomplete adsorption state, the monitoring component 300 cannot detect the target nuclides, and at the same time, it is impossible to determine the content of the target nuclides adsorbed in the adsorption component 100. If detection is performed in the incomplete adsorption state, the content of the target nuclides is likely to be low, resulting in a decrease in the detection accuracy of the detection component 500.

[0033] The basically full adsorption state means that the adsorption component 100 can adsorb most of the target nuclides in the passing radioactive gas, and only a very small part of the nuclides pass through the adsorption component 100. In the basically full adsorption state, the monitoring component 300 detects the target nuclides, and the monitored target nuclides continue to rise. When the monitoring component 300 detects the target nuclides, the adsorption component 100 has just entered the basically full adsorption state, and the content of the target nuclides in the adsorption component 100 can meet the accuracy requirements of the detection component 500. At the same time, only a small amount of target nuclides are lost, and the detection accuracy of the target nuclides is higher.

[0034] The fully adsorbed state means that all pores of the porous material in the adsorption assembly 100 are embedded with the target nuclide, and no target nuclide is adsorbed when the radioactive gas passes through. In the fully adsorbed state, the target nuclide content detected by the monitoring assembly 300 remains stable, but in the process from the monitoring assembly 300 detecting the target nuclide to the target nuclide content being stable, part of the target nuclide passes through the monitoring assembly 300 and is discharged, resulting in a decrease in the target nuclide content and a serious impact on the detection accuracy.

[0035] Therefore, in this embodiment, the monitoring component 300 is used to monitor whether the radioactive gas passing through the adsorption component 100 contains nuclides. When nuclides appear, it is determined that the adsorption component 100 is just in a basically full adsorption state. At this time, the adsorption component 100 adsorbs an appropriate amount of target nuclides, and the target nuclide content can reach the accurate detection range of the detection component 500. The detection accuracy of the detection component 500 is higher, and the target nuclides are detected when passing through the monitoring component 300. The escape amount of the target nuclides is lower, and the content of the target nuclides is more accurate, which improves the content accuracy of the target nuclides and the detection accuracy, so that the calculated concentration of the target nuclides in the radioactive gas is more accurate.

[0036] The desorption component 400 is used to make the adsorption component 100 release the adsorbed target nuclide; specifically, the adsorption component 100 embeds the target nuclide through the pores. When the desorption component 400 heats the target nuclide, the porous material expands due to the heat, so that the pores are further enlarged, and the target nuclide cannot be embedded in the pores, resulting in the de-embedding of the target nuclide, thereby separating the target nuclide 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. In addition, the desorption component 400 can directly heat the adsorption component 100, or it can be a porous material in the adsorption component 100 that is manually transferred and then heated separately.

[0037] 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, among which there are particles emitted toward the detection surface, and the particles can be vertically toward the detection surface or inclined toward 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 in the cavity, so as to detect more particles, so that the detection accuracy of the detection component 500 is higher.

[0038] The first control valve group 600 is used to switch the connection 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 arranged between the adsorption component 100 and the sampling component 200, a second valve 620 arranged between the adsorption component 100 and the monitoring component 300, and a third valve 630 arranged between the adsorption component 100 and the detection component 500. Among them, the second valve 620 can also be arranged at the tail end of the monitoring component 300 along the direction of radioactive gas transmission. In addition, the second valve 620 and the third valve 630 can be integrated into a three-way valve, and the connection between the adsorption component 100 and the sampling component 200 and the connection between the adsorption component 100 and the detection component 500 are controlled by the same three-way valve.

[0039] 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, wherein 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 and the sampling component 200, as well as the adsorption component 100 and the monitoring component 300; specifically, when the monitoring component 300 detects that the radioactive gas passing through the adsorption component 100 contains the target nuclide, the adsorption component 100 is in a basically full adsorption state, at which time the controller controls the first valve 610 and the second valve 620 to close, the sampling component 200 no longer transports the radioactive gas through the adsorption component 100 to determine the total amount of the transported radioactive gas, and the radioactive gas no longer flows out of the monitoring component 300 to avoid the 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. According to 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.

[0040] It is worth understanding that the adsorption component 100 adsorbs the target nuclides in the radioactive gas. When the adsorption component 100 cannot completely absorb the target nuclides in the radioactive gas, that is, when the adsorption component 100 is in a basically full adsorption state, the monitoring component 300 will detect that the radioactive gas passing through the adsorption component 100 contains the target nuclides. At this time, the controller controls the first control valve group 600 to disconnect the adsorption component 100 from the sampling component 200 and the adsorption component 100 from the monitoring component 300, and to connect the adsorption component 100 to the detection component 500. The desorption component 400 drives the adsorption component 100 to the detection component 500. The attachment component 100 releases the adsorbed target nuclides, and the detection component 500 detects the content of the target nuclides released by the adsorption component 100, so that the detection accuracy of the target nuclides is higher; the monitoring component 300 monitors the change in the concentration of the radioactive gas passing through the adsorption component 100 to determine whether the adsorption of the adsorption component 100 is completed, so that the adsorption component 100 can fully adsorb the target nuclides, and only a trace amount of the target nuclides escape. The escaped target nuclides have less impact on the detection accuracy of the overall target nuclides; and sufficient target nuclides can meet the detection requirements of the detection component 500, so that the detection of the detection component 500 is more accurate.

[0041] Reference Figure 4 , Figure 5 and Figure 6As shown, in some embodiments of the present invention, 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 worth understanding that the transfer component 700 can transfer the target nuclide released by the adsorption component 100 to the cavity in the detection component 500 by negative pressure transfer or purge transfer, so as to facilitate the detection component 500 to detect the target nuclide.

[0042] Reference Figure 4 , Figure 5 and Figure 6 As shown, in some specific embodiments of the present invention, the transfer assembly 700 includes transfer modes such as purge transfer, negative pressure transfer, and combinations thereof.

[0043] When the transfer assembly 700 is in the purge transfer, refer to Figure 4 As shown, the transfer assembly 700 , the adsorption assembly 100 and the detection assembly 500 are connected in sequence, and the transfer assembly 700 is used to transport the purge gas that does not react with the target nuclide to the detection assembly 500 to purge the target nuclide released by the adsorption assembly 100 to the detection assembly 500 .

[0044] Specifically, the purging process of the transfer component 700 can be that the transfer component 700 is purging while the desorption component 400 is heating the adsorption component 100 to achieve the transfer of the target nuclide. Alternatively, the desorption component 400 first heats the adsorption component 100, and the transfer component 700 then purges. 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, and the purge gas is continuously input through the purge gas source, so that the target nuclide released by the adsorption component 100 is purged into the cavity of the detection component 500.

[0045] When the transfer assembly 700 is under negative pressure transfer, refer to Figure 5 and Figure 6As shown, the transfer component 700 includes a vacuum pumping component 710 and a second control valve group 720, the vacuum pumping 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 vacuum pumping component 710 and the connection between the detection component 500 and the adsorption component 100; wherein the controller is configured to: when the transfer component 700 performs a transfer operation, control the second control valve group 720 to make the detection component 500 and the vacuum pumping component 710 in a connected state, and make the detection component 500 and the adsorption component 100 in a disconnected state, and the vacuum pumping component 710 performs a vacuum pumping operation; when a preset negative pressure is formed in the detection component 500, control the second control valve group 720 to make the detection component 500 and the vacuum pumping component 710 in a disconnected state, and make the detection component 500 and the adsorption component 100 in a connected state.

[0046] Specifically, before the negative pressure is transferred, it is necessary to pre-form a negative pressure in the cavity of the detection component 500, and the target nuclide in the adsorption component 100 is pre-deembedded. During this process, the adsorption component 100 and the detection component 500 remain disconnected; then, when the preset negative pressure is formed in the detection component 500, the preparation is completed, and the adsorption component 100 is controlled to communicate with the detection component 500 through the second control valve group 720. 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 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 drawn out into the cavity of the detection component 500 by the negative pressure. A vacuum gauge can be set in the detection component 500 to display the negative pressure value in the detection component 500. The vacuum gauge can be connected to the controller for easy automatic control. The second control valve assembly 720 includes a fourth valve disposed between the adsorption assembly 100 and the detection assembly 500 .

[0047] In addition, when the transfer assembly 700 is transferred under negative pressure and the detection assembly 500 is connected to the adsorption assembly 100 , a certain amount of purge gas can be continuously introduced to fully discharge the target nuclides released by the adsorption assembly 100 .

[0048] Reference Figure 5As shown, it should be noted that the detection component 500 includes a window-type detector and a windowless detector. In the window-type detector, the incident window position covers the spacer membrane 530. When the transfer component 700 evacuates the detection chamber 520, the spacer membrane 530 is affected by the negative pressure and deforms toward one side of the detection chamber 520, which can easily cause damage to the spacer membrane 530. At the same time, when the transfer component 700 purges the detection chamber 520, the spacer membrane 530 is also disturbed by the air, which can easily cause damage to the spacer membrane 530. In order to avoid the occurrence of damage to the spacer membrane 530, in some specific embodiments of the present invention, the detection component 500 includes: an equipment chamber 510, a detection chamber 520, a spacer membrane 530, a spacer plate 540 and a detection member 550, the equipment chamber 510 and the detection chamber 520 are interconnected through an incident window, and the detection chamber 520 is connected to the adsorption component 100; the spacer membrane 530 is arranged at the incident window; the spacer plate 540 is arranged at the incident window and is 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 incident window; the detection member 550 is arranged in the equipment chamber 510; wherein the controller is configured to: when the transfer component 700 transfers the target nuclide released from the adsorption component 100 to the detection chamber 520, control the spacer plate 540 to close the incident window; after the adsorption component 100 completes the transfer operation, control the spacer plate 540 to open the incident window, and control the detection member 550 located in the equipment chamber 510 to perform the detection operation.

[0049] Specifically, refer to Figure 5As shown, the detection assembly 500 is a window-type detector, the detection element 550 is arranged in the equipment room 510, and the target nuclide is located in the detection room 520. When the transfer assembly 700 evacuates or purges the target nuclide released by the adsorption assembly 100 into the detection room 520, the partition plate 540 closes the incident window to reduce the impact of the transfer assembly 700 on the partition film 530. At the same time, after the transfer assembly 700 stops evacuating and the detection room 520 is connected to the adsorption assembly 100, the partition plate 540 opens the incident window, and the detection element 550 can perform the detection operation. Or when the transfer assembly 700 stops purging, the partition plate 540 opens the incident window, and the detection element 550 can perform the detection operation. In this embodiment, the target nuclide will continue to decay, and during the decay process, the target nuclide emits particles in all directions, among which there are particles emitted toward the detection element 550, and the particles can be vertically toward the detection element 550 or inclined toward the detection element 550. When the target nuclide is dispersed in the detection chamber 520, the particle can directly pass through the incident window into the equipment chamber 510 and be detected by the detection element 550. The detection element 550 can detect particles emitted in different directions in the detection chamber 520 to detect more particles, thereby improving the detection accuracy of the detection element 550. The detection chamber 520 is a closed chamber, and the inner wall of the detection chamber 520 has a reflective layer that is easy for particles to reflect. The equipment chamber 510 is also a closed chamber. The detection element 550 is a microstructure gas detector, and the spacer film 530 is a film that allows particles to pass, such as a PT film. The transfer assembly 700 also includes a driving source, which is connected to the partition plate 540 in a transmission manner to drive the partition plate 540 to open or close the incident window. The driving source can be a telescopic structure or a telescopic rod driven by a motor or a motor to drive the partition plate 540 to rotate, wherein, after the partition plate 540 moves, the partition plate 540 can be located on one side of the incident window or the incident window is located on the bottom surface of the detection chamber 520, and the partition plate 540 rotates to the side of the detection chamber 520. The driving source is connected to the controller signal, and the controller controls the driving source to drive the partition plate 540 to open or close the incident window. In addition, the partition plate 540 can also only open part of the incident window.

[0050] It is worth understanding that by detecting the target nuclide through the separate detection chamber 520, the detection element 550 can detect a larger number of particles, making the detection accuracy of the detection element 550 higher. At the same time, the spacer plate 540 covers the incident window, and the spacer plate 540 is located on the side of the spacer membrane 530 away from the detection chamber 520. When the transfer assembly 700 is vacuumed or purged, the spacer plate 540 will support the spacer membrane 530 or seal the incident window, so that the spacer membrane 530 is protected by the spacer plate 540 and is not easily damaged.

[0051] Reference Figure 6As shown, in some specific embodiments of the present invention, the detection component 500 includes: a detection chamber 520, a detection member 550, a working component 560 and a working valve 570, the detection chamber 520 is connected to the adsorption component 100, the detection member 550 is arranged in the detection chamber 520, the working component 560 is connected to the detection chamber 520, and is used to pass the working gas into the detection chamber 520, and the working valve 570 is used to control the connection between the working component 560 and the detection chamber 520; wherein, the controller is configured to: when the transfer component 700 performs the transfer operation or after the adsorption component 100 completes the transfer operation, control the working valve 570 to make the working component 560 and the detection chamber 520 in a connected state, and control the working component 560 to pass the working gas into the detection chamber 520, and control the detection member 550 located in the detection chamber 520 to perform the detection operation.

[0052] Specifically, refer to Figure 6 As shown, the detection assembly 500 is a windowless detector, and the detection member 550 is directly disposed in the detection chamber 520, and detects the target nuclide in the detection chamber 520. After the working gas is introduced into the detection chamber 520, the detection member 550 detects the target nuclide. In this embodiment, the detection chamber 520 is a closed chamber, the detection member 550 is a microstructure gas detector, and the working assembly 560 includes a working gas source, through which the working gas is introduced into the detection chamber 520.

[0053] Reference Figure 1 and Figure 2 As shown, in some specific embodiments of the present invention, the sampling component 200 includes a sampling source, which can be a gas storage component 210 storing radioactive gas, or a pipe to be tested 230 that discharges radioactive gas. The gas storage component 210 refers to an object that collects radioactive gas, such as a gas tank, or a gas bag, etc.; the pipe to be tested 230 is a pipe that is discharging radioactive gas in real time, such as a chimney, an exhaust ventilation pipe or other space to be tested.

[0054] When the sampling source is a gas storage member 210 storing radioactive gas, refer to Figure 1 As shown, the sampling assembly 200 includes a gas storage member 210 and a gas flow meter 220. The gas storage member 210 is connected to the adsorption assembly 100 and is used to store radioactive gas. The gas flow meter 220 is provided in a pipeline between the gas storage member 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).

[0055] Specifically, the radioactive gas stored in the gas storage 210 is passed into the adsorption assembly 100 to achieve the adsorption of the target nuclides in the radioactive gas. The gas flow meter 220 detects the total amount of radioactive gas transported by the gas storage 210. When the monitoring assembly 300 detects that the radioactive gas passing through the adsorption assembly 100 contains the target nuclides, the transport of the gas storage 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 a long half-life and a long detection time. Such targets are suitable for detection by the gas storage 210, and the detection accuracy is higher. In addition, the radioactive gas passing through the monitoring assembly 300 can be directly discharged for treatment or collected again.

[0056] When the sampling source is the pipeline 230 to be tested that discharges radioactive gas, refer to Figure 2 As shown, the sampling component 200 includes a pipeline to be tested 230, a sample inlet pipeline 240, a sample outlet pipeline 250 and a gas flow meter 220. The pipeline to be tested 230 is used to discharge radioactive gas, and has a first position and a second position distributed in sequence along the discharge direction. The sample inlet pipeline 240 connects the pipeline to be tested 230 and the adsorption component 100 at the first position, and the sample outlet pipeline 250 connects the pipeline to be tested 230 and the monitoring component 300 at the second position. The gas flow meter 220 is arranged on the sample inlet pipeline 240, and is used to detect the total amount of radioactive gas entering the adsorption component 100.

[0057] Specifically, the radioactive gas flowing in the pipeline 230 to be tested is introduced into the adsorption assembly 100 through the sampling pipeline to achieve the adsorption of the target nuclide in the radioactive gas. The gas flow meter 220 detects the total amount of radioactive gas delivered by the gas storage component 210. When the monitoring assembly 300 detects that the radioactive gas passing through the adsorption assembly 100 contains the target nuclide, the sampling of the sampling pipeline is stopped, and the total amount of radioactive gas recorded by the gas flow meter 220 is recorded. Among them, real-time sampling is performed in the pipeline 230 to be tested through the sampling pipeline 240, and the sampling pipeline 250 discharges the radioactive gas of the adsorbed target nuclide into the pipeline 230 to be tested again, and the sampling pipeline 250 discharges the radioactive gas at the second position to avoid affecting the radioactive gas in the sampling pipeline 240. It should be noted that the half-life of some target nuclides is short and the reserved detection time is short. If the detection is performed by means of the gas storage part 210, the target nuclides may have decayed completely during the transportation of the gas storage part 210, resulting in the undetectable content. Therefore, direct sampling and detection during the discharge of the target nuclides can make the detection accuracy of the target nuclides higher. Of course, the method of directly sampling the pipeline 230 to be tested that discharges radioactive gas is also applicable to the scenario where the half-life of the target nuclides is long.

[0058] Reference Figure 3As shown, in some specific embodiments of the present invention, the adsorption component 100 includes a shell 110 and a porous adsorption member 120, the shell 110 defines an adsorption chamber, the adsorption chamber has a first connection position and a second connection position, the shell 110 is connected to the sampling component 200 at the first connection position, and the shell 110 is connected to the monitoring component 300 or the detection component 500 at the second connection position, the porous adsorption member 120 is arranged in the adsorption chamber, and is arranged between the first connection position and the second connection position along the transport direction of the radioactive gas.

[0059] Among them, the shell 110 is made of stainless steel, and its specific shape and size can be selected according to needs. The porous adsorbent 120 includes granular materials and / or powder materials such as metal organic framework materials (MOF), non-metal organic framework materials (COF), zeolite, molecular sieves, activated carbon derivatives, etc. In this embodiment, the shell 110 is a hollow cylinder, and the granular materials or powder materials are sequentially filled into the shell 110 along the axial direction of the cylinder to form the porous adsorbent 120. The first connecting position and the second connecting position are respectively set at both ends of the shell 110 along the axial direction of the cylinder. The radioactive gas will pass through the porous adsorbent 120 along the axial direction of the cylinder and fully contact with the porous adsorbent 120, so that the target nuclide is embedded in the pores of the porous adsorbent 120.

[0060] Reference Figure 4 As shown, in some other specific embodiments of the present invention, the adsorption component 100 includes a shell 110 and a separation membrane 130, the shell 110 defines a first cavity 111 and a second cavity 112, the first cavity 111 is connected to the sampling component 200, the second cavity 112 is connected to the monitoring component 300 or the detection component 500, and 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.

[0061] Among them, the 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 by materials such as MOF and COF. In this embodiment, the shell 110 is also in the shape of a hollow cylinder, and the separation membrane 130 is arranged in the middle of the axial direction of the hollow cylinder, and the hollow cylinder is divided into a first cavity 111 and a second cavity 112 that are basically the same. Of course, the position of the separation membrane 130 can also be arranged as needed, for example, it is arranged at one-third of the axial position of the hollow circumference, and the hollow cylinder is divided into a first cavity 111 with a size of one-third and a second cavity 112 with a size of two-thirds, or a second cavity 112 with a size of one-third and a first cavity 111 with a size of two-thirds.

[0062] In addition, the desorption component 400 heats the porous adsorbent material, which can be specifically heating the outer shell 110 to heat the porous adsorbent 120 or the separation membrane 130 at intervals, or the heating part of the desorption component 400 is arranged in 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 a certain period of activation, the activation component can remove impurities and moisture in the porous adsorbent 120 or the separation membrane 130 to improve the adsorption effect.

[0063] Reference Figure 4 As shown, in some specific embodiments of the present invention, the adsorption assembly 100 includes a housing 110 and a separation membrane 130 , and the pressure in the second cavity 112 is lower than the pressure in the first cavity 111 .

[0064] 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 continues to move toward the second cavity 112, and the target nuclide continues to embed into the separation membrane 130, thereby improving the embedding efficiency of the target nuclide.

[0065] In this embodiment, the radioactive gas detection device further includes a back pressure valve 140, which is disposed between the adsorption assembly 100 and the monitoring assembly 300. The back pressure valve 140 is configured to adjust the pressure in the second cavity 112 to be lower than the pressure in the first cavity 111 when the pressure in the second cavity 112 is a preset pressure. Specifically, after a period of time of radioactive gas being introduced, the first cavity 111 and the second cavity 112 are both filled with radioactive gas, and the pressure between the first cavity 111 and the second cavity 112 is substantially the same and continues to increase with the introduction of gas, but the pressure in the first cavity 111 and the second cavity 112 is substantially the same, resulting in a reduced efficiency of embedding the target nuclide into the separation membrane 130. Therefore, when the pressure in the second cavity 112 increases to a preset pressure, the preset pressure is greater than the external pressure, so that the back pressure valve 140 is opened under the action of the pressure difference, and the radioactive gas in the second cavity 112 will be discharged, causing the pressure in the second cavity 112 to decrease and be lower than the pressure in the first cavity 111, thereby improving the efficiency of embedding the target nuclide into the separation membrane 130.

[0066] The second embodiment of the present invention provides a detection method, the steps of which include: S1: transporting radioactive gas through the adsorption assembly 100, and the adsorption assembly 100 adsorbs target nuclides in the radioactive gas; 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 the delivered radioactive gas X1 and the content of the target nuclide X2 adsorbed by the adsorption component 100 are obtained; S3: Obtain the concentration of the target nuclide based on the total amount of radioactive gas X1 and the target nuclide content X2.

[0067] Specifically, when the 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 set at the position before the radioactive gas enters the adsorption component 100, and the gas flow meter 220 counts the passing radioactive gas 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 X2 of the target nuclide; the target nuclide content X2 is divided by the total amount X1 of the radioactive gas to obtain the concentration of the target nuclide in the radioactive gas to determine whether the concentration of the target nuclide meets the emission requirements.

[0068] It is worth understanding that by monitoring whether the radioactive gas passing through the adsorption component 100 contains the target nuclide through the monitoring component 300, it is determined whether the adsorption component 100 has completed the adsorption. The adsorption component 100 is able to adsorb a sufficient amount of the target nuclide for detection. At the same time, fewer target nuclides pass through the monitoring component 300, and the detection accuracy and content accuracy of the target nuclides are higher, thereby improving the detection accuracy of the target nuclide concentration in the radioactive gas.

[0069] In some specific embodiments of the present invention, in S2, the target nuclide adsorbed by the adsorption component 100 is released by heating, and the target nuclide content X2 released by the adsorption component 100 is detected; wherein the heating temperature ranges from 80°C to 100°C.

[0070] It is worth understanding that by heating, the porous material in the adsorption assembly 100 undergoes thermal expansion, and the target nuclide is disengaged from the pores of the porous material, so that the target nuclide is separated from the porous material and detected. In this embodiment, the heating temperature is controlled at 80°C to 100°C, which can reduce energy consumption and save detection costs. The heating time is controlled at 1h to 2h. Of course, the specific time can be extended or shortened according to the amount of porous material.

[0071] The embodiments of the present invention are described in detail above with reference to the accompanying drawings, but the present invention is not limited to the above embodiments, and various changes can be made within the knowledge scope of ordinary technicians in the relevant technical field without departing from the purpose of the present invention.

Claims

1. A radioactive gas detection device, used for detecting radioactive gas containing target nuclides, characterized in that: include: An adsorption component capable of adsorbing target nuclides in the radioactive gas; A sampling component, connected to the adsorption component, and used to provide the radioactive gas to the adsorption component; A monitoring component, connected to the adsorption component, for monitoring the target nuclide in the radioactive gas after passing through the adsorption component; A desorption component, used to make the adsorption component release the adsorbed target nuclide; A detection component, connected to the adsorption component, for detecting the content of the target nuclide released by the adsorption component; A first control valve group, used for switching on and off 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; Wherein, 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 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 also 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 comprises: an equipment chamber, a detection chamber, a spacer membrane, a spacer plate and a detection member, the equipment chamber and the detection chamber are connected to each other through an incident window, and the detection chamber is connected to the adsorption assembly; the spacer membrane is arranged at the incident window; the spacer plate is arranged at the incident window and is located at a side of the spacer membrane away from the equipment chamber, and the spacer plate can close or open the incident window; the detection member is arranged in the equipment chamber; Wherein, the controller is configured to: when the transfer component transfers the target nuclide released from the adsorption component to the detection room, control the partition plate to close the incident window; after the adsorption component completes the transfer operation, control the partition plate to open the incident window, and control the detection component located in the equipment room to perform the detection operation.

4. The radioactive gas detection device according to claim 2, characterized in that: The detection assembly comprises: a detection chamber, a detection member, a working assembly and a working valve, wherein the detection chamber is connected to the adsorption assembly, the detection member is arranged in the detection chamber, the working assembly 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 connection and disconnection between the working assembly and the detection chamber; Wherein, the controller is configured to: when the transfer component performs the transfer operation or after the adsorption component completes the transfer operation, control the working valve to make the working component and the detection chamber in a connected state, control the working component to pass the working gas into the detection chamber, and control the detection component 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, and the transfer component is used to transport the purge gas that does not react with the target nuclide to the detection component to purge the target nuclide released by the adsorption component to the detection component; and / or, The transfer component includes a vacuum component and a second control valve group, the vacuum component is connected to the detection component, and the second control valve group is used to switch the connection between the detection component and the vacuum component and the connection between the detection component and the adsorption component; Wherein, the controller is configured as follows: when the transfer component performs a transfer operation, the second control valve group is controlled to make the detection component and the vacuum component in a connected state, and the detection component and the adsorption component in a disconnected state, and the vacuum component performs a vacuum operation; when a preset negative pressure is formed in the detection component, the second control valve group is controlled to make the detection component and the vacuum component in a disconnected state, and 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 component and a gas flow meter. The gas storage component is connected to the adsorption component and is used to store the radioactive gas. The gas flow meter is arranged in a pipeline between the gas storage component and the adsorption component and is used to detect the total amount of the radioactive gas entering the adsorption component. or, The sampling component includes a pipeline to be tested, a sample inlet pipeline, a sample outlet pipeline and a gas flow meter. The pipeline to be tested is used to discharge the radioactive gas and has a first position and a second position distributed in sequence along the discharge direction. The sample inlet pipeline connects the pipeline to be tested and the adsorption component at the first position, and the sample outlet pipeline connects the pipeline to be tested and the monitoring component at the second position. The gas flow meter is arranged on the sample inlet pipeline and is used to detect the total amount of the radioactive gas entering the adsorption component.

7. The radioactive gas detection device according to claim 1, characterized in that: The adsorption assembly comprises a shell and a porous adsorption member, the shell defines an adsorption chamber, the adsorption chamber has a first communication position and a second communication position, the shell is connected to the sampling assembly at the first communication position, the shell is connected to the monitoring assembly or the detection assembly at the second communication position, the porous adsorption member is arranged in the adsorption chamber, and is arranged between the first communication position and the second communication position along the transport direction of the radioactive gas; or, The adsorption component includes an outer shell and a separation membrane, the outer shell defines a first cavity and a second cavity, the first cavity is connected to the sampling component, the second cavity is connected to the monitoring component or the detection component, and the separation membrane is arranged 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: transporting radioactive gas through an adsorption component, wherein the adsorption component adsorbs target nuclides 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 X1 of the delivered radioactive gas and the content X2 of the target nuclide adsorbed by the adsorption component are obtained; S3: Obtaining the concentration of the target nuclide according to the total amount of radioactive gas X1 and the target nuclide content 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; Among them, the heating temperature range is 80℃~100℃.

Images