A radioactive waste liquid nuclide separation device

Abstract

This utility model discloses a radionuclide separation device for radioactive waste liquid, comprising a separation device body, a precipitation chamber, and an ion exchange column. The precipitation chamber is located at one end of the separation device body, and a metering cylinder is located at the top end of the separation device body. A piston pusher plate is installed inside the metering cylinder, and a cylinder is fixed to the top of the metering cylinder. The output end of the cylinder is connected to the piston pusher plate via a telescopic rod. An ion exchange column is located inside the separation device body on one side of the precipitation chamber. This utility model, by installing a separation device body, a filter box, a precipitation chamber, a first drive motor, a stirring component, a metering cylinder, a cylinder, a piston pusher plate, a discharge pipe, and a solenoid valve, controls the amount of chemical reagent introduced, quantitatively adding reagent to ensure sufficient reaction between the radionuclides in the waste liquid and the chemical reagent, thereby improving separation efficiency.

Description

Technical Field

[0001] This utility model relates to the field of radioactive waste liquid separation technology, specifically a radioactive waste liquid nuclide separation device. Background Technology

[0002] Radioactive waste contains various radionuclides (such as uranium, plutonium, cesium, strontium, etc.), and its radioactivity level may be extremely high. Direct discharge or storage of untreated radioactive waste may pose a serious threat to the environment and human health. By separating radionuclides, high-level radionuclides can be removed or reduced, thereby lowering the radioactivity level of the waste and reducing environmental risks.

[0003] When separating radioactive waste liquid from radionuclides, it is generally necessary to first pass it through a filtration device to remove suspended solids, and then enter a chemical precipitation reactor. Chemical reagents are added to cause the target radionuclides (such as strontium and cesium) to precipitate. The upper layer of waste liquid is then passed through an ion exchange column, where the resin adsorbs radionuclides such as uranium and plutonium, thereby separating the radionuclides from the radioactive waste liquid. However, the addition of chemical reagents to the precipitation reactor generally lacks the function of quantitative introduction, and the amount of chemical reagents added directly affects the reaction efficiency between the radionuclides and the reagents. Insufficient reagents can easily lead to incomplete reactions, while excessive reagents will cause waste. Therefore, improvements are needed. Utility Model Content

[0004] The purpose of this invention is to provide a radioactive waste liquid nuclide separation device to solve the problems mentioned in the background art.

[0005] To achieve the above objectives, this utility model provides the following technical solution: a radioactive waste liquid nuclide separation device, comprising a separation device body, a precipitation chamber, and an ion exchange column. A precipitation chamber is located at one end of the separation device body. A metering cylinder is located at one end of the top of the separation device body, and the bottom of the metering cylinder is connected to the precipitation chamber via an outlet pipe. An inlet pipe is located on one side of the metering cylinder, and a solenoid valve is installed on the outlet pipe. A piston pusher plate is located inside the metering cylinder, and a cylinder is fixed at the top of the metering cylinder. The output end of the cylinder is connected to the piston pusher plate via a telescopic rod. An ion exchange column is located inside the separation device body on one side of the precipitation chamber, and the interior of the ion exchange column is uniformly filled with resin particles. A first pump body is fixed at the center of the top of the separation device body, and both ends of the first pump body are connected to the precipitation chamber and the ion exchange column via connecting pipes, respectively.

[0006] Preferably, a filter box is provided on one side of the main body of the separation device, and one side of the filter box is connected to the sedimentation chamber. A filter screen is provided inside the filter box, and a differential pressure sensor is provided at one end of the top of the filter box. A high-pressure end and a negative-pressure end are respectively connected to the differential pressure sensor by wires. The high-pressure end and the negative-pressure end are respectively located on the front and rear sides of the filter screen.

[0007] Preferably, a tank is provided at the bottom of the sedimentation chamber, and a roller is provided inside the tank. Spiral blades are evenly distributed on the roller. A second drive motor is fixed at the bottom of one side of the main body of the separation device, and the output end of the second drive motor is connected to the roller.

[0008] Preferably, a stirring element is provided at the center of the sedimentation chamber, and a first drive motor is fixed on the main body of the separation device above the sedimentation chamber, with the output end of the first drive motor connected to the stirring element.

[0009] Preferably, an evaporation cylinder is provided inside the separation device body on one side of the ion exchange column, and a second pump body is fixed inside the separation device body between the evaporation cylinder and the ion exchange column. The two ends of the second pump body are respectively connected to the ion exchange column and the evaporation cylinder through connecting pipes.

[0010] Preferably, a heating chamber is provided on the outer side of the evaporation cylinder, and electric heating tubes are evenly distributed inside the heating chamber.

[0011] Preferably, a condenser box is provided on the side of the main body of the separation device away from the metering cylinder, and a condensation chamber is provided at the top of the condenser box. The top of the evaporation cylinder is connected to the condensation chamber through a gas guide pipe.

[0012] Preferably, the condensing chamber is provided with a condensing pipe inside, and the condensing box below the condensing chamber is provided with a collection tank.

[0013] Preferably, a first pump body is fixed at the center of the top of the main body of the separation device, and the two ends of the first pump body are respectively connected to the precipitation chamber and the ion exchange column through connecting pipes.

[0014] Compared with the prior art, the beneficial effects of this utility model are as follows: This radioactive waste liquid nuclide separation device is equipped with a separation device body, a filter box, a sedimentation chamber, a first drive motor, a stirring component, a metering cylinder, a cylinder, a piston pusher plate, a discharge pipe, and a solenoid valve. The radioactive waste liquid first enters the filter box to remove suspended solids and solid particles. Then it enters the sedimentation chamber and is connected to a chemical reagent supply device through an inlet pipe to introduce chemical reagents into the metering cylinder. After that, the solenoid valve is opened, and the cylinder drives the piston pusher plate to move down, pressing the chemical reagents into the sedimentation chamber to mix and react with the waste liquid, causing the target nuclide to precipitate. By adjusting the position of the piston pusher plate driven by the cylinder, the internal space of the metering cylinder below the piston pusher plate is controlled, thereby controlling the amount of chemical reagent introduced. The quantitative addition of reagents ensures that the nuclides in the waste liquid react fully with the chemical reagents, improving the separation efficiency and avoiding incomplete reaction due to insufficient chemical reagents or waste due to excessive chemical reagents. Attached Figure Description

[0015] To more clearly illustrate the technical solutions of the embodiments of this utility model, the drawings used in the embodiments will be briefly introduced below. It should be understood that the following drawings only show some embodiments of this utility model and should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can be obtained based on these drawings without creative effort.

[0016] Figure 1 This is a frontal cross-sectional view of the present invention.

[0017] Figure 2 This is a schematic diagram of the cross-sectional structure of the metering cylinder of this utility model;

[0018] Figure 3 For the present utility model Figure 1 Enlarged structural diagram at point A in the middle;

[0019] Figure 4 This is a schematic cross-sectional view of the filter box structure of this utility model;

[0020] Figure 5 This is a schematic cross-sectional view of the condenser box of this utility model.

[0021] In the diagram: 1. Main body of the separation device; 2. Filter box; 3. Filter screen; 4. Sedimentation chamber; 5. Metering cylinder; 6. Stirring component; 7. First drive motor; 8. Tank; 9. Second drive motor; 10. First pump body; 11. Ion exchange column; 12. Resin particles; 13. Evaporation cylinder; 14. Heating chamber; 15. Electric heating tube; 16. Condenser; 17. Second pump body; 18. Piston pusher plate; 19. Cylinder; 20. Inlet pipe; 21. Outlet pipe; 22. Solenoid valve; 23. Roller; 24. Spiral blade; 25. Differential pressure sensor; 26. High pressure end; 27. Negative pressure end; 28. Condenser chamber; 29. ​​Condenser tube; 30. Collection tank. Detailed Implementation

[0022] The technical solutions of the present utility model will be clearly and completely described below with reference to the accompanying drawings of the embodiments. All other embodiments obtained by those skilled in the art based on the embodiments of the present utility model without creative effort are within the scope of protection of the present utility model.

[0023] Please see Figure 1-5 An embodiment of this utility model is provided: a radioactive waste liquid nuclide separation device, including a separation device body 1, a precipitation chamber 4 and an ion exchange column 11. A filter box 2 is provided on one side of the separation device body 1, and a filter screen 3 is provided inside the filter box 2. A precipitation chamber 4 is provided at one end inside the separation device body 1, and one side of the filter box 2 is connected to the precipitation chamber 4.

[0024] Radioactive waste liquid first enters the filter box 2, where suspended solids and solid particles are removed by the filter screen 3, and then enters the sedimentation chamber 4;

[0025] A differential pressure sensor 25 is installed at one end of the top of the filter box 2. The differential pressure sensor 25 is connected to a high pressure end 26 and a negative pressure end 27 by wires. The high pressure end 26 and the negative pressure end 27 are respectively located on the front and rear sides of the filter screen 3 to monitor the pressure difference between the front and rear ends of the filter screen 3 in real time.

[0026] Since clogging of filter screen 3 will cause the pressure difference between the inlet and outlet sides to increase, the differential pressure sensor 25 monitors the pressure difference before and after filter screen 3, and transmits the signal to the control system when the pressure difference before and after exceeds the preset threshold, so as to prompt the staff to replace filter screen 3.

[0027] A metering cylinder 5 is provided at one end of the top of the main body 1 of the separation device, and the bottom of the metering cylinder 5 is connected to the sedimentation chamber 4 through the liquid outlet pipe 21. A liquid inlet pipe 20 is provided on one side of the metering cylinder 5, and a solenoid valve 22 is provided on the liquid outlet pipe 21. A piston pusher plate 18 is provided inside the metering cylinder 5, and a cylinder 19 is fixed on the top of the metering cylinder 5. The output end of the cylinder 19 is connected to the piston pusher plate 18 through a telescopic rod.

[0028] The chemical reagent supply equipment is connected through the liquid inlet pipe 20, and the chemical reagent is introduced into the metering cylinder 5. Then the solenoid valve 22 is opened, and the cylinder 19 drives the piston pusher plate 18 to move down, pressing the chemical reagent into the precipitation chamber 4, where it mixes and reacts with the waste liquid, causing the target nuclide such as strontium and cesium to precipitate.

[0029] By adjusting the position of the piston pusher plate 18 driven by the cylinder 19, the internal space of the metering cylinder 5 below the piston pusher plate 18 is controlled, thereby controlling the amount of chemical reagent introduced. The quantitative addition of reagents allows the nuclides in the waste liquid to fully react with the chemical reagents, improving the separation efficiency and avoiding incomplete reaction due to insufficient chemical reagents or waste due to excessive chemical reagents.

[0030] A stirring element 6 is installed in the center of the sedimentation chamber 4. A first drive motor 7 is fixed on the main body 1 of the separation device above the sedimentation chamber 4. The output end of the first drive motor 7 is connected to the stirring element 6. The first drive motor 7 drives the stirring element 6 to rotate, thereby improving the reaction efficiency of radioactive waste liquid and chemical reagents.

[0031] The bottom of the sedimentation chamber 4 is provided with a tank 8, and the inside of the tank 8 is provided with a roller 23. Spiral blades 24 are evenly distributed on the roller 23. The bottom of one side of the separation device body 1 is fixed with a second drive motor 9, and the output end of the second drive motor 9 is connected to the roller 23.

[0032] After the target nuclide is precipitated, it enters the tank 8. Subsequently, the second drive motor 9 drives the roller 23 and the spiral blade 24 to rotate, which can transport the precipitate towards the discharge port for easy discharge.

[0033] An ion exchange column 11 is installed inside the main body 1 of the separation device on one side of the precipitation chamber 4, and the interior of the ion exchange column 11 is uniformly filled with resin particles 12. A first pump body 10 is fixed at the center of the top of the main body 1 of the separation device, and the two ends of the first pump body 10 are connected to the precipitation chamber 4 and the ion exchange column 11 respectively through connecting pipes.

[0034] The upper layer of waste liquid in the sedimentation chamber 4 is pumped into the ion exchange column 11 through the first pump body 10. The resin particles 12 adsorb uranium and plutonium nuclides in the waste liquid. After adsorption, the uranium and plutonium nuclides are desorbed from the resin particles 12 by elution treatment, thereby achieving separation.

[0035] An evaporation cylinder 13 is installed inside the separation device body 1 on one side of the ion exchange column 11, and a second pump body 17 is fixed inside the separation device body 1 between the evaporation cylinder 13 and the ion exchange column 11. The two ends of the second pump body 17 are connected to the ion exchange column 11 and the evaporation cylinder 13 respectively through connecting pipes.

[0036] A heating chamber 14 is provided on the outside of the evaporator cylinder 13, and electric heating tubes 15 are evenly distributed inside the heating chamber 14.

[0037] Radioactive waste can have some radionuclides removed through precipitation and ion exchange treatment, but the remaining waste liquid may still contain low concentrations of nuclides. At this time, the remaining waste is drawn into the evaporation cylinder 13 through the second pump body 17. The electric heating tube 15 is energized and heats up to evaporate the remaining waste liquid. Evaporation removes water from the remaining waste, thereby increasing the concentration of nuclides in the remaining waste and reducing the volume of the waste liquid, thus reducing storage and disposal costs and facilitating subsequent treatment or recycling.

[0038] A condenser box 16 is provided on the side of the main body 1 of the separation device away from the filter box 2, and a condenser chamber 28 is provided at the top of the condenser box 16. The top of the evaporator 13 is connected to the condenser chamber 28 through a gas guide pipe.

[0039] The condenser chamber 28 is equipped with a condenser pipe 29, and the condenser box 16 below the condenser chamber 28 is equipped with a collection tank 30.

[0040] The water vapor generated during the evaporation of the remaining waste liquid enters the condensation chamber 28 through the gas guide pipe, and condenses into liquid by exchanging heat with the cooling water introduced in the condensation pipe 29 and is collected in the collection tank 30.

[0041] The specific models and specifications of the first drive motor 7, the second drive motor 9, the first pump body 10, the second pump body 17, the cylinder 19, the differential pressure sensor 25, the solenoid valve 22, and the electric heating tube 15 need to be determined based on the specifications and parameters of the device. The selection and calculation method is existing technology, so it will not be described in detail here.

[0042] Working Principle: In this embodiment, the radioactive waste liquid first enters the filter box 2, where suspended solids and particles are removed by the filter screen 3. It then enters the sedimentation chamber 4, and is connected to a chemical reagent supply device via the inlet pipe 20. The chemical reagent is introduced into the metering cylinder 5. Then, the solenoid valve 22 opens, and the cylinder 19 moves the piston pusher plate 18 downwards, forcing the chemical reagent into the sedimentation chamber 4 to mix and react with the waste liquid, causing the target nuclide (such as strontium or cesium) to precipitate. The position of the piston pusher plate 18 is adjusted by regulating the cylinder 19, thereby controlling the internal space of the metering cylinder 5 below the piston pusher plate 18 and thus controlling the amount of chemical reagent introduced. Quantitative addition of reagent ensures that the nuclide in the waste liquid reacts fully with the chemical reagent, improving separation efficiency and avoiding incomplete reaction due to insufficient chemical reagent or waste due to excessive chemical reagent. Simultaneously, the first drive motor 7 rotates the stirring element 6, further improving the reaction efficiency between the radioactive waste liquid and the chemical reagent. After precipitation, the target nuclide enters the tank 8. Subsequently, the second drive motor 9 drives the roller 23 and the spiral blade 24 to rotate, which can transport the precipitate towards the discharge port for easy discharge. The upper waste liquid is pumped into the ion exchange column 11 through the first pump body 10. The resin particles 12 adsorb uranium and plutonium nuclides in the waste liquid. After adsorption, the uranium and plutonium nuclides are desorbed from the resin particles 12 through elution treatment, thereby achieving separation. Radioactive waste can remove some radionuclides through precipitation and ion exchange treatment, but the remaining waste liquid may still contain low concentrations of nuclides. At this time, the remaining waste enters the evaporation cylinder 13. The electric heating tube 15 is energized and heats up to evaporate the remaining waste liquid. Evaporation removes water from the remaining waste, thereby increasing the concentration of nuclides in the remaining waste and reducing the volume of waste liquid, thereby reducing storage and disposal costs and facilitating subsequent treatment or recycling. The water vapor enters the condensation chamber 28 through the gas guide pipe and condenses into liquid by exchanging heat with the cooling water in the condensation tube 29 and is collected in the collection tank 30.

[0043] Obviously, the embodiments described above are only some embodiments of this utility model, and not all embodiments. Based on the embodiments of this utility model, all other embodiments obtained by those skilled in the art without creative effort should fall within the protection scope of this utility model.

[0044] It should be noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to limit the exemplary embodiments according to this application. As used herein, the singular form is intended to include the plural form as well, unless the context clearly indicates otherwise. Furthermore, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.

[0045] It should be noted that the terms "first," "second," etc., used in the specification, claims, and accompanying drawings of this application are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments of this application described herein can be implemented in sequences other than those illustrated or described herein.

[0046] The above are merely preferred embodiments of this utility model and are not intended to limit the scope of this utility model. Various modifications and variations can be made to this utility model by those skilled in the art. Any modifications, equivalent substitutions, or improvements made within the spirit and principles of this utility model should be included within the protection scope of this utility model.

Claims

1. A device for the separation of radwaste nuclides, characterized in that, The device includes a separation device body (1), a precipitation chamber (4), and an ion exchange column (11). The precipitation chamber (4) is located at one end of the separation device body (1). A metering cylinder (5) is located at one end of the top of the separation device body (1). The bottom of the metering cylinder (5) is connected to the precipitation chamber (4) through an outlet pipe (21). An inlet pipe (20) is located on one side of the metering cylinder (5). A solenoid valve (22) is located on the outlet pipe (21). A piston pusher plate (18) is located inside the metering cylinder (5). A cylinder (19) is fixed at the top of the metering cylinder (5). The output end of the cylinder (19) is connected to the piston pusher plate (18) through a telescopic rod. An ion exchange column (11) is located inside the separation device body (1) on one side of the precipitation chamber (4). The interior of the ion exchange column (11) is uniformly filled with resin particles (12).

2. A device for the separation of radionuclides from radioactive liquid waste according to claim 1, characterized in that: A filter box (2) is provided on one side of the main body (1) of the separation device. One side of the filter box (2) is connected to the sedimentation chamber (4). A filter screen (3) is provided inside the filter box (2). A differential pressure sensor (25) is provided at one end of the top of the filter box (2). A high-pressure end (26) and a negative-pressure end (27) are respectively connected to the differential pressure sensor (25) by wires. The high-pressure end (26) and the negative-pressure end (27) are respectively located on the front and rear sides of the filter screen (3).

3. The radioactive waste liquid nuclide separation device according to claim 1, characterized in that: The sedimentation chamber (4) has a tank (8) at the bottom, and a roller (23) is provided inside the tank (8). Spiral blades (24) are evenly distributed on the roller (23). A second drive motor (9) is fixed at the bottom of one side of the main body (1) of the separation device, and the output end of the second drive motor (9) is connected to the roller (23).

4. The radioactive waste liquid nuclide separation device according to claim 1, characterized in that: A stirring element (6) is provided in the center of the sedimentation chamber (4), and a first drive motor (7) is fixed on the main body (1) of the separation device above the sedimentation chamber (4). The output end of the first drive motor (7) is connected to the stirring element (6).

5. The radioactive waste liquid nuclide separation device according to claim 1, characterized in that: An evaporator (13) is provided inside the separation device body (1) on one side of the ion exchange column (11), and a second pump body (17) is fixed inside the separation device body (1) between the evaporator (13) and the ion exchange column (11). The two ends of the second pump body (17) are connected to the ion exchange column (11) and the evaporator (13) respectively through connecting pipes.

6. The radioactive waste liquid nuclide separation device according to claim 5, characterized in that: A heating chamber (14) is provided on the outside of the evaporator (13), and electric heating tubes (15) are evenly distributed inside the heating chamber (14).

7. The radioactive waste liquid nuclide separation device according to claim 5, characterized in that: The main body (1) of the separation device is provided with a condenser (16) on the side away from the metering cylinder (5), and a condenser chamber (28) is provided at the top of the condenser (16). The top of the evaporator (13) is connected to the condenser chamber (28) through a gas guide pipe.

8. A radioactive waste liquid nuclide separation device according to claim 7, characterized in that: The condenser (28) is provided with a condenser pipe (29) inside, and a collection tank (30) is provided in the condenser box (16) below the condenser (28).

9. A radioactive waste liquid nuclide separation device according to claim 1, characterized in that: The first pump body (10) is fixed at the center of the top of the main body (1) of the separation device, and the two ends of the first pump body (10) are connected to the precipitation chamber (4) and the ion exchange column (11) respectively through connecting pipes.

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