Radioactive waste liquid detection system
By setting up a shielded room and an independent storage tank and pipeline structure in the radioactive waste liquid detection system, non-contact detection of the waste liquid is achieved, solving the problems of reduced accuracy and poor maintenance economy in the existing technology, and improving the stability and maintenance efficiency of the system.
Patent Information
- Application Number
- CN202520110366.8
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2025-01-17
- Publication Date
- 2026-03-13
- Estimated Expiration
- 2035-01-17
AI Technical Summary
Existing radioactive waste detection devices are prone to reduced accuracy and increased failure rate during long-term use, and their maintenance is not economical.
A radioactive waste liquid detection system was designed, including a shielded room, a storage tank, a detection device, an inlet pipe, and a drain pipe. The detection device is located outside the storage tank, and non-contact detection of the waste liquid is achieved through the inlet and drain pipes. Shielding material is installed inside the storage tank to avoid external radiation interference.
It improves the operational stability of the testing device, avoids reduced accuracy and increased failure rate, has high maintenance economy, and allows for individual disassembly and cleaning of components, ensuring the accuracy and consistency of testing.
Smart Images
Figure CN223992965U_ABST
Abstract
Description
Technical Field
[0001] This application relates to the field of nuclear radiation monitoring technology, and in particular to a radioactive waste liquid detection system. Background Technology
[0002] To ensure that the impact of waste liquid discharged from nuclear power plants on the environment and the public is minimized, and to continuously monitor the radioactivity concentration of water bodies surrounding nuclear power plants, it is necessary to monitor the radioactivity concentration of waste liquid discharged from nuclear power plants so that the radioactivity concentration of waste liquid meets the requirements.
[0003] In related technologies, there are generally two methods for monitoring radioactive waste liquid. The first method involves installing a detection device on the discharge pipeline of a nuclear power plant to directly detect and analyze the concentration of radionuclides in the raw waste liquid. The second method involves placing an immersion detection device directly in the water body to be tested, which is then submerged in the water to continuously monitor the radioactivity concentration. Both methods require immersing the detection device in water, which can easily lead to reduced accuracy and increased failure rate with long-term use. Utility Model Content
[0004] This application provides a radioactive waste liquid detection system to solve or alleviate one or more technical problems in the prior art.
[0005] As one aspect of this application, this application provides a radioactive waste liquid detection system, including: a shielded room; a storage tank disposed within the shielded room, the storage tank having an inlet and a drain hole spaced apart; a detection device disposed within the shielded room, located outside the storage tank, the detection device being used to detect the radioactive concentration of the waste liquid to be tested within the storage tank; an inlet pipe, the input end of which is connected to a container for the waste liquid to be tested, and the output end of which is connected to the inlet hole; and a drain pipe, the input end of which is connected to the drain hole, and the output end of which is connected to the container for the waste liquid to be tested.
[0006] In one embodiment, the reservoir defines a detection recess with a top opening, and at least a portion of the detection device is located within the detection recess.
[0007] In one embodiment, the detection device includes a scintillator crystal, a photomultiplier tube, and a data processing unit. The scintillator crystal is disposed in a detection groove and is used to detect the radiation signal of the waste liquid to be tested in the storage tank and emit light. The photomultiplier tube and the data processing unit are both located outside the detection groove. The photomultiplier tube is connected to the scintillator crystal and is used to convert scintillating photons into analog electrical signals. The input terminal of the data processing unit is connected to the output terminal of the photomultiplier tube.
[0008] In one embodiment, when the amount of waste liquid to be tested in the storage tank reaches a preset threshold, the scintillator crystal is located at the spatial center of the waste liquid to be tested.
[0009] In one embodiment, the shielding chamber includes a shielding body and a shielding top cover. The shielding top cover is connected to the top of the shielding body, the detection device is connected to the shielding body, the liquid inlet pipe passes through the shielding body and is connected to the liquid inlet hole, and the liquid outlet pipe passes through the shielding body and is connected to the liquid outlet hole.
[0010] In one embodiment, the shielding top cover includes a first cover body and a second cover body arranged along the axial direction. One of the first cover body and the second cover body is provided with a top cover mating protrusion, and the other of the first cover body and the second cover body is provided with a top cover mating groove, and the top cover mating protrusion is mated in the top cover mating groove; and / or, the shielding body includes a plurality of shielding structures arranged sequentially along the axial direction. Two adjacent shielding structures are respectively a first shielding structure and a second shielding structure. One of the first shielding structure and the second shielding structure is provided with a main body mating protrusion, and the other of the first shielding structure and the second shielding structure is provided with a main body mating groove, and the main body mating protrusion is mated in the main body mating groove.
[0011] In one embodiment, the shielding top cover includes a first cover and a second cover arranged along the axial direction. The bottom of the first cover is provided with a first wire-passing groove, and the top of the second cover is provided with a second wire-passing groove. The first wire-passing groove and the second wire-passing groove together form a wire-passing hole; and / or, the shielding body includes a plurality of shielding structures arranged sequentially along the axial direction, and the detection device is connected to the topmost shielding structure.
[0012] In one embodiment, the liquid storage tank includes an acrylic glass layer, a copper layer, and a cadmium layer, which are stacked sequentially in the direction of proximity to the shielded chamber; and / or, the shielded chamber includes a first steel layer, a second steel layer, and a lead layer, with the lead layer disposed between the first steel layer and the second steel layer.
[0013] In one embodiment, an inlet valve is provided on the inlet pipe and a drain valve is provided on the drain pipe; the radioactive waste liquid detection system further includes: a level gauge, installed in a shielded room, used to detect the liquid level of the waste liquid to be tested in the storage tank; and a control unit, installed outside the shielded room and connected to the inlet valve, the drain valve and the level gauge. When the liquid level of the waste liquid to be tested in the storage tank reaches a preset height, the control unit controls the opening of the inlet valve and the opening of the drain valve to make the inlet rate and the drain rate of the storage tank consistent.
[0014] In one embodiment, the control unit is also connected to the detection device. When the detection device detects that the radioactivity concentration of the waste liquid to be tested in the storage tank reaches a preset concentration threshold, the control unit controls the inlet valve and the outlet valve to close and issues an alarm signal.
[0015] The embodiments of this application adopt the above-mentioned technical solution. On the one hand, the detection device has no direct contact with the waste liquid to be tested in the storage tank, and is protected from light, wind, and sand, placing it in an optimal working environment. This avoids problems such as reduced accuracy and increased failure rate, effectively improving the operational stability of the radioactive waste liquid detection system. On the other hand, the storage tank, inlet pipe, and outlet pipe are all independent components. In case of contamination or equipment failure, the storage tank, inlet pipe, and outlet pipe can be disassembled separately for cleaning, disinfection, and maintenance, resulting in high maintenance economics.
[0016] The above overview is for illustrative purposes only and is not intended to be limiting in any way. In addition to the illustrative aspects, embodiments, and features described above, further aspects, embodiments, and features of this application will become readily apparent from the accompanying drawings and the following detailed description. Attached Figure Description
[0017] In the accompanying drawings, unless otherwise specified, the same reference numerals throughout the various drawings denote the same or similar parts or elements. These drawings are not necessarily drawn to scale. It should be understood that these drawings depict only some embodiments disclosed in this application and should not be construed as limiting the scope of this application.
[0018] Figure 1 A schematic diagram of the structure of the first radioactive waste liquid detection system in the related technology is shown;
[0019] Figure 2 A schematic diagram of the structure of the second type of radioactive waste liquid detection system in the related technology is shown;
[0020] Figure 3 A schematic diagram of the structure of a radioactive waste liquid detection system according to an embodiment of this application is shown;
[0021] Figure 4 A schematic diagram of the structure of a shielded room according to an embodiment of this application is shown;
[0022] Figure 5 Show along Figure 4 Cross-sectional view of line AA in the middle. Detailed Implementation
[0023] In the following description, only certain exemplary embodiments are briefly described. As those skilled in the art will recognize, the described embodiments can be modified in various ways without departing from the spirit or scope of this application. Therefore, the drawings and description are considered to be exemplary in nature and not restrictive.
[0024] Figure 1 A schematic diagram of the structure of the first radioactive waste detection system in the related technology is shown. For example... Figure 1As shown, the radioactive waste detection system includes a main body, an underwater section located at the bottom of the main body, and an above-water section located at the top of the main body. The underwater section includes a low-background lead chamber 7 and a detector 9 placed inside the low-background lead chamber 7. The above-water section includes a solar power panel 11 and a host computer 12. This technical solution directly places the low-background lead chamber 7 and the detector 9 in the water area to be tested. Long-term water erosion will lead to problems such as reduced detection accuracy and increased failure rate. In addition, this technical solution has poor maintenance economy. Once the system is contaminated, decontamination is difficult, and a new device must be redeployed.
[0025] Figure 2 A schematic diagram of the structure of a second type of radioactive waste detection system in the related technology is shown. For example... Figure 2 As shown, the radioactive waste liquid detection system includes a radiation detector 1 installed outside the tested pipe section 2 of the radioactive waste liquid discharge pipe to detect the radioactive waste liquid flowing through the pipe. This technical solution directly deploys the detection device on the radioactive waste liquid discharge pipeline. If the equipment malfunctions or becomes contaminated, the entire pipeline needs to be throttled, and the detection device removed for repair or a new device needs to be redeployed. Furthermore, this solution also requires immersing the detector in water, which can lead to reduced accuracy and increased failure rate with prolonged use.
[0026] To address the aforementioned issues, this application provides a radioactive waste liquid detection system 10. Figure 3 A schematic diagram of the structure of a radioactive waste detection system 10 according to an embodiment of this application is shown. Figure 3 As shown, the radioactive waste liquid detection system 10 includes a shielded chamber 100, a storage tank 200, a detection device 300, an inlet pipe 400, and an outlet pipe 500.
[0027] Figure 4 A schematic diagram of the structure of a shielded chamber 100 according to an embodiment of this application is shown; Figure 5 Show along Figure 4 Cross-sectional view of line AA. Specifically, refer to... Figures 3-5 A storage tank 200 is located inside a shielded room 100. The storage tank 200 has an inlet port 210 and a drain port, which are spaced apart. A detection device 300 is located inside the shielded room 100, outside the storage tank 200. The detection device 300 is used to detect the radioactivity concentration of the waste liquid to be tested inside the storage tank 200. The input end of the inlet pipe 400 is connected to the waste liquid container 20, and the output end of the inlet pipe 400 is connected to the inlet port 210. The input end of the drain pipe 500 is connected to the drain port, and the output end of the drain pipe 500 is connected to the waste liquid container 20.
[0028] For example, a storage chamber can be defined within the storage tank 200, and the waste liquid to be tested can enter the storage chamber of the storage tank 200 through the inlet pipe 400. The detection device 300 is located outside the storage chamber, so the detection device 300 has no direct contact with the waste liquid to be tested inside the storage chamber.
[0029] For example, initially, the inlet pipe 400 can be opened, and the outlet pipe 500 can be closed. The waste liquid to be tested in the waste liquid container 20 can enter the storage tank 200 through the inlet pipe 400. When the amount of waste liquid to be tested in the storage tank 200 reaches a preset threshold, both the inlet pipe 400 and the outlet pipe 500 can be opened, and the inlet and outlet rates of the storage tank 200 can be controlled to be consistent. This ensures that there is sufficient waste liquid to be tested in the storage tank 200 for continuous detection by the detection device 300. When the detection device 300 detects that the radioactivity concentration of the waste liquid to be tested in the storage tank 200 reaches a preset concentration threshold, both the inlet pipe 400 and the outlet pipe 500 can be closed. Then, the waste liquid to be tested in the storage tank 200 is further tested. If the radioactivity concentration of the waste liquid in the storage tank 200 is confirmed to reach the preset concentration threshold, the drain pipe 500 can be opened while the inlet pipe 400 is closed. This allows the waste liquid in the storage tank 200 to re-enter the waste liquid container 20 through the drain pipe 500 for a new round of purification. Contaminated components such as the storage tank 200, inlet pipe 400, and drain pipe 500 are replaced promptly. After the contaminated components are replaced, the environmental background is checked to see if it has returned to its initial value. Once the environmental background is confirmed to have returned to its initial value, the next round of radioactivity concentration testing can be performed.
[0030] For example, the shielding chamber 100 may include shielding material (e.g., lead) with effective radioactive shielding performance, thereby blocking external radiation from interfering with the detection results, ensuring a stable detection environment, and reducing background radiation and environmental noise, thereby improving the sensitivity, accuracy and efficiency of the detection, and ensuring that the detected signal comes from the waste liquid to be tested in the storage tank 200.
[0031] Optionally, the volume of the liquid storage tank 200 can be 4L to 6L (including the endpoint value), for example, 5L, but not limited to this. The inlet pipe 400 and the outlet pipe 500 can be arranged appropriately according to the actual site conditions. The inlet hole 210 and the outlet hole can be G1 / 2 standard internal thread holes, but are not limited to this.
[0032] According to the embodiment of the radioactive waste liquid detection system 10 of this application, by setting up a shielded chamber 100, a storage tank 200, a detection device 300 set in the shielded chamber 100, and an inlet pipe 400 and an outlet pipe 500 connected to the storage tank 200, and by positioning the detection device 300 outside the storage tank 200, the detection device 300 has no direct contact with the waste liquid to be tested in the storage tank 200, and is protected from light, wind, and sand, thus being in an optimal working environment. This avoids problems such as reduced accuracy and increased failure rate, effectively improving the operational stability of the radioactive waste liquid detection system 10. On the other hand, the storage tank 200, the inlet pipe 400, and the outlet pipe 500 are all independent components. In the event of contamination or equipment failure, the storage tank 200, the inlet pipe 400, and the outlet pipe 500 can be disassembled individually for cleaning, disinfection, and maintenance, resulting in high maintenance economics.
[0033] In one implementation, reference Figure 5 The reservoir 200 defines a detection recess 220 with a top opening, and at least a portion of the detection device 300 is located within the detection recess 220. For example, in Figure 5 In the example, the storage tank 200 is formed into a U-shaped structure. A detection groove 220 is defined by the outer surface of the storage tank 200. The detection groove 220 includes side walls and a bottom wall. The side walls of the detection groove 220 are disposed opposite to the side surface of the storage tank 200. The bottom wall of the detection groove 220 is disposed opposite to the bottom surface of the storage tank 200. The top opening of the detection groove 220 allows communication between the detection groove 220 and the internal space of the shielding chamber 100. The detection device 300 extends from the top of the detection groove 220 into the detection groove 220 to detect the radioactivity concentration of the waste liquid to be tested within the storage tank 200.
[0034] In this embodiment, by setting a detection groove 220 and having at least a portion of the detection device 300 located within the detection groove 220, the maximum distance between the detection device 300 and the waste liquid to be tested in the storage tank 200 can be shortened, ensuring the accuracy and consistency of the detection.
[0035] In one embodiment, the detection device 300 may include a scintillator crystal, a photomultiplier tube, and a data processing unit. The scintillator crystal is disposed in the detection groove 220 and is used to detect the radiation signal of the waste liquid to be tested in the storage tank 200 and emit light. The photomultiplier tube and the data processing unit are both located outside the detection groove 220. The photomultiplier tube is connected to the scintillator crystal and is used to convert scintillating photons into analog electrical signals. The input terminal of the data processing unit is connected to the output terminal of the photomultiplier tube.
[0036] For example, the data processing unit may include a preamplifier, an analog-to-digital converter (ADC), a digital processor, and a controller. The input of the preamplifier is connected to the output of the photomultiplier tube, and the preamplifier amplifies the analog electrical signal. The input of the ADC is connected to the output of the preamplifier, and the ADC converts the analog electrical signal into a digital electrical signal. The input of the digital processor is connected to the output of the ADC, and the digital processor processes the digital electrical signal and outputs energy spectrum data. The input of the controller is connected to the output of the digital processor, and the controller performs energy spectrum measurement and analysis based on the energy spectrum data to determine the detection result of the radioactivity concentration of the waste liquid to be tested.
[0037] For example, the digital processor can be a Field-Programmable Gate Array (FPGA), which may include logic modules, flip-flops, programmable interconnect networks, digital signal processing modules, and storage modules (not shown in the figure). The logic modules can be used to classify and process received digital electrical signals, and perform various logical operations, such as determining the amplitude and timing characteristics of the digital electrical signals. The flip-flops can store the processed pulse amplitude information, ensuring that the energy spectrum data is transmitted to the controller at the appropriate clock cycle. The programmable interconnect network allows users to flexibly adjust the processing path of the digital electrical signals, enabling data to be processed according to a specific timing and sequence to meet different experimental needs. The digital signal processing module can be used for high-precision signal analysis, such as advanced processing of digital electrical signals including filtering, integration, and differentiation, helping to extract key information such as pulse amplitude more accurately. The storage module can be used to store pulse data, such as intermediate processing results and pulse counts, and can also be used to buffer acquired data for subsequent processing or transmission.
[0038] Optionally, the scintillator crystal can be a 3-inch × 3-inch NaI scintillator, but is not limited thereto.
[0039] In this embodiment, by placing the scintillator crystal inside the detection groove 220, and having the photomultiplier tube and data processing unit located outside the detection groove 220, the maximum distance between the scintillator crystal and the waste liquid to be tested in the storage tank 200 is small. The scintillator crystal can effectively detect the radiation signal of the waste liquid to be tested in the storage tank 200 and emit light, thereby further ensuring the accuracy of the detection.
[0040] In one embodiment, when the amount of waste liquid to be tested in the storage tank 200 reaches a preset threshold, the scintillator crystal is located at the spatial center of the waste liquid to be tested. This setting can further ensure the consistency of the detection.
[0041] In one implementation, such as Figures 3-5As shown, the shielded chamber 100 may include a shielding body 110 and a shielding top cover 120. The shielding top cover 120 is connected to the top of the shielding body 110. The detection device 300 is connected to the shielding body 110. The liquid inlet pipe 400 passes through the shielding body 110 and is connected to the liquid inlet hole 210. The liquid outlet pipe 500 passes through the shielding body 110 and is connected to the liquid outlet hole. Thus, the shielding body 110 can support the installation and fixation of the detection device 300, the liquid inlet pipe 400, and the liquid outlet pipe 500.
[0042] For example, the projected area of the shielding top cover 120 on the horizontal plane can be smaller than the projected area of the shielding body 110 on the horizontal plane. The shielding body 110 may be provided with an inlet pipe opening 112 and a drain pipe opening 113, arranged at intervals. The inlet pipe 400 can pass through the inlet pipe opening 112 and communicate with the inlet port 210 of the storage tank 200. The drain pipe 500 can pass through the drain pipe opening 113 and communicate with the drain port of the storage tank 200. The data processing unit of the detection device 300 can be connected to the shielding body 110.
[0043] In one embodiment, the shielding top cover 120 may include a first cover body 121 and a second cover body 122 arranged axially. One of the first cover body 121 and the second cover body 122 is provided with a top cover mating protrusion 1221, and the other of the first cover body 121 and the second cover body 122 is provided with a top cover mating groove. That is, the first cover body 121 may be provided with the top cover mating protrusion 1221, and the second cover body 122 may be provided with the top cover mating groove; alternatively, the second cover body 122 may be provided with the top cover mating protrusion 1221, and the first cover body 121 may be provided with the top cover mating groove. The top cover mating protrusion 1221 engages within the top cover mating groove.
[0044] For example, in Figure 5 In the example, the first cover 121 and the second cover 122 are arranged axially along the first cover 121, with the first cover 121 located on top of the second cover 122. A top cover mating groove is located at the end of the first cover 121 facing the second cover 122, and a top cover mating protrusion 1221 is located at the end of the second cover 122 facing the first cover 121. The width of the top cover mating protrusion 1221 gradually increases along the direction toward the shielding body 110. The shape of the top cover mating groove matches the shape of the top cover mating protrusion 1221. Optionally, the first cover 121 and the second cover 122 can also be connected and fixed by a fixing rod to ensure the stability of the shielding top cover 120.
[0045] In this embodiment, by setting the first cover 121 and the second cover 122, the shielding top cover 120 can be assembled and deployed on-site without the aid of mechanical equipment. By having the top cover mating protrusion 1221 fit into the top cover mating groove, the relative movement of the first cover 121 and the second cover 122 can be limited, ensuring a stable fit between the first cover 121 and the second cover 122 and guaranteeing all-round shielding against external background radiation.
[0046] In one implementation, such as Figure 4 and Figure 5 As shown, the shielding body 110 may include a plurality of shielding structures 111 arranged sequentially along the axial direction. Two adjacent shielding structures 111 are respectively a first shielding structure and a second shielding structure. One of the first and second shielding structures is provided with a main body mating protrusion 1111, and the other of the first and second shielding structures is provided with a main body mating groove. The main body mating protrusion 1111 fits into the main body mating groove. In the description of this application, "a plurality of" means two or more.
[0047] For example, Figure 4 and Figure 5 Eleven shielding structures 111 are shown. For ease of description, the eleven shielding structures 111 are referred to from top to bottom as shielding structure one, shielding structure two, ... shielding structure eleven. Shielding structure one has a main body mating groove at its bottom. Shielding structure two has a main body mating protrusion 1111 at its top to mate with the main body mating groove at the bottom of shielding structure one, and a main body mating groove at its bottom. Similarly, shielding structures three through ten all have main body mating protrusions 1111 at their tops and main body mating grooves at their bottoms. Shielding structure eleven has a main body mating protrusion 1111 at its top to mate with the main body mating groove at the bottom of shielding structure ten. The width of the main body mating protrusion 1111 gradually increases in the direction away from the shielding top cover 120. The shape of the main body mating groove matches the shape of the main body mating protrusion 1111. Optionally, adjacent shielding structures 111 can also be connected and fixed by a fixing rod to ensure the stability of the shielding body 110.
[0048] For example, the liquid storage tank 200 can be placed on the shielding structure ten and fixed to the shielding structure ten by a connecting rod. When installing or removing the liquid storage tank 200, the installation and removal of the liquid storage tank 200 can be achieved by removing the first cover 121, the second cover 122, the first shielding structure, and the second shielding structure. The inlet pipe opening 112 can be provided in the third shielding structure, and the outlet pipe opening 113 can be provided in the ninth shielding structure.
[0049] In this embodiment, by setting multiple shielding structures 111, the shielding body 110 can be assembled and deployed on-site without the aid of mechanical equipment. By having the main body mating protrusion 1111 fit into the main body mating groove, the relative movement of two adjacent shielding structures 111 can be limited, ensuring stable mating of the two adjacent shielding structures 111 and ensuring all-round shielding against external background radiation.
[0050] Figure 4 and Figure 5 Eleven shielding structures 111 are shown for illustrative purposes, but those skilled in the art, after reading the technical solution of this application, will obviously understand that the solution can be applied to other numbers of shielding structures 111, which would also fall within the protection scope of this application.
[0051] In one implementation, reference Figure 5 The shielding top cover 120 may include a first cover 121 and a second cover 122 arranged along the axial direction. The bottom of the first cover 121 is provided with a first wire-passing groove 1211, and the top of the second cover 122 is provided with a second wire-passing groove 1222. The first wire-passing groove 1211 and the second wire-passing groove 1222 together form a wire-passing hole 123. In this way, the wire-passing hole 123 can be used to lead out the connecting cable of the detection device 300.
[0052] In one implementation, such as Figure 5 As shown, the shielding body 110 includes a plurality of shielding structures 111 arranged sequentially along the axial direction, and the detection device 300 is connected to the topmost shielding structure 111. For example, in Figure 5 In the example, the detection device 300 can be connected and fixed to the shielding structure. When it is necessary to install or remove the detection device 300, it is only necessary to remove the first cover 121 and the second cover 122.
[0053] Therefore, by connecting the detection device 300 to the topmost shielding structure 111, the detection device 300 can be installed and removed by disassembling the shielding top cover 120. The structure is simple and the operation is convenient.
[0054] In one embodiment, the storage tank 200 may include an acrylic glass layer, a copper layer, and a cadmium layer, which are stacked sequentially in the direction approaching the shielding chamber 100. Exemplarily, after the waste liquid to be tested in the waste liquid receiving pool 20 enters the storage tank 200 through the inlet pipe 400, the acrylic glass layer is in contact with the waste liquid. The copper layer is located between the acrylic glass layer and the cadmium layer. Optionally, the thickness of the acrylic glass layer can be 7mm to 9mm (including endpoints), for example, 8mm. The thickness of the copper layer can be 0.5mm to 1.5mm (including endpoints), for example, 1mm. The thickness of the cadmium layer can be 0.5mm to 1.5mm (including endpoints), for example, 1mm.
[0055] In this embodiment, by sequentially stacking an organic glass layer, a copper layer, and a cadmium layer in the direction close to the shielding chamber 100, fast neutrons that may be present can be absorbed and slowed down, thus preventing neutrons from reacting with unknown substances in the waste liquid and releasing gamma rays, which would affect the detection accuracy.
[0056] In one embodiment, the shielded chamber 100 may include a first steel layer, a second steel layer, and a lead layer, with the lead layer disposed between the first and second steel layers. Exemplarily, when the shielded chamber 100 includes a shielding body 110 and a shielding top cover 120 connected to the top of the shielding body 110, and the shielding top cover 120 includes a first cover 121 and a second cover 122 arranged axially, and the shielding body 110 includes a plurality of shielding structures 111 arranged sequentially axially, the first cover 121, the second cover 122, and each shielding structure 111 may each include a first steel layer, a second steel layer, and a lead layer disposed between the first and second steel layers. The first steel layer, the lead layer, and the second steel layer are arranged sequentially in the radial direction. Optionally, the thickness of the first steel layer may be 4mm to 6mm (including endpoint values), for example, 5mm. The thickness of the second steel layer may be 4mm to 6mm (including endpoint values), for example, 5mm. The thickness of the lead layer may be 75mm to 85mm (including endpoint values), for example, 80mm.
[0057] In this embodiment, by setting up a first steel layer, a second steel layer, and a lead layer, the shielded chamber 100 has an extremely low measurement background and high detection accuracy. The input waste liquid to be tested does not require pretreatment such as sedimentation or ashing; it can be directly input into the storage tank 200 for real-time detection.
[0058] In one implementation, such as Figures 3-5As shown, an inlet valve 410 can be installed on the inlet pipe 400, and a drain valve 510 can be installed on the drain pipe 500. The radioactive waste liquid detection system 10 may also include a level gauge 600 and a control unit 700. The level gauge 600 is installed inside the shielded chamber 100 and is used to detect the liquid level of the waste liquid to be tested in the storage tank 200. The control unit 700 is installed outside the shielded chamber 100 and is connected to the inlet valve 410, the drain valve 510, and the level gauge 600. When the liquid level of the waste liquid to be tested in the storage tank 200 reaches a preset height, the control unit 700 controls the opening of the inlet valve 410 and the drain valve 510 to make the inlet rate and the drain rate of the storage tank 200 consistent, thereby ensuring that there is sufficient waste liquid to be tested in the storage tank 200 for continuous detection by the detection device 300.
[0059] For example, firstly, the control unit 700 controls the inlet valve 410 to open, so that the inlet pipe 400 is in an open state, and controls the drain valve 510 to close, so that the drain pipe 500 is in a closed state. The waste liquid to be tested in the waste liquid container 20 can enter the storage tank 200 through the inlet pipe 400. When the liquid level of the waste liquid to be tested in the storage tank 200 reaches a preset height, and it is confirmed that the amount of waste liquid to be tested in the storage tank 200 reaches a preset threshold, the control unit 700 controls both the inlet valve 410 and the drain valve 510 to open, so that both the inlet pipe 400 and the drain pipe 500 are in an open state, and controls the opening degree of the inlet valve 410 and the drain valve 510 to make the inlet rate and the drain rate of the storage tank 200 consistent.
[0060] In one embodiment, the control unit 700 is also connected to the detection device 300. When the detection device 300 detects that the radioactivity concentration of the waste liquid to be tested in the storage tank 200 reaches a preset concentration threshold, the control unit 700 controls the inlet valve 410 and the outlet valve 510 to close and issues an alarm signal. In this way, an alarm can be triggered in real time when the radioactivity concentration of the waste liquid to be tested reaches the preset concentration threshold, realizing unattended detection.
[0061] For example, combined Figure 3 The control unit 700 may include a host computer 710 and a host computer 720. The host computer 710 can be connected to the detection device 300 via a connecting cable. The host computer 710 can be installed and fixed outside the shielded room 100 for displaying equipment status and issuing alarm signals. Independent setup of the host computer 710 and the detection device 300 facilitates deployment in various complex environments. The host computer 710 can be installed in a safe area easily accessible to operators for observation, without affecting the deployment of the detection device 300. The host computer 710 can be connected to the host computer 720 via a communication line. The host computer 720 is used to set equipment parameters and read equipment information. The host computer 720 can be installed in the area where the operator is located, allowing remote control of the detection of radioactivity concentration in the waste liquid under test.
[0062] For example, when the liquid level of the waste liquid to be tested in the storage tank 200 reaches a preset height, and the amount of waste liquid to be tested in the storage tank 200 is confirmed to have reached a preset threshold, the host computer 720 controls the detection device 300 to start detection and sets the corresponding alarm threshold parameter, i.e., the preset concentration threshold. Then, the opening of the inlet valve 410 and the outlet valve 510 is adjusted to ensure that the inlet and outlet rates of the storage tank 200 are consistent, guaranteeing that there is sufficient waste liquid to be tested in the storage tank 200 for continuous detection by the detection device 300. When the detection device 300 detects that the radioactivity concentration of the waste liquid to be tested in the storage tank 200 has reached the preset concentration threshold, the host computer 710 controls both the inlet valve 410 and the outlet valve 510 to close and continuously issues an alarm signal. The radioactivity concentration of the waste liquid to be tested can be displayed on the host computer 720. Further testing of the waste liquid in the storage tank 200 is conducted. If the radioactivity concentration of the waste liquid in the storage tank 200 is confirmed to reach the preset concentration threshold, the pump on the drain pipe 500 can be operated via the host computer 720 to allow the waste liquid in the storage tank 200 to re-enter the waste liquid container 20 for a new round of purification. Contaminated components such as the storage tank 200, inlet pipe 400, and drain pipe 500 are promptly replaced. After the contaminated components are replaced, the environmental background is checked to see if it has returned to its initial value. Once the environmental background is confirmed to have returned to its initial value, the next round of radioactivity concentration testing can be performed.
[0063] In one embodiment, the weight of the shielded chamber 100, the liquid storage tank 200, the detection device 300, the liquid inlet pipe 400, and the liquid outlet pipe 500 can each be less than 60 kg, which allows for single-person operation and deployment, making operation more convenient.
[0064] Other components of the radioactive waste liquid detection system 10 in the above embodiments can be adopted from various technical solutions that are now and will be known to those skilled in the art, and will not be described in detail here.
[0065] In the description of this specification, it should be understood that the terms "center," "longitudinal," "transverse," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used 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. Therefore, they should not be construed as limitations on this application.
[0066] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Therefore, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature.
[0067] In this application, unless otherwise expressly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection, an electrical connection, or a communication connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. Those skilled in the art can understand the specific meaning of the above terms in this application according to the specific circumstances.
[0068] In this application, unless otherwise expressly specified and limited, "above" or "below" the second feature can include direct contact between the first and second features, or contact between the first and second features through another feature between them. Furthermore, "above," "over," and "on top" of the second feature includes the first feature being directly above or diagonally above the second feature, or simply indicates that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature includes the first feature being directly above or diagonally above the second feature, or simply indicates that the first feature is at a lower horizontal level than the second feature.
[0069] The foregoing disclosure provides many different implementations or examples for carrying out different structures of this application. To simplify the disclosure, specific examples of components and arrangements are described above. Of course, these are merely examples and are not intended to limit the scope of this application. Furthermore, reference numerals and / or letters may be repeated in different examples; such repetition is for simplification and clarity and does not in itself indicate a relationship between the various implementations and / or arrangements discussed.
[0070] The above description is merely a specific embodiment of this application, but the scope of protection of this application is not limited thereto. Any person skilled in the art can easily conceive of various variations or substitutions within the technical scope disclosed in this application, and these should all be included within the scope of protection of this application. Therefore, the scope of protection of this application should be determined by the scope of the claims.
[0071] Explanation of reference numerals in the attached figures:
[0072] 10: Radioactive waste liquid detection system; 100: Shielding room; 110: Shielding main body; 111: Shielding structure; 1111: Main body matching protrusion; 112: Inlet pipe opening; 113: Drain pipe opening; 120: Shielding top cover; 121: First cover; 1211: First wiring groove; 122: Second cover; 1221: Top cover matching protrusion; 1222: Second wiring groove; 123: Wiring hole; 200: Storage tank; 210: Inlet hole; 220: Detection groove; 300: Detection device; 400: Inlet pipe; 410: Inlet valve; 500: Drain pipe; 510: Drain valve; 600: Level gauge; 700: Control unit; 710: Main unit; 720: Host computer; 20: Waste liquid container to be tested.
Claims
1. A radioactive waste liquid detection system, characterized by, The application relates to a shielding chamber for detecting the radioactivity concentration of waste liquid. The shielding chamber comprises a shielding chamber body, a liquid storage tank arranged in the shielding chamber body, a liquid inlet hole and a liquid outlet hole arranged on the liquid storage tank, a detection device arranged in the shielding chamber body, the detection device being located outside the liquid storage tank and used for detecting the radioactivity concentration of waste liquid in the liquid storage tank, a liquid inlet pipeline, an input end of the liquid inlet pipeline being used for connecting a waste liquid containing pool, and an output end of the liquid inlet pipeline being connected to the liquid inlet hole, and a liquid outlet pipeline, an input end of the liquid outlet pipeline being connected to the liquid outlet hole, and an output end of the liquid outlet pipeline being used for connecting the waste liquid containing pool. The liquid storage tank defines a top-open detection groove, and at least part of the detection device is located in the detection groove. The detection device comprises a scintillator crystal, a photomultiplier tube and a data processing unit, the scintillator crystal is arranged in the detection groove and used for detecting a radiation signal of waste liquid in the liquid storage tank and emitting light, the photomultiplier tube and the data processing unit are both located outside the detection groove, the photomultiplier tube is connected to the scintillator crystal and used for converting scintillation photons into analog electric signals, and an input end of the data processing unit is connected to an output end of the photomultiplier tube. When the amount of waste liquid in the liquid storage tank reaches a preset threshold value, the scintillator crystal is located at the spatial position center of the waste liquid. The shielding chamber comprises a shielding chamber body and a shielding top cover, the shielding top cover is connected to the top of the shielding chamber body, the detection device is connected to the shielding chamber body, the liquid inlet pipeline penetrates through the shielding chamber body and is connected to the liquid inlet hole, and the liquid outlet pipeline penetrates through the shielding chamber body and is connected to the liquid outlet hole.
2. The radioactive waste liquid detection system according to claim 1, characterized by, The shielding top cover comprises a first cover body and a second cover body arranged in an axial direction, one of the first cover body and the second cover body is provided with a top cover matching protrusion, the other of the first cover body and the second cover body is provided with a top cover matching groove, and the top cover matching protrusion is matched in the top cover matching groove; and / or 3. The radioactive liquid waste detection system of claim 2, wherein, The shielding chamber body comprises a plurality of shielding structures arranged in sequence in an axial direction, two adjacent shielding structures are a first shielding structure and a second shielding structure respectively, one of the first shielding structure and the second shielding structure is provided with a body matching protrusion, the other of the first shielding structure and the second shielding structure is provided with a body matching groove, and the body matching protrusion is matched in the body matching groove.
4. The radioactive waste liquid detection system according to claim 3, wherein The shielding top cover comprises a first cover body and a second cover body arranged in an axial direction, the bottom of the first cover body is provided with a first threading groove, the top of the second cover body is provided with a second threading groove, and the first threading groove and the second threading groove jointly form a threading hole; and / or 5. The radioactive waste liquid detection system of claim 1, wherein, The shielding chamber body comprises a plurality of shielding structures arranged in sequence in an axial direction, and the detection device is connected to the topmost shielding structure.
6. The radioactive waste liquid detection system of claim 5, wherein, The liquid storage tank comprises an organic glass layer, a red copper layer and a cadmium layer, the organic glass layer, the red copper layer and the cadmium layer are sequentially stacked in a direction close to the shielding chamber body; and / or 7. The radioactive waste liquid detection system of claim 5, wherein, 8. The radioactive waste liquid detection system of claim 5, wherein, The shielding chamber comprises a first steel layer, a second steel layer and a lead layer, and the lead layer is arranged between the first steel layer and the second steel layer.
9. The radioactive liquid waste detection system of any one of claims 1-8, wherein, The liquid inlet pipeline is provided with a liquid inlet valve, and the liquid outlet pipeline is provided with a liquid outlet valve; the radioactive waste liquid detection system further comprises: a liquid level meter arranged in the shielding chamber and used for detecting the liquid level of the waste liquid to be detected in the liquid storage tank; a control unit arranged outside the shielding chamber and connected with the liquid inlet valve, the liquid outlet valve and the liquid level meter, and configured to control the opening degree of the liquid inlet valve and the opening degree of the liquid outlet valve to make the liquid inlet rate and the liquid outlet rate of the liquid storage tank consistent when the liquid level of the waste liquid to be detected in the liquid storage tank reaches a preset height.
10. The radioactive liquid waste detection system of claim 9, wherein, The control unit is further connected with the detection device, and configured to control the liquid inlet valve and the liquid outlet valve to be closed and send an alarm signal when the detection device detects that the radioactivity concentration of the waste liquid to be detected in the liquid storage tank reaches a preset concentration threshold.