Real-time monitoring system for gamma radioactivity of nuclear waste liquid

Abstract

The invention discloses a real-time monitoring system for gamma radioactivity of nuclear waste liquid. Comprising a heat exchange module, a gamma detection device, a flow meter, a PH meter, a flow adjusting electromagnetic valve, a flow adjusting manual valve and an infusion pump which are sequentially arranged from the liquid outlet end to the liquid inlet end of a nuclear waste liquid discharging pipeline, and a multi-channel power supply processing box and an industrial personal computer which are fixedly assembled on the outer side of the gamma detection device. The gamma detection device is provided with a temperature and liquid level integrated probe and an annular sodium iodide crystal detector; the heat exchange module, the temperature and liquid level integrated probe, the annular sodium iodide crystal detector, the flow meter, the PH meter, the flow adjusting electromagnetic valve, the infusion pump and the industrial personal computer are all electrically connected with the multi-channel power supply processing box. The gamma detection device is further provided with a measuring cylinder used for containing nuclear waste liquid, and the temperature and liquid level integrated probe and the annular sodium iodide crystal detector are fixedly assembled in the measuring cylinder. The system can continuously monitor the gamma radioactive activity concentration of the nuclear waste liquid on line, and the detection efficiency is high.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear radiation monitoring, in particular to a real-time monitoring system for gamma radioactivity of nuclear waste liquid. Background Art

[0002] During the power generation process at nuclear power plants, radioactive materials are released into water, forming liquid nuclear waste. This waste is sometimes temporarily discharged. During this temporary discharge, radioactivity testing and analysis are required to ensure that the radioactive content is within safety standards and to prevent harm to the environment and public health.

[0003] In existing technology, monitoring of temporarily discharged nuclear waste liquid typically involves periodic monitoring of gamma radioactivity using sodium iodide detectors containing columnar sodium iodide crystals. However, the radioactivity intensity of temporarily discharged nuclear waste liquid is not constant, and periodic monitoring cannot accurately determine the real-time gamma radioactivity concentration of the waste liquid, potentially leading to uncontrolled release of radioactive waste liquid. Furthermore, the detection surfaces of the columnar sodium iodide crystals are limited to the sidewalls and bottom, resulting in low detection efficiency. Summary of the Invention

[0004] Based on this, it is necessary to provide a real-time monitoring system for gamma radioactivity of nuclear waste liquid to address the above technical problems, which can continuously monitor the gamma radioactivity activity concentration of nuclear waste liquid online with high detection efficiency.

[0005] The present invention provides a real-time monitoring system for gamma radioactivity of nuclear waste liquid, comprising a heat exchange module, a gamma detection device, a flow meter, a pH meter, a flow regulating solenoid valve, a flow regulating manual valve and a liquid pump, and a multi-channel power supply processing box and an industrial control computer fixedly mounted on the outside of the gamma detection device, which are sequentially arranged from the liquid inlet end to the liquid outlet end of the nuclear waste liquid discharge pipeline;

[0006] The gamma detection device is equipped with a temperature and liquid level integrated probe and a ring-shaped sodium iodide crystal detector;

[0007] The heat exchange module, the integrated temperature and liquid level probe, the annular sodium iodide crystal detector, the flow meter, the pH meter, the flow regulating solenoid valve, the liquid pump and the industrial computer are all electrically connected to the multi-channel power supply processing box;

[0008] The gamma detection device is also provided with a measuring cylinder for containing nuclear waste liquid, and a temperature and liquid level integrated probe and an annular sodium iodide crystal detector are fixedly assembled inside the measuring cylinder;

[0009] The maximum outer diameter of the annular sodium iodide crystal detector is smaller than the inner diameter of the measuring tube, and the distance between the bottom of the annular sodium iodide crystal detector and the bottom of the measuring tube is L;

[0010] The annular sodium iodide crystal detector is provided with an annular sodium iodide crystal and an annular shell. The sodium iodide crystal is arranged inside the shell. The top of the shell is fixedly connected with multiple photoelectric multiplication and signal processing components coupled with the sodium iodide crystal.

[0011] In one embodiment, a multi-channel power supply processing box is used to receive measurement signals from a temperature and liquid level integrated probe, an annular sodium iodide crystal detector, a flow meter and a pH meter, and analyze and process the measurement signals to obtain the pH value of the nuclear waste liquid and the flow rate flowing through the discharge pipeline, as well as the temperature, liquid level and measurement energy spectrum of the nuclear waste liquid in the gamma detection device, and then send the pH value, flow, temperature, liquid level and measurement energy spectrum of the annular sodium iodide crystal detector to an industrial computer; and is used to power the heat exchange module, the temperature and liquid level integrated probe, the annular sodium iodide crystal detector, the flow meter, the pH meter, the flow regulating solenoid valve, the liquid pump and the industrial computer.

[0012] In one embodiment, the industrial computer is used to analyze the measured energy spectrum of the annular sodium iodide crystal detector to obtain the total gamma activity concentration and the activity concentration of each radioactive nuclide of the nuclear waste liquid;

[0013] Used to send control signals to the flow regulating solenoid valve and the liquid pump through the multi-channel power supply processing box;

[0014] It is also used to display the total gamma activity concentration, the activity concentration of each radionuclide, pH, flow rate, temperature and liquid level.

[0015] In one embodiment, a support seat is provided inside the measuring cylinder, and the support seat is provided with a fixing plate and a groove ring, the fixing plate is vertically fixedly connected to the inner wall of the measuring cylinder, and the groove ring is integrally connected to the middle part of the fixing plate, and the opening of the groove ring faces upward;

[0016] The fixing plate is annular, and the outer diameter of the fixing plate is equal to the inner diameter of the measuring cylinder;

[0017] The housing is sleeved inside the groove ring, and the photomultiplier and signal processing components are located above the fixed plate;

[0018] The temperature-liquid-level integrated probe is fixedly assembled on the fixed plate, and the bottom of the temperature-liquid-level integrated probe abuts against the bottom of the measuring cylinder.

[0019] In one embodiment, a cover is fixedly mounted on the top of the measuring cylinder. The cover is provided with a plurality of first through holes, the number of which is equal to the number of the photomultiplier and signal processing components. Each photomultiplier and signal processing component is inserted into a first through hole.

[0020] In one embodiment, the gamma detection device is further provided with a liquid outlet pipe and a liquid inlet pipe;

[0021] The cover plate is provided with a second through hole, the fixed plate is provided with a first liquid outlet hole, a sealing plate is provided at the top of the central cavity of the shell, the sealing plate is fixedly connected to the top of the groove ring, the sealing plate is provided with a second liquid outlet hole, one end of the liquid outlet pipe is connected to the nuclear waste liquid discharge pipeline, and the other end of the liquid outlet pipe passes through the second through hole and is connected to both the first liquid outlet hole and the second liquid outlet hole;

[0022] A liquid inlet hole is provided at the bottom of the measuring cylinder, one end of the liquid inlet pipe is connected to the nuclear waste liquid discharge pipeline, and the other end of the liquid inlet pipe is connected to the liquid inlet hole.

[0023] In one embodiment, L ≥ 10 cm;

[0024] A foldable bracket is also provided at the bottom of the measuring tube, and the bracket is fixedly connected to the measuring tube;

[0025] A grip is provided on the top of the cover plate, and the grip is fixedly connected to the cover plate.

[0026] The beneficial effects of the present invention are:

[0027] (1) The real-time monitoring system for gamma radioactivity of nuclear waste liquid of the present invention can perform real-time continuous online monitoring of the total gamma activity concentration and the activity concentration of each radioactive nuclide of the discharged nuclear waste liquid, thereby avoiding the uncontrolled discharge of radioactive nuclear waste liquid.

[0028] (2) The real-time monitoring system for gamma radioactivity of nuclear waste liquid of the present invention can automatically control the flow regulating solenoid valve and the liquid extraction pump according to the measured flow rate, the total gamma activity concentration of the nuclear waste liquid and the activity concentration of each radioactive nuclide, so as to realize the automated control of the nuclear waste liquid discharge condition.

[0029] (3) The gamma detection device of the present invention uses an annular sodium iodide crystal detector to detect the gamma radioactivity of the nuclear waste liquid entering the measuring tube. The measuring tube can increase the volume of the radioactive nuclear waste liquid to be measured, thereby lowering the detection limit. In addition, the sodium iodide crystal of the annular sodium iodide crystal detector is annular, allowing the nuclear waste liquid to enter the central cavity of the shell. The detection surface of the annular sodium iodide crystal includes not only the side walls and bottom, but also the central inner wall, which can increase the detection efficiency of the sodium iodide crystal. BRIEF DESCRIPTION OF THE DRAWINGS

[0030] Figure 1 A schematic diagram of a real-time monitoring system for gamma radioactivity in nuclear waste water provided by an embodiment of the present invention;

[0031] Figure 2 A schematic structural diagram of a gamma detection device provided in an embodiment of the present invention;

[0032] Figure 3 for Figure 2 One of the cross-sectional diagrams along the axis of the measuring cylinder;

[0033] Figure 4 A schematic structural diagram of a ring-shaped sodium iodide crystal detector provided in an embodiment of the present invention;

[0034] Figure 5 for Figure 4 One of the schematic cross-sections along the axis of a sodium iodide crystal;

[0035] Figure 6 A schematic structural diagram of a support base provided in an embodiment of the present invention.

[0036] Explanation of the reference numerals: 10, liquid inlet; 20, heat exchange module; 30, gamma detection device; 31, multi-channel power supply processing box; 32, industrial computer; 40, flow meter; 50, pH meter; 60, flow regulating solenoid valve; 70, flow regulating manual valve; 80, liquid pump; 90, liquid outlet; 100, measuring cylinder; 110, cover plate; 120, gripper; 200, annular sodium iodide crystal detector; 210, housing; 220, sodium iodide crystal; 230, photomultiplier and signal processing component; 300, support seat; 310, fixing plate; 320, groove ring; 330, sealing plate; 340, first liquid outlet; 350, temperature and liquid level integrated probe; 400, liquid outlet pipe; 500, liquid inlet pipe; 600, bracket. DETAILED DESCRIPTION

[0037] In order to make the above-mentioned objects, features and advantages of the present invention more obvious and easy to understand, the specific embodiments of the present invention are described in detail below with reference to the accompanying drawings.

[0038] It should be noted that in the description of the present invention, “upper”, “lower”, “top”, “bottom”, orientation or position relationship is based on the attached Figure 2 Regarding the orientation or positional relationship shown, it should be understood that these orientation terms are only for the convenience of describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operate in a specific orientation. Therefore, it should not be understood as a limitation on the present invention.

[0039] In one embodiment, Figure 1As shown, the real-time monitoring system for gamma radioactivity of nuclear waste liquid of this embodiment includes a heat exchange module 20, a gamma detection device 30, a flow meter 40, a pH meter 50, a flow regulating solenoid valve 60, a flow regulating manual valve 70 and a liquid pump 80 arranged in sequence along the liquid inlet end 10 to the liquid outlet end 90 of the nuclear waste liquid discharge pipeline, and a multi-channel power supply processing box 31 and an industrial computer 32 fixedly assembled on the outside of the gamma detection device 30; the gamma detection device 30 is provided with a temperature-liquid-level integrated probe 350 and an annular sodium iodide crystal detector 200; the heat exchange module 20, the temperature-liquid-level integrated probe 350, the annular sodium iodide crystal detector 200, the flow meter 40, the pH meter 50, the flow regulating solenoid valve 60, the liquid pump 80 and the industrial computer 32 are all electrically connected to the multi-channel power supply processing box 31.

[0040] Specifically, the multi-channel power supply processing box 31 is used to receive measurement signals from the temperature and liquid level integrated probe 350, the annular sodium iodide crystal detector 200, the flow meter 40 and the pH meter 50, and analyze and process the measurement signals to obtain the pH value of the nuclear waste liquid and the flow rate flowing through the discharge pipeline, as well as the temperature, liquid level and measurement energy spectrum of the nuclear waste liquid in the gamma detection device 30 of the annular sodium iodide crystal detector 200, and then send the pH value, flow, temperature, liquid level and measurement energy spectrum of the annular sodium iodide crystal detector 200 to the industrial computer 32; and is used to power the heat exchange module 20, the temperature and liquid level integrated probe 350, the annular sodium iodide crystal detector 200, the flow meter 40, the pH meter 50, the flow regulating solenoid valve 60, the liquid pump 80 and the industrial computer 32.

[0041] The industrial computer 32 of this embodiment is used to analyze the measured energy spectrum of the annular sodium iodide crystal detector 200 to obtain the total gamma activity concentration and the activity concentration of each radioactive nuclide of the nuclear waste liquid; is used to send control signals to the flow regulating solenoid valve 60 and the liquid pump 80 through the multi-channel power supply processing box 31; and is used to display the total gamma activity concentration, the activity concentration of each radioactive nuclide, pH, flow rate, temperature and liquid level.

[0042] When the total gamma radiation detected in the nuclear waste exceeds the alarm threshold, the industrial computer 32 sends a closing signal to the flow regulating solenoid valve 60 through the multi-channel power supply processing box 31. Simultaneously, the industrial computer 32 sends a stop signal to the flow pump through the multi-channel power supply processing box 31. When it is necessary to stop detecting gamma radiation in the nuclear waste, the industrial computer 32 sends a stop signal to the flow pump through the multi-channel power supply processing box 31.

[0043] Specifically, the heat exchange module 20 is used to cool the nuclear waste liquid. After entering the discharge pipeline from the liquid inlet 10, the nuclear waste liquid first passes through the heat exchange module 20. When the nuclear waste liquid temperature exceeds 40°C, the heat exchange module 20 activates to reduce the nuclear waste liquid temperature to below 40°C, preventing excessive temperature damage to the equipment. The gamma detector 30 is used to measure the gamma radioactivity of the nuclear waste liquid; the liquid pump 80 provides power for extracting the nuclear waste liquid; the flow control solenoid valve 60 is controlled by the industrial computer 32 to adjust the flow in the nuclear waste liquid discharge pipeline; and the flow control manual valve 70 is manually controlled to adjust the flow in the nuclear waste liquid discharge pipeline.

[0044] The real-time monitoring system for gamma radioactivity of nuclear waste liquid of this embodiment can perform real-time continuous online monitoring of the total gamma activity concentration of the discharged nuclear waste liquid and the activity concentration of each radioactive nuclide, and automatically control the flow regulating manual valve 70 and the liquid suction pump 80 according to the measured flow rate, the total gamma activity concentration of the nuclear waste liquid and the activity concentration of each radioactive nuclide to achieve automated control of the nuclear waste liquid discharge condition, thereby avoiding uncontrolled discharge of radioactive nuclear waste liquid.

[0045] like Figure 2 and Figure 3 As shown, in this embodiment, the gamma detection device 30 is further provided with a measuring cylinder 100 for containing nuclear waste liquid, and the temperature and liquid level integrated probe 350 and the annular sodium iodide crystal detector 200 are fixedly assembled inside the measuring cylinder 100 .

[0046] The maximum outer diameter of the annular sodium iodide crystal detector 200 is smaller than the inner diameter of the measuring cylinder 100 , and the distance between the bottom of the annular sodium iodide crystal detector 200 and the bottom of the measuring cylinder 100 is L, where L is ≥ 10 cm.

[0047] like Figure 4 and Figure 5 As shown, the annular sodium iodide crystal detector 200 is provided with an annular sodium iodide crystal 220 and an annular shell 210. The sodium iodide crystal 220 is arranged inside the shell 210. A plurality of photoelectric multiplication and signal processing components 230 coupled with the sodium iodide crystal 220 are fixedly connected to the top of the shell 210.

[0048] Specifically, the photomultiplier and signal processing assembly 230 includes a photomultiplier tube, a voltage divider, and a signal processing circuit. The photomultiplier tube is coupled to a sodium iodide crystal 220. When gamma rays from the radioactive liquid in the sodium iodide crystal 220 detector are incident on the crystal, the crystal generates fluorescent photons in the visible light phase. These fluorescent photons then strike the photocathode of the photomultiplier tube, generating photoelectrons due to the photoelectric effect. After being amplified by the dynodes of the photomultiplier tube, the photoelectrons are output at the anode, generating electrical pulse signals that can be processed and analyzed by the voltage divider and signal processing circuitry.

[0049] The provision of the measuring tube 100 can increase the volume of radioactive nuclear waste to be measured, thereby lowering the detection limit. Once the nuclear waste enters the measuring tube 100, the outer wall, inner wall, and bottom of the annular sodium iodide crystal 220 can all detect gamma radiation, thereby enhancing the detection efficiency of the nuclear waste gamma detection device 30.

[0050] Specifically, the measuring cylinder 100 in this embodiment is made of stainless steel, and is designed to have an inner diameter no greater than 30 cm, an inner height no greater than 30 cm, and a weight less than 10 kg.

[0051] Preferably, the sodium iodide crystal 220 has an outer diameter of 6 inches, an inner diameter of 2 inches, and a height of 6 inches. To ensure the energy resolution of the detector, the photomultiplier tube is 1.5 inches in size. The number of photomultiplier and signal processing components 230 is four.

[0052] In one embodiment, Figure 6 As shown, a support base 300 is provided inside the measuring cylinder 100, and the support base 300 is provided with a fixing plate 310 and a groove ring 320. The fixing plate 310 is vertically fixedly connected to the inner wall of the measuring cylinder 100, and the groove ring 320 is integrally connected to the middle part of the fixing plate 310, and the opening of the groove ring 320 is upward; the fixing plate 310 is annular, and the outer diameter of the fixing plate 310 is equal to the inner diameter of the measuring cylinder 100; the outer shell 210 is sleeved on the inside of the groove ring 320, and the photomultiplier and signal processing component 230 is located above the fixing plate 310; the temperature and liquid level integrated probe 350 is fixedly assembled on the fixing plate 310, and the bottom of the temperature and liquid level integrated probe 350 is abutted against the bottom of the measuring cylinder 100.

[0053] In this embodiment, the groove ring 320 is disposed at the center of the fixed plate 310, and the fixed plate 310 is sleeved on the outside of the groove ring 320. The integrated temperature and level probe 350 is used to monitor the liquid level and temperature of the nuclear waste liquid inside the measuring cylinder 100 in real time. When the nuclear waste liquid level reaches the fixed plate 310, the entire system enters the measurement process.

[0054] In one embodiment, a cover plate 110 is fixedly mounted on the top of the measuring tube 100. The cover plate 110 is provided with a plurality of first through holes, the number of which is equal to the number of the photomultiplier and signal processing components 230. Each photomultiplier and signal processing component 230 is inserted into a first through hole.

[0055] In one embodiment, the gamma detection device 30 is also provided with a liquid outlet pipe 400 and a liquid inlet pipe 500; the cover plate 110 is provided with a second through hole, the fixed plate 310 is provided with a first liquid outlet hole 340, and a sealing plate 330 is provided at the top of the central cavity of the outer shell 210. The sealing plate 330 is fixedly connected to the top of the groove ring 320, and the sealing plate 330 is provided with a second liquid outlet hole. One end of the liquid outlet pipe 400 is connected to the nuclear waste liquid discharge pipeline, and the other end of the liquid outlet pipe 400 is connected to both the first liquid outlet hole 340 and the second liquid outlet hole after passing through the second through hole; a liquid inlet hole is provided at the bottom of the measuring cylinder 100, one end of the liquid inlet pipe 500 is connected to the nuclear waste liquid discharge pipeline, and the other end of the liquid inlet pipe 500 is connected to the liquid inlet hole.

[0056] Specifically, the liquid outlet pipe 400 is a three-way pipe, the liquid outlet portion of the three-way pipe passes through the second through hole, and the two liquid inlets of the three-way pipe are respectively connected to the first liquid outlet hole 340 and the second liquid outlet hole.

[0057] The sealing plate 330 cooperates with the support base 300 to divide the interior of the fixed cylinder into two cavities, an upper cavity and an lower cavity. When the nuclear waste liquid gamma detection device 30 is in use, the nuclear waste liquid only stays in the lower cavity and will not damage the photomultiplier and signal processing component 230.

[0058] In this embodiment, the liquid outlet pipe 400 and the liquid inlet pipe 500 are connected to the discharge pipeline using quick connectors, which can reduce the connection time of the pipelines when the device is used.

[0059] In one embodiment, the top of the housing 210 is fixedly connected to the fixing plate 310 via multiple Z-shaped connecting pieces, enhancing the secure connection between the annular sodium iodide crystal detector 200 and the support base 300. A foldable bracket 600 is also provided at the bottom of the measuring tube 100 and is fixedly connected to the measuring tube 100. A gripper 120 is provided at the top of the cover plate 110 and is fixedly connected to the cover plate 110, facilitating movement of the device.

[0060] The above-described embodiments merely represent several implementation methods of the present invention. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the present invention. It should be noted that a person skilled in the art would be able to make various modifications and improvements without departing from the spirit of the present invention, all of which fall within the scope of protection of the present invention. Therefore, the scope of protection of the present invention shall be determined by the appended claims.

Claims

1. A real-time monitoring system for gamma radioactivity of nuclear waste liquid, characterized in that: The invention comprises a heat exchange module (20), a gamma detection device (30), a flow meter (40), a pH meter (50), a flow regulating solenoid valve (60), a flow regulating manual valve (70) and a liquid pump (80) which are sequentially arranged along the liquid inlet end (10) to the liquid outlet end (90) of the nuclear waste liquid discharge pipeline, and a multi-channel power supply processing box (31) and an industrial control computer (32) which are fixedly assembled on the outside of the gamma detection device (30); The gamma detection device (30) is provided with a temperature and liquid level integrated probe (350) and a ring-shaped sodium iodide crystal detector (200); The heat exchange module (20), the integrated temperature and liquid level probe (350), the annular sodium iodide crystal detector (200), the flow meter (40), the pH meter (50), the flow regulating solenoid valve (60), the liquid pump (80) and the industrial computer (32) are all electrically connected to the multi-channel power supply processing box (31); The gamma detection device (30) is further provided with a measuring cylinder (100) for containing nuclear waste liquid, and the temperature and liquid level integrated probe (350) and the annular sodium iodide crystal detector (200) are fixedly assembled inside the measuring cylinder (100); The maximum outer diameter of the annular sodium iodide crystal detector (200) is smaller than the inner diameter of the measuring cylinder (100), and the distance between the bottom of the annular sodium iodide crystal detector (200) and the bottom of the measuring cylinder (100) is L; The annular sodium iodide crystal detector (200) is provided with an annular sodium iodide crystal (220) and an annular housing (210); the sodium iodide crystal (220) is arranged inside the housing (210); and a plurality of photoelectric multiplication and signal processing components (230) coupled to the sodium iodide crystal (220) are fixedly connected to the top of the housing (210).

2. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 1, characterized in that: The multi-channel power supply processing box (31) is used to receive measurement signals from the temperature and liquid level integrated probe (350), the annular sodium iodide crystal detector (200), the flow meter (40) and the pH meter (50), and analyze and process the measurement signals to obtain the pH value of the nuclear waste liquid and the flow rate flowing through the discharge pipeline, as well as the temperature and liquid level of the nuclear waste liquid in the gamma detection device (30) and the measurement energy spectrum of the annular sodium iodide crystal detector (200), and then send the pH value, flow rate, temperature, liquid level and the measurement energy spectrum of the annular sodium iodide crystal detector (200) to the industrial control computer (32); and is used to power the heat exchange module (20), the temperature and liquid level integrated probe (350), the annular sodium iodide crystal detector (200), the flow meter (40), the pH meter (50), the flow regulating solenoid valve (60), the liquid pump (80) and the industrial control computer (32).

3. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 2, characterized in that: The industrial control computer (32) is used to analyze the measured energy spectrum of the annular sodium iodide crystal detector (200) to obtain the total gamma activity concentration of the nuclear waste liquid and the activity concentration of each radioactive nuclide; for sending control signals to the flow regulating solenoid valve (60) and the liquid pump (80) through the multi-channel power supply processing box (31); It is also used to display the total gamma activity concentration, the activity concentration of each radionuclide, pH, flow rate, temperature and liquid level.

4. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 1, characterized in that: A support seat (300) is provided inside the measuring cylinder (100), and the support seat (300) is provided with a fixing plate (310) and a groove ring (320), wherein the fixing plate (310) is vertically fixedly connected to the inner wall of the measuring cylinder (100), and the groove ring (320) is integrally connected to the middle part of the fixing plate (310), and the opening of the groove ring (320) is upward; The fixing plate (310) is annular, and the outer diameter of the fixing plate (310) is equal to the inner diameter of the measuring cylinder (100); The housing (210) is sleeved inside the groove ring (320), and the photomultiplier and signal processing component (230) is located above the fixing plate (310); The temperature-liquid-level integrated probe (350) is fixedly assembled on the fixed plate (310), and the bottom of the temperature-liquid-level integrated probe (350) abuts against the bottom of the measuring cylinder (100).

5. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 4, characterized in that: A cover plate (110) is fixedly mounted on the top of the measuring cylinder (100), and the cover plate (110) is provided with a plurality of first through holes, the number of which is equal to the number of the photomultiplier and signal processing components (230), and each photomultiplier and signal processing component (230) is inserted into one of the first through holes.

6. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 5, characterized in that: The gamma detection device (30) is further provided with a liquid outlet pipe (400) and a liquid inlet pipe (500); The cover plate (110) is provided with a second through hole, the fixed plate (310) is provided with a first liquid outlet (340), a sealing plate (330) is provided at the top of the central cavity of the housing (210), the sealing plate (330) is fixedly connected to the top of the groove ring (320), the sealing plate (330) is provided with a second liquid outlet, one end of the liquid outlet pipe (400) is communicated with the nuclear waste liquid discharge pipeline, and the other end of the liquid outlet pipe (400) passes through the second through hole and is communicated with both the first liquid outlet (340) and the second liquid outlet; A liquid inlet hole is provided at the bottom of the measuring cylinder (100), one end of the liquid inlet pipe (500) is connected to the nuclear waste liquid discharge pipeline, and the other end of the liquid inlet pipe (500) is connected to the liquid inlet hole.

7. The real-time monitoring system for gamma radioactivity of nuclear waste liquid according to claim 6, characterized in that: L ≥ 10cm; A foldable bracket (600) is further provided at the bottom of the measuring cylinder (100), and the bracket (600) is fixedly connected to the measuring cylinder (100); A gripper (120) is provided on the top of the cover plate (110), and the gripper (120) is fixedly connected to the cover plate (110).

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