Treatment device for tritium-containing waste liquid

Abstract

The invention belongs to the technical field of radioactive waste liquid treatment, and particularly relates to a tritium-containing waste liquid treatment device. The tritium-containing waste liquid treatment device comprises a separation unit, a storage unit, an overhead condenser and a vacuum pump. A feeding hole is formed in the side surface of the separation unit, and a light component discharging port and a light component reflux inlet are formed in the top of the separation unit. And a heavy component discharge port is formed in the bottom of the separation unit. And the separation unit is connected between the tower top condenser and the storage unit. And the overhead condenser is connected with a light component discharge port of the separation unit, a light component reflux inlet of the separation unit and a vacuum pump. The tritium-containing waste liquid is treated by adopting a repeated rectification technology, so that the technical problems that an existing treatment device has the capacity of treating the high-capacity low-emission tritium-containing waste liquid and is safe, economical and easy and convenient to operate and maintain are solved.

Description

Technical Field

[0001] This application belongs to the technical field of radioactive waste liquid treatment, and particularly relates to a treatment device for tritium-containing waste liquid. Background Art

[0002] During the operation of nuclear power plants, radioactive wastes such as radioactive gases, liquids, and solids will be generated due to the existence of fission products, corrosion products, and activation of coolants. Tritium in radioactive wastes exists in the form of tritiated water and cannot be separated by the purification system. The tritium-containing waste liquid is characterized by a large volume and a low specific activity of tritium.

[0003] Currently, the main methods for tritium separation and concentration include cryogenic distillation, water rectification, electrolysis, thermal diffusion, solvent extraction, molecular laser method, catalytic exchange method, chromatography, and processes and derivative processes that combine two or more of these methods. Among them, most methods such as cryogenic distillation, thermal diffusion, and catalytic exchange method require converting the raw material into hydrogen before separation. For tritium-containing waste liquid with low specific activity and large volume, direct conversion is very uneconomical and unrealistic. The electrolysis method also has problems such as small treatment throughput, high energy consumption, and cannot meet the treatment requirements of tritium-containing waste liquid with large volume. Chromatography is a feasible method for hydrogen isotope gas separation, but this method cannot be used to directly enrich tritium from tritium-containing waste liquid. Therefore, it is necessary to develop a method that not only has the ability to treat large-capacity low-level tritium-containing waste liquid but also is safe, economical, and easy to operate and maintain. Summary of the Invention

[0004] In view of this, this application is committed to providing a treatment device for tritium-containing waste liquid, and by adopting the repeated rectification technology to treat the tritium-containing waste liquid, it aims to solve the technical problem that it is difficult for existing treatment devices to have both the ability to treat large-capacity low-level tritium-containing waste liquid and be safe, economical, and easy to operate and maintain.

[0005] The present application provides a treatment device for tritium-containing waste liquid. The treatment device for tritium-containing waste liquid includes a separation unit, a storage unit, a top condenser and a vacuum pump. The side of the separation unit is provided with a feed port, and the top of the separation unit is provided with a light component discharge port and a light component reflux port. The bottom of the separation unit is provided with a heavy component discharge port. The separation unit is connected between the top condenser and the storage unit, and is used for rectifying and separating the tritium-containing waste liquid entering the separation unit from the feed port and the light component reflux port into gaseous light isotope water of hydrogen and liquid heavy isotope water of hydrogen. The top condenser is connected to the light component discharge port of the separation unit, the light component reflux port of the separation unit and the vacuum pump, and is used for condensing the gaseous light isotope water of hydrogen entering through the light component discharge port to obtain light component water, and when the tritium concentration of the light component water does not meet the discharge standard, it is refluxed into the separation unit through the light component reflux port, and is discharged after the tritium concentration of the light component water meets the discharge standard. The storage unit is used for storing the liquid heavy isotope water of hydrogen transmitted by the separation unit through the heavy component discharge port, and conveying it to the feed port of the separation unit after the liquid heavy isotope water of hydrogen is stored to a preset amount.

[0006] In a specific embodiment of the present application, the separation unit includes a primary rectification column. The top of the primary rectification column is connected to a top condenser and a vacuum pump. The heavy component discharge port at the bottom of the primary rectification column is connected to the storage unit.

[0007] In a specific embodiment of the present application, the separation unit includes a liquid delivery pump, a bottom reboiler and a multi-stage rectification column arranged in series. The top of the first-stage rectification column in the multi-stage rectification column is designed with a light component discharge port and is connected to a top condenser and a vacuum pump. A bottom reboiler is connected to the heavy component discharge port at the bottom of the last-stage rectification column in the multi-stage rectification column. A gas pipeline and a liquid pipeline are connected between the top and the bottom of adjacent two-stage rectification columns. A liquid delivery pump is provided on the liquid pipeline.

[0008] In a specific embodiment of the present application, the number of stages of the multi-stage rectification column ranges from 2 to 10.

[0009] In a specific embodiment of the present application, the height range of the rectification column is 1 m to 50 m; and / or, the diameter range of the rectification column is 0.05 m to 10 m; and / or, the feed rate range of the rectification column is 0.1 kg / h to 10000 kg / h; and / or, the reflux ratio range of the rectification column is 1 to 500; the top pressure range of the rectification column is 6 KPa to 100 KPa.

[0010] In a specific embodiment of the present application, the height range of the rectification column is 10 m to 40 m; and / or, the diameter range of the rectification column is 0.1 m to 5 m; and / or, the feed rate range of the rectification column is 5 kg / h to 1000 kg / h; and / or, the reflux ratio range of the rectification column is 10 KPa to 100 KPa.

[0011] In a specific embodiment of the present application, the packing used in the distillation column includes surface-modified corrugated phosphor bronze wire mesh packing.

[0012] In a specific embodiment of the present application, the packing used in the distillation column includes surface-modified corrugated phosphor bronze wire mesh packing and random packing.

[0013] In a specific embodiment of the present application, the storage unit includes a storage tank circulation pump and at least one storage tank. At least one storage tank is designed in parallel and connected to one end of the storage tank circulation pump. The other end of the storage tank circulation pump is connected to the feed inlet of the separation unit.

[0014] In a specific embodiment of the present application, the storage tank adopts a double storage tank structure, and the effective volume of each storage tank is 10 tons to 50 tons.

[0015] The beneficial effects of the technical solution of the present application are as follows: By using the separation unit to carry out distillation separation on the tritium-containing waste liquid, and using the top condenser to discharge low-tritium water meeting the emission standards and returning the low-tritium water not meeting the emission standards to the separation unit, the technical means of using distillation technology to treat the tritium-containing waste liquid is adopted, achieving the technical effect of reducing the liquid tritium emission in nuclear power plants. Compared with other tritium separation and enrichment technologies, the embodiments of the present application have the advantages of convenient steam energy, small investment, safety, simple operation and maintenance, and no radioactive solid waste. In addition, the storage unit is used to store the heavy isotope water of hydrogen in the liquid phase, and after the heavy isotope water of hydrogen in the liquid phase is stored to a preset amount, it is transported to the feed inlet of the separation unit for repeated distillation separation. Therefore, the storage unit is used to store the heavy isotope water of hydrogen in the liquid phase, and the repeated distillation treatment technology of the heavy isotope water of hydrogen in the liquid phase is adopted, reducing the subsequent treatment process and device of the heavy isotope water of hydrogen in the liquid phase, and achieving the technical effect of reducing the volume and storing the tritium-containing waste liquid in nuclear power plants. In addition, compared with other technologies for treating tritium-rich water, including low-temperature distillation for tritium extraction, electrolytic enrichment for tritium extraction, electrolysis + chromatographic separation for tritium extraction, etc., the treatment device for the tritium-containing waste liquid does not require additional investment in the treatment of the heavy isotope water of hydrogen in the liquid phase, and has the advantages of small investment, safety (no risk of hydrogen explosion), simple operation and maintenance, and no radioactive waste. That is, it reduces the investment cost, industrial risk and operation and maintenance complexity, achieving the purpose of effectively reducing the volume of the tritium-containing waste liquid in nuclear power plants and reducing the liquid tritium emission. Furthermore, the treatment device for the tritium-containing waste liquid provided by the embodiments of the present application has a mature process, a simple structure, convenient operation and maintenance, a high degree of automation, can operate stably for a long time, and can also operate intermittently according to actual needs. BRIEF DESCRIPTION OF THE DRAWINGS

[0016] Figure 1 The following shows a schematic structural diagram of a tritium-containing waste liquid treatment device provided by an embodiment of the present application.

[0017] In the figure, 1 is a rectifying column; 2 is a packing; 3 is a liquid transfer pump; 4 is a storage tank circulation pump; 5 is a bottom reboiler; 6 is a top condenser; 7 is a vacuum pump; 8 is a storage tank; 9 is a gas pipeline; 10 is a liquid pipeline; A is a feed inlet; B is a light component discharge port; C is a light component reflux port. Specific Embodiment

[0018] Next, the technical solutions in the embodiments of the present application will be clearly and completely described with reference to the accompanying drawings in the embodiments of the present application. Obviously, the described embodiments are only a part of the embodiments of the present application, rather than all the embodiments. Based on the embodiments in the present application, all other embodiments obtained by those of ordinary skill in the art without making creative efforts shall fall within the protection scope of the present application.

[0019] At least one embodiment of the present application provides a treatment device for tritium-containing waste liquid. Referring to Figure 1 , the treatment device for tritium-containing waste liquid includes a separation unit, a storage unit, a top condenser 6 and a vacuum pump 7. The side of the separation unit is provided with a feed inlet A, and the top of the separation unit is provided with a light component discharge port B and a light component reflux port C. The bottom of the separation unit is provided with a heavy component discharge port D. The separation unit is connected between the top condenser 6 and the storage unit, and is used for rectifying and separating the tritium-containing waste liquid entering the separation unit from the feed inlet A and the light component reflux port C into gaseous light isotope water of hydrogen and liquid heavy isotope water of hydrogen. The top condenser 6 is connected to the light component discharge port B of the separation unit, the light component reflux port C of the separation unit and the vacuum pump 7, and is used for condensing the gaseous light isotope water of hydrogen entering through the light component discharge port B to obtain light component water, and when the tritium concentration of the light component water does not meet the discharge standard, it is refluxed into the separation unit through the light component reflux port C, and when the tritium concentration of the light component water meets the discharge standard, it is discharged. The storage unit is used for storing the liquid heavy isotope water of hydrogen transmitted by the separation unit through the heavy component discharge port D, and conveying it to the feed inlet A of the separation unit after the liquid heavy isotope water of hydrogen is stored to a preset amount.

[0020] It should be noted that the tritium-containing waste liquid can be the tritium-containing waste liquid of a nuclear power plant or others, and the embodiments of the present application do not make specific limitations on this. The liquid heavy isotope water of hydrogen can also be called heavy component water or tritium-rich water. The light component water meeting the discharge standard can be called low-tritium water.

[0021] The function of the vacuum pump 7 is to create and maintain a negative pressure environment for the separation unit to optimize the separation process. The side of the vacuum pump 7 facing away from the top condenser 6 can discharge non-condensable gases.

[0022] According to the technical solution provided by the embodiments of the present application, by using a separation unit to perform rectification separation on the tritium-containing waste liquid, and using the top condenser 6 to discharge low-tritium water meeting the emission standards and returning the low-tritium water not meeting the emission standards to the separation unit, thus adopting the technical means of rectification technology to treat the tritium-containing waste liquid, the technical effect of reducing the liquid tritium emission in nuclear power plants is achieved. Compared with other tritium separation and enrichment technologies, the embodiments of the present application have the advantages of convenient steam energy, small investment, safety, simple operation and maintenance, and no generation of radioactive solid waste. In addition, the storage unit is used to store the heavy isotope water of hydrogen in the liquid phase, and after the heavy isotope water of hydrogen in the liquid phase (which can also be called tritium-rich water) is stored to a preset amount, it is transported to the feed port A of the separation unit for repeated rectification separation. Thus, the storage unit is used to store the heavy isotope water of hydrogen in the liquid phase, and the repeated rectification treatment technology of the heavy isotope water of hydrogen in the liquid phase is adopted, reducing the subsequent treatment process and device of the heavy isotope water of hydrogen in the liquid phase, and achieving the technical effect of volume reduction and storage of the tritium-containing waste liquid in nuclear power plants. In addition, compared with other technologies for treating tritium-rich water, including low-temperature rectification for tritium extraction, electrolytic enrichment for tritium extraction, electrolysis + chromatographic separation for tritium extraction, etc., the tritium-containing waste liquid treatment device provided by the embodiments of the present application does not require additional investment for the treatment of the heavy isotope water of hydrogen in the liquid phase, and has the advantages of small investment, safety (no risk of hydrogen explosion), simple operation and maintenance, and no radioactive waste, that is, reducing the investment cost, industrial risk and operation and maintenance complexity, and achieving the purpose of effective volume reduction of the tritium-containing waste liquid in nuclear power plants and reducing the liquid tritium emission. Furthermore, the tritium-containing waste liquid treatment device provided by the embodiments of the present application has a mature process, a simple structure, convenient operation and maintenance, a high degree of automation, can operate stably for a long time, and can also operate intermittently according to actual needs.

[0023] The separation unit only needs to be able to perform rectification separation on the tritium-containing waste liquid. On this basis, the specific structural composition of the separation unit is not limited in the embodiments of the present application. For example, the separation unit may include a single-stage or multi-stage rectification column 1. Below, with reference to specific embodiments, the specific structural composition of the separation unit will be illustrated by way of example.

[0024] In at least one embodiment of the present application, the separation unit includes a single-stage rectification column 1. The top of the single-stage rectification column 1 is connected with a top condenser 6 and a vacuum pump 7. The heavy component discharge port D at the bottom of the single-stage rectification column 1 is connected with the storage unit.

[0025] In at least one embodiment of the present application, the separation unit includes a liquid-phase transfer pump 3, a bottom reboiler 5, and a multi-stage distillation column 1 arranged in series. A light-component discharge port B is designed at the top of the first-stage distillation column in the multi-stage distillation column 1 and is connected to a top condenser 6 and a vacuum pump 7. A bottom reboiler 5 is connected to the heavy-component discharge port D at the bottom of the last-stage distillation column in the multi-stage distillation column 1. When the number of stages of the distillation column 1 is at least two, a gas-phase pipeline 9 and a liquid-phase pipeline 10 are connected between the top and the bottom of adjacent two-stage distillation columns 1. The liquid-phase transfer pump 3 is provided on the liquid-phase pipeline 10.

[0026] It should be noted that the separation unit may include one or more stages of distillation columns 1. The multi-stage distillation column 1 is at least a two-stage distillation column. The liquid-phase transfer pump 3 may also be referred to as a distillation column transfer pump.

[0027] In the embodiment of the present application, by designing the separation unit to be composed of cascaded multi-stage distillation columns 1, a light-component discharge port B is designed at the top of the first-stage distillation column in the multi-stage distillation column 1 and is connected to a top condenser 6 and a vacuum pump 7. After the tritium concentration of the light-component water extracted at the top condenser 6 meets the discharge standard, it is discharged. Thus, the distillation cascade process is adopted to treat the tritium-containing waste liquid in the nuclear power plant by using the principle of hydrogen isotope separation, so that while the treated low-tritium waste liquid meets the discharge requirements, the tritium specific activity of the treated low-tritium waste liquid is reduced to 0.1% - 10% of that of the tritium-containing waste liquid, that is, the liquid tritium discharge from the nuclear power plant will be reduced by 90% - 99.9%.

[0028] In at least one embodiment of the present application, the number of stages of the multi-stage distillation column 1 ranges from 2 to 10. In this way, while ensuring the distillation treatment effect, the number of distillation columns 1 is reduced.

[0029] In at least one embodiment of the present application, the tower height of the distillation column 1 ranges from 1 m to 50 m; and / or, the tower diameter of the distillation column 1 ranges from 0.05 m to 10 m; and / or, the feed rate of the distillation column 1 ranges from 0.1 kg / h to 10,000 kg / h; and / or, the reflux ratio of the distillation column 1 ranges from 1 to 500; the top pressure of the distillation column 1 ranges from 6 KPa to 100 KPa.

[0030] In at least one embodiment of the present application, the tower height of the distillation column 1 ranges from 10 m to 40 m; and / or, the tower diameter of the distillation column 1 ranges from 0.1 m to 5 m; and / or, the feed rate of the distillation column 1 ranges from 5 kg / h to 1000 kg / h; and / or, the reflux ratio of the distillation column 1 ranges from 10 KPa to 100 KPa.

[0031] In at least one embodiment of the present application, the packing 2 used in the rectification column 1 includes surface-modified phosphor bronze wire gauze structured packing, or structured packing and random packing. Thus, it is possible to decide whether to use only structured packing or a combination of structured packing and random packing in the separation unit according to actual needs. Random packing can be used in the last 1-2 stages of the rectification column in the separation unit. In this way, by setting the packing 2 used in the rectification column 1 to be metal packing, the designed service life of the treatment device is long, the packing does not need to be replaced during the service life, and no radioactive solid waste is generated during use.

[0032] The storage unit only needs to be able to store the heavy isotope water of hydrogen in liquid phase transmitted by the separation unit through the heavy component discharge port D, and deliver it to the feed port A of the separation unit after the heavy isotope water of hydrogen in liquid phase is stored to a preset amount. On this basis, the specific structural composition of the storage unit in the embodiments of the present application is not limited. Below, the specific structural composition of the storage unit will be illustrated by way of specific examples.

[0033] In at least one embodiment of the present application, the storage unit includes a storage tank circulation pump 4 and at least one storage tank 8. At least one storage tank 8 is designed in parallel and connected to one end of the storage tank circulation pump 4. The other end of the storage tank circulation pump 4 is connected to the feed port A of the separation unit. Thus, the heavy isotope water of hydrogen in liquid phase is stored in the storage tank 8, and the storage tank circulation pump 4 can deliver it to the feed port A of the separation unit after the heavy isotope water of hydrogen in liquid phase is stored to a preset amount.

[0034] It should be noted that the storage tank 8 can be a storage trough, and correspondingly, the storage tank circulation pump 4 can be a storage trough circulation pump. The storage unit can also be designed with a valve group corresponding to at least one storage tank 8.

[0035] The number of at least one storage tank 8 can be designed according to actual conditions, and the embodiments of the present application do not make specific limitations on this. For example, the storage unit can be designed to be able to store tritium-rich water for 5 to 10 years. For example, in some embodiments, the storage tank 8 adopts a double storage trough structure, and the effective volume of each storage trough is 10 to 50 tons. Since the decay period of tritium is 12.5 years, the stored tritium-rich water will decay year by year, and the specific activity of tritium will decrease accordingly; after being stored to the preset amount, the tritium-rich water is introduced into the separation unit again for rectification and concentration to further reduce the volume of the tritium-rich water. Repeated operations can ensure that the tritium-rich water is not discharged into the environment, thereby reducing the liquid tritium emission of the nuclear power plant.

[0036] Below, the specific process of treating tritium-containing waste liquid by using the tritium-containing waste liquid treatment device will be illustrated by way of specific examples.

[0037] First, the tritium-containing waste liquid enters the distillation tower 1 of the separation unit from the feed port A of the separation unit; in the distillation tower 1, the light isotope water of hydrogen rises along the tower in the gas phase, and the heavy isotope water of hydrogen flows to the bottom of the tower in the liquid phase, and enters the adjacent distillation tower 1 through the liquid phase pipeline 10 under the action of the liquid phase delivery pump 3; the gas phase isotope water enters the adjacent distillation tower 1 through the gas phase pipeline 9; in the distillation tower 1, the gas-liquid two phases are mixed, contacted and separated for many times, and heat is transferred, so that each component is obtained. to separation; the top condenser 6 of the first-stage distillation tower 1 condenses the gas phase to obtain light component water, a part of the light component water is refluxed to the distillation tower of this stage, and the other part of the light component water is extracted as low-tritium water and discharged after passing the test; the bottom reboiler 5 can heat the bottom liquid phase water of the heavy component discharge port D of the separation unit, a part of the water is vaporized and returned to the distillation tower 1 in the gas phase, and the other part of the water is extracted to obtain heavy component tritium-rich water, which is transmitted to the storage tank 8 for storage.

[0038] After a certain amount of tritium-rich water is stored in the storage unit, the tritium-rich water is transported to the feed port of the separation unit through the storage tank circulation pump 4 of the storage unit. The tritium-rich water enters the separation unit for repeated separation. The tritium-rich water after separation, concentration and volume reduction is extracted again and transported to the storage unit for storage.

[0039] Example 1 The feed concentration of tritium is 1×10 7 Bq / L of tritium-containing waste liquid, the separation unit adopts a two-stage distillation tower (tower height 36m, tower diameter set to 2.2m, feed rate set to 312kg / h, reflux ratio set to 17, tower pressure 10kpa); the light component discharge port B of the separation unit produces light component low-tritium water, and its tritium concentration is 1×10 6 Bq / L, heavy component tritium-rich water is obtained at the heavy component discharge port D, and the tritium concentration is 2×10 9 Bq / L. It operates safely and stably for 8,000 hours per year, treats a total of 2,496 tons of tritium-containing waste liquid, and stores 12 tons of tritium-enriched water. The storage tank 8 adopts a double storage tank structure, each storage tank has an effective volume of 40 tons. After the separation unit has been in operation for 6 years, the tritium-enriched water collected in the storage tank is transferred to the separation unit for repeated separation, concentration and storage.

[0040] It should be noted that the combination of the various technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments, and all technical features described in the present application can be freely combined or combined in any way unless there is a contradiction between them.

[0041] As shown in this application and the claims, unless the context clearly indicates otherwise, words such as "a" and / or "the" are not specifically singular and may also include the plural. Generally speaking, the term "comprising" only indicates the inclusion of the steps and elements that have been clearly identified, and these steps and elements do not constitute an exclusive list. The method or device may also include other steps or elements.

[0042] The above are only the preferred embodiments of this application and are not intended to limit this application. Any modifications, equivalent replacements, etc. made within the spirit and principles of this application shall be included within the protection scope of this application.

Claims

1. A device for treating tritium-containing waste liquid, characterized in that: Including separation unit, storage unit, top condenser and vacuum pump, The side of the separation unit is provided with a feed port, the top of the separation unit is provided with a light component discharge port and a light component reflux port, and the bottom of the separation unit is provided with a heavy component discharge port; The separation unit is connected between the tower top condenser and the storage unit, and is used for distilling the tritium-containing waste liquid entering the separation unit from the feed inlet and the light component reflux inlet into gas phase hydrogen light isotope water and liquid phase hydrogen heavy isotope water; The tower top condenser is connected to the light component discharge port of the separation unit, the light component reflux port of the separation unit and the vacuum pump, and is used to condense the light isotope water of hydrogen in the gas phase entering through the light component discharge port to obtain light component water, and reflux it into the separation unit through the light component reflux port after the tritium concentration of the light component water does not meet the emission standard, and discharge it after the tritium concentration of the light component water meets the emission standard; The storage unit is used to store the heavy isotope water of hydrogen in the liquid phase transmitted by the separation unit through the heavy component discharge port, and to transport the heavy isotope water of hydrogen in the liquid phase to the feed port of the separation unit after the heavy isotope water of hydrogen in the liquid phase is stored to a preset amount.

2. The device for treating tritium-containing waste liquid according to claim 1, characterized in that: The separation unit comprises a primary distillation tower, the top of which is connected with a tower top condenser and a vacuum pump, and the heavy component discharge port at the bottom of the primary distillation tower is connected with the storage unit.

3. The device for treating tritium-containing waste liquid according to claim 1, characterized in that: The separation unit includes a liquid phase delivery pump, a tower bottom reboiler and a multi-stage distillation tower arranged in series; The top of the first-stage distillation tower in the multi-stage distillation tower is designed with a light component discharge port and is connected to the top condenser and the vacuum pump; A bottom reboiler is connected to the heavy component discharge port at the bottom of the last distillation tower in the multi-stage distillation tower, and a gas phase pipeline and a liquid phase pipeline are connected between the top and the bottom of the two adjacent distillation towers, and a liquid phase delivery pump is provided on the liquid phase pipeline.

4. The device for treating tritium-containing waste liquid according to claim 3, characterized in that: The number of stages of a multi-stage distillation tower ranges from 2 to 10.

5. A device for treating tritium-containing waste liquid according to any one of claims 2 to 4, characterized in that: The tower height of the distillation tower ranges from 1m to 50m; and / or, the tower diameter of the distillation tower ranges from 0.05m to 10m; and / or, the feed amount of the distillation tower ranges from 0.1kg / h to 10000kg / h; and / or, the reflux ratio of the distillation tower ranges from 1 to 500; the top pressure of the distillation tower ranges from 6KPa to 100KPa.

6. A device for treating tritium-containing waste liquid according to any one of claims 2 to 4, characterized in that: The tower height of the distillation tower ranges from 10m to 40m; and / or, the tower diameter of the distillation tower ranges from 0.1m to 5m; and / or, the feed rate of the distillation tower ranges from 5kg / h to 1000kg / h; and / or, the reflux ratio of the distillation tower ranges from 10KPa to 100KPa.

7. A device for treating tritium-containing waste liquid according to any one of claims 2 to 4, characterized in that: The packing used in the distillation tower includes surface-modified phosphor bronze wire mesh structured packing.

8. A device for treating tritium-containing waste liquid according to any one of claims 2 to 4, characterized in that: The packings used in the distillation tower include surface-modified phosphor bronze wire mesh structured packings and random packings.

9. A device for treating tritium-containing waste liquid according to any one of claims 1 to 4, characterized in that: The storage unit comprises a storage tank circulation pump and at least one storage tank. The at least one storage tank is connected to one end of the storage tank circulation pump after being designed in parallel, and the other end of the storage tank circulation pump is connected to the feed port of the separation unit.

10. The device for treating tritium-containing waste liquid according to claim 9, characterized in that: The storage box adopts a double storage tank structure, and the effective volume of each storage tank is 10 tons to 50 tons.

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