A fluidized bed based radioactive wet waste treatment system and method

By using fluidized bed and plasma melting technologies to treat radioactive wet waste from nuclear power plants, the incremental problem of cement solidification treatment has been solved, achieving waste reduction and safe and harmless disposal, thus meeting the needs of the large-scale development of the nuclear power industry.

CN123053583APending Publication Date: 2026-11-06华能海南昌江核电有限公司
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Patent Information

Application Number
CN202611360268.5
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2026-09-03
Publication Date
2026-11-06

AI Technical Summary

Technical Problem

In existing technologies, the cement solidification treatment of radioactive wet waste from nuclear power plants has the problem of incremental growth, occupies a large storage space, has high operation and maintenance costs, and is difficult to adapt to the needs of large-scale development of the nuclear power industry, violating the principle of minimizing radioactive waste.

Method used

A fluidized bed-based treatment system is adopted, including an air preheating module, a fluidized bed module, a plasma melting module, and an exhaust gas treatment module. Through fluidized bed drying, plasma melting, and exhaust gas purification, the volume reduction treatment of radioactive wet waste is achieved.

Benefits of technology

This method achieves volume reduction treatment of radioactive wet waste, removing free water, burning organic components and melting inorganic components into glass, achieving a volume reduction ratio of 20:1, reducing radiation dose and exhaust gas pollution, and ensuring the safety and environmental friendliness of the treatment process.

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Abstract

The application relates to a fluidized bed-based radioactive wet waste treatment system and treatment method, which comprises an air preheating module, a fluidized bed module, a plasma melting module and a tail gas treatment module. The fluidized bed module comprises a fluidized bed and a collecting tank, the discharge port of the fluidized bed is connected with the feeding port of the collecting tank, the plasma melting module comprises a plasma melting furnace, a glass body formula feeding device and a glass body collecting device, the air preheating module is connected with the air inlet of the fluidized bed and the air inlet of the plasma melting furnace respectively, the discharge port of the collecting tank and the discharge port of the glass body formula feeding device are connected with the feeding port of the plasma melting furnace respectively, the glass body collecting device is connected with the discharge port of the plasma melting furnace, and the tail gas treatment module is connected with the exhaust port of the plasma melting furnace. The application removes free water of radioactive wet waste, burns organic components in the waste, melts inorganic components into glass bodies, and realizes a reduction target.
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Description

Technical Field

[0001] This invention relates to the treatment of radioactive wet waste, specifically to a fluidized bed-based radioactive wet waste treatment system and system. Background Technology

[0002] The safe disposal and reduction of radioactive wet waste (mainly waste resin and waste concentrate) generated by nuclear power plants has become a critical issue that urgently needs to be addressed in the industry. Currently, civilian nuclear power plants generally use cement solidification technology to treat radioactive wet waste. This method can fix radioactive materials and shield radiation, but it has obvious technical defects. It is an incremental treatment technology, which not only occupies a large amount of storage space and increases operation and maintenance costs, but also creates many hidden dangers for the long-term management and final disposal of waste. It is difficult to adapt to the long-term needs of the large-scale development of my country's nuclear power industry and violates the core principle of minimizing radioactive waste. Summary of the Invention

[0003] The technical problem to be solved by the present invention is to provide a fluidized bed-based radioactive wet waste treatment system and method, which realizes waste reduction treatment and reduces occupational radiation dose.

[0004] The technical solution of the present invention to solve the above-mentioned technical problems is as follows: A radioactive wet waste treatment system based on a fluidized bed includes an air preheating module, a fluidized bed module, a plasma melting module, and a tail gas treatment module. The fluidized bed module includes a fluidized bed and a collection tank. The outlet of the fluidized bed is connected to the inlet of the collection tank. The plasma melting module includes a plasma melting furnace, a glass formulation feeding device, and a glass collection device. The air preheating module is connected to the air inlet of the fluidized bed and the air inlet of the plasma melting furnace, respectively. The outlet of the collection tank and the outlet of the glass formulation feeding device are connected to the inlet of the plasma melting furnace, respectively. The glass collection device is connected to the outlet of the plasma melting furnace. The tail gas treatment module is connected to the exhaust port of the plasma melting furnace.

[0005] The beneficial effects of this invention are: the treatment system removes free water from radioactive wet waste, burns organic components in the waste, and melts inorganic components into a glassy substance. Under ideal conditions, the volume reduction ratio reaches 20:1, thus achieving the volume reduction target.

[0006] Based on the above technical solution, the present invention can be further improved as follows.

[0007] Furthermore, the collecting tank and the glass formulation feeding device are located above the plasma melting furnace, and the glass collecting device is located below the discharge port of the plasma melting furnace.

[0008] The advantages of adopting the above-mentioned further solution are that it facilitates the flow of dynamic vitreous material into the vitreous material collection device by gravity, which is energy-saving, environmentally friendly, and reduces radiation exposure.

[0009] Furthermore, the vitreous body collection device is a steel drum with a volume of 400L, and the steel drum needs to be sealed with cement.

[0010] The advantages of adopting the above-mentioned further solutions are that the vitreous body collection device has the advantage of small size, while the steel drum can provide mechanical containment, and the cement sealing forms an external protective barrier, which can delay the corrosion of the steel drum, reduce the radiation dose on the outer surface, and help ensure the safe isolation of radioactive waste.

[0011] Furthermore, the exhaust gas treatment module includes a heat exchanger, a quench tower, an alkaline scrubbing tower, a filter, and an exhaust fan connected in sequence, and the inlet of the heat exchanger is connected to the exhaust port of the plasma melting furnace.

[0012] The beneficial effects of adopting the above-mentioned further scheme are that the high-temperature exhaust gas is first cooled by a heat exchanger, and then successively subjected to rapid cooling, alkaline washing, and filtration purification to remove heat, acidic pollutants and particulate matter from the flue gas. The exhaust fan provides suction to ensure negative pressure inside the furnace, so that the qualified flue gas is discharged, realizing the staged purification of exhaust gas and preventing the leakage of harmful pollutants.

[0013] Furthermore, the heat exchanger is a plate heat exchanger, which includes a liquid side and a gas side. Cooling water circulates within the liquid side, and the gas inlet is connected to the exhaust port of the plasma melting furnace, while the gas exhaust port is connected to the quench tower.

[0014] The beneficial effects of adopting the above-mentioned further scheme are that gas-liquid heat exchange is achieved by using a plate heat exchanger, cooling water circulates on the liquid side to remove heat from the high-temperature exhaust gas, pre-cools the exhaust gas, reduces the heat load of the subsequent quench tower, recovers some heat, the equipment has high heat exchange efficiency, and reduces the working pressure of subsequent processing equipment.

[0015] Furthermore, the quench tower is equipped with a spray device inside, which is located at the top of the quench tower, while the air inlet of the quench tower is located at the bottom of the quench tower.

[0016] The beneficial effect of adopting the above-mentioned further scheme is that the exhaust gas is sent into the quench tower from bottom to top in a countercurrent manner, and comes into countercurrent contact with the condensate sprayed by the spray device, which ensures sufficient heat exchange and good cooling effect.

[0017] In addition to addressing the aforementioned technical problems, the present invention provides the following technical solution: a method for treating radioactive wet waste based on a fluidized bed, executed by the treatment system described above, comprising the following steps: Step S1: In the fluidized bed, the radioactive wet waste is suspended and pulverized by hot air to form dry salts, which are then collected in a collection tank. Step S2: The collection tank sends the dried salt into the plasma melting furnace, and the glass formula feeding device adds glass formula into the plasma melting furnace. Under the hot air atmosphere, the dried salt and glass formula form a fluid glass in the plasma melting furnace in proportion, and the glass collection device collects the fluid glass. Step S3: The exhaust gas generated by the plasma melting furnace is discharged after being cooled, alkali washed and filtered in sequence.

[0018] The beneficial effects of this invention are as follows: First, radioactive wet waste is suspended, pulverized, and dried in a fluidized bed using hot air to obtain dried salts, which are then melted with glass formulation materials at high temperature to form a glass body, thus achieving stable solidification of radioactive nuclides; the exhaust gas is cooled, alkali-washed, and filtered before being discharged, taking into account both waste volume reduction and solidification and harmless treatment of exhaust gas, ensuring radiation safety during the treatment process. Furthermore, in step S2, the weight ratio of dried salt to glass formulation material is 2:1.

[0019] The beneficial effect of adopting the above-mentioned further scheme is that the ratio can ensure that the dry salt and glass formulation are fully melted to form a structurally stable glass body, which can effectively seal radionuclides, avoid unnecessary volume increase caused by excessive formulation, and balance the curing effect and minimize waste.

[0020] Furthermore, in step S3, the exhaust gas is first cooled to 235℃~245℃ through a gradient process, then cooled to 55℃~65℃ through alkaline washing, and finally discharged after filtration.

[0021] The beneficial effects of adopting the above-mentioned further scheme are that gradient cooling can avoid the temperature range in which harmful substances are generated and reduce the generation of secondary pollutants; further cooling and removal of acidic gases by alkaline washing, followed by filtration to remove particulate matter, ensure that the exhaust gas meets emission standards.

[0022] Furthermore, in step S2, the fluid dynamic glass flows into the glass collection device by gravity and is sealed and fixed by cement.

[0023] The advantages of adopting the above-mentioned further solutions are that gravity is used to achieve gravity-fed collection of the vitreous body, eliminating the need for additional conveying equipment and simplifying the process; and the cement encapsulation creates multiple barriers to inhibit radionuclide leaching, thereby improving the mechanical strength of the waste package and the safety of long-term storage and disposal. Attached Figure Description

[0024] Figure 1 This is a schematic diagram of a fluidized bed-based radioactive wet waste treatment system according to the present invention.

[0025] The attached diagram lists the components represented by each number as follows: 1. Air preheating and air inlet device; 21. Fluidized bed; 22. Collection tank; 23. First transfer pump; 24. Second transfer pump; 31. Plasma melting furnace; 32. Glass formulation feeding device; 33. Glass collection device; 41. Heat exchanger; 42. Quenching tower; 43. Alkali washing tower; 44. Filter; 45. Exhaust fan; 6. Chimney. Detailed Implementation

[0026] The principles and features of the present invention are described below. The examples given are only for explaining the present invention and are not intended to limit the scope of the present invention.

[0027] Example 1 This embodiment provides a fluidized bed-based radioactive wet waste treatment system, including an air preheating module, a fluidized bed module, a plasma melting module, and a tail gas treatment module. The fluidized bed module includes a fluidized bed 21 and a collection tank 22, with the outlet of the fluidized bed 21 connected to the inlet of the collection tank 22. The plasma melting module includes a plasma melting furnace 31, a glass formulation feeding device 32, and a glass collection device 33. The air preheating module is connected to the air inlet of the fluidized bed 21 and the air inlet of the plasma melting furnace 31, respectively. The outlets of the collection tank 22 and the glass formulation feeding device 32 are connected to the inlet of the plasma melting furnace 31, respectively. The glass collection device 33 is connected to the outlet of the plasma melting furnace 31. The tail gas treatment module is connected to the exhaust port of the plasma melting furnace 31.

[0028] In this embodiment, the treatment system removes the free water from the radioactive wet waste, burns the organic components in the waste, and melts the inorganic components into a glassy substance. Ideally, the volume reduction ratio reaches 20:1, thus achieving the volume reduction target.

[0029] Specifically, in this embodiment, the air preheating module includes an air preheating air inlet device 1, i.e., an air preheater. The air preheating air inlet device 1 is equipped with an electric heating wire. The air preheating air inlet device 1 heats the air and sends it into the fluidized bed module and the plasma melting module. The temperature of the hot air sent in by the air preheating air inlet device 1 is adjusted according to the actual application. The role of the preheated air in the fluidized bed module is to dry and supply air, and in the plasma melting module, it is used to provide air to ensure complete combustion.

[0030] The fluidized bed module includes a fluidized bed 21 and a collection tank 22. The fluidized bed 21 utilizes existing technology. Its inlet receives transported radioactive wet waste, and its outlet is connected to the inlet of the collection tank 22. The outlet of an air preheating inlet device 1 is connected to the inlet of the fluidized bed 21, allowing it to deliver hot air. The radioactive wet waste is blown up, boils, and is suspended and pulverized, forming dried salts which are then temporarily stored in the collection tank 22. Steam generated during the drying process enters a condenser at the top of the fluidized bed 21, condenses into water, and is then discharged. In this embodiment, a first transfer pump 23 is installed on the pipeline transporting the radioactive wet waste. A second transfer pump 24 is installed on the pipeline connecting the fluidized bed 21 and the collection tank 22, pumping the dried salts into the collection tank 22.

[0031] The plasma melting module includes a plasma melting furnace 31, a glass formula feeding device 32, and a glass collection device 33. The plasma melting furnace 31 can be equipped with a nitrogen plasma cabinet, which does not use natural gas, thus saving fossil fuels and increasing the core temperature of the furnace body to ensure melting. The inlet of the plasma melting furnace 31 is connected to the outlet of the collection tank 22 and the outlet of the glass formula feeding device 32, respectively, so that the dry salt temporarily stored in the collection tank 22 and the glass formula material in the glass formula feeding device 32 are fed into the plasma melting furnace 31 in a certain proportion. The air inlet of the plasma melting furnace 31 is connected to the air preheating air inlet device 1 to receive heated air, so that the dry salt can be fully combusted in an aerobic environment. The exhaust gas generated by combustion is sent to the exhaust gas treatment module for treatment through the exhaust port of the plasma melting furnace 31 before being discharged.

[0032] In this embodiment, both the fluidized bed 21 and the plasma melting furnace 31 are constructed using heat-resistant and wear-resistant crucibles, with a steel lining added to the crucible to increase the strength of the fluidized bed 21.

[0033] Preferred, such as Figure 1 As shown, the collection tank 22 and the glass formulation feeding device 32 are located above the plasma melting furnace 31, and the glass collection device 33 is located below the discharge port of the plasma melting furnace 31. This allows the flowing glass to be discharged into the glass collection device 33 by gravity, saving energy, protecting the environment, and reducing radiation exposure.

[0034] Specifically, in this embodiment, the glass formulation material can be selected from existing technologies, and its components are generally SiO2 (quartz sand), B2O3 (borax / boric acid), Al2O3, CaO, Na2O, etc., which are premixed powders or granules according to the formulation.

[0035] The vitreous body collection device 33 is a 400L steel drum, which must be sealed with cement. In this way, the vitreous body collection device 33 has the advantage of small size. At the same time, the steel drum provides mechanical containment, while the cement sealing forms an external protective barrier, which can delay the corrosion of the steel drum, reduce the radiation dose on the outer surface, and help ensure the safe isolation of radioactive waste.

[0036] Specifically, the exhaust gas treatment module includes a heat exchanger 41, a quench tower 42, an alkaline scrubbing tower 43, a filter 44, and an exhaust fan 45 connected in sequence. The inlet of the heat exchanger 41 is connected to the exhaust port of the plasma melting furnace 31. Thus, the high-temperature exhaust gas is first cooled by the heat exchanger 41, and then sequentially quenched, scrubbed, and filtered to remove heat, acidic pollutants, and particulate matter from the flue gas. The exhaust fan 45 provides suction to maintain negative pressure inside the furnace, ensuring that the qualified flue gas is discharged, achieving staged purification of the exhaust gas and preventing the leakage of harmful pollutants.

[0037] The exhaust gas is first cooled in heat exchanger 41 through a partitioned heat exchange, typically reducing the exhaust gas temperature from 900°C to 600°C. It is then sent to quench tower 42 for a second cooling, reducing the exhaust gas temperature from 600°C to 240°C. After two cooling cycles, the exhaust gas is further cooled in alkaline scrubbing tower 43 to remove acidic substances, typically reducing the exhaust gas temperature to 60°C. Finally, it passes through filter 44 to adsorb residues and harmful gases before being sent to chimney 6 by exhaust fan 45. Preferably, chimney 6 can be equipped with a gamma radiation monitoring device and a multi-gas concentration monitoring device. If an abnormality in radioactivity or an excessive concentration of harmful gases is detected, exhaust fan 45 will be shut down to prevent pollutants from leaking out.

[0038] In this embodiment, the heat exchanger 41 is a plate heat exchanger, comprising a liquid side and a gas side. Cooling water circulates within the liquid side, and the gas inlet is connected to the exhaust port of the plasma melting furnace 31, while the gas exhaust port is connected to the quench tower 42. Thus, gas-liquid heat exchange is achieved using the plate heat exchanger. The cooling water circulates on the liquid side, carrying away heat from the high-temperature exhaust gas, pre-cooling the exhaust gas, reducing the heat load on the subsequent quench tower 42, and recovering some heat. The equipment has high heat exchange efficiency, reducing the working pressure on subsequent processing equipment.

[0039] The quench tower 42 is equipped with a spray device inside. The quench tower 42 and the spray device can be selected from existing devices. The spray device is located at the top of the quench tower 42, and the air inlet of the quench tower 42 is located at the bottom of the quench tower 42. The exhaust gas is sent into the quench tower 42 from bottom to top in a countercurrent manner, and comes into countercurrent contact with the condensate sprayed by the spray device, which ensures sufficient heat exchange and good cooling effect.

[0040] The bottom of the quench tower 42 is also equipped with a water outlet. The cooling water sprayed by the spraying device is drawn out from the bottom, cooled by the external cooler, and then sent back to the spraying device to achieve recycling and save resources.

[0041] Alkali scrubbing tower 43 can be made using existing technology. Alkali scrubbing tower 43 stores a certain amount of sodium hydroxide solution, which neutralizes acidic substances such as nitrogen oxides in the tail gas and further cools it down.

[0042] The filter 44 includes a pre-filter 44, an adsorber, and a post-filter 44. The adsorbent of the adsorber is activated carbon. Preferably, a demister is also provided between the filter 44 and the alkaline washing tower 43. The demister can be a wire mesh demister, which removes small droplets mixed in the exhaust gas to avoid affecting the filtration effect of the filter 44.

[0043] Example 2 This embodiment provides a method for treating radioactive wet waste based on a fluidized bed, executed by the treatment system provided in Embodiment 1, and includes the following steps: Step S1: In the fluidized bed 21, the radioactive wet waste is suspended and pulverized by the hot air supplied to form dry salts, which are then collected by the collection tank 22. Step S2: The collection tank 22 sends the dried salt into the plasma melting furnace 31, and the glass formula feeding device 32 adds glass formula into the plasma melting furnace 31. Under the hot air atmosphere, the dried salt and glass formula melt in the plasma melting furnace 31 in proportion and the flowing glass is collected. Step S3: The exhaust gas generated by the plasma melting furnace 31 is discharged after being cooled, alkali washed and filtered in sequence.

[0044] In this embodiment, the radioactive wet waste is first suspended, pulverized, and dried in a fluidized bed 21 using hot air to obtain dried salts, which are then melted with glass formulation materials at high temperature to form a glass body, thereby achieving stable solidification of radionuclides. The exhaust gas is cooled, alkali-washed, and filtered for purification before being discharged, taking into account both waste volume reduction and solidification and harmless treatment of exhaust gas, ensuring radiation safety during the treatment process. Furthermore, in step S2, the weight ratio of the dried salt to the glass formulation is 2:1. This ratio ensures that the dried salt and the glass formulation are fully melted to form a structurally stable glass body, achieving effective encapsulation of radioactive nuclides while avoiding unnecessary volume increase caused by excessive formulation material, thus balancing curing effect and waste minimization.

[0045] In another embodiment, the dried salt and glass formulation are added according to a procedure, and the weight ratio of the dried salt to the glass formulation can be adjusted according to the actual situation.

[0046] Furthermore, in step S3, the exhaust gas is first cooled to 235℃~245℃ via a gradient cooling process, then cooled to 55℃~65℃ via alkaline washing, and finally filtered before being discharged. In this way, the gradient cooling process avoids the temperature range where harmful substances are generated, reducing the generation of secondary pollutants; the alkaline washing further cools and removes acidic gases, and the subsequent filtration removes particulate matter, ensuring that the exhaust gas meets emission standards.

[0047] In this embodiment, the exhaust gas undergoes gradient cooling in the heat exchanger 41 and quench tower 42 of the exhaust gas treatment module, and the alkaline scrubbing tower 43 completes alkaline scrubbing and cooling. Specifically, the exhaust gas undergoes the first cooling in the heat exchanger 41, with the exhaust gas temperature decreasing from 900°C to 600°C. Subsequently, the exhaust gas is cooled to 235°C to 245°C in the quench tower 42, and then alkaline scrubbing to remove acidic substances is completed in the alkaline scrubbing tower 43, with the exhaust gas temperature decreasing to 55°C to 65°C.

[0048] Furthermore, in step S2, the flowing vitreous flows into the vitreous collection device 33 by gravity and is then sealed and fixed with cement. Thus, gravity-driven collection of the vitreous eliminates the need for additional conveying equipment, simplifying the process. The cement sealing then creates multiple barriers, inhibiting radionuclide leaching and improving the mechanical strength of the waste package and the safety of long-term storage and disposal.

[0049] In the description of this invention, it should be understood that the terms "center," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing this invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0050] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0051] In this invention, unless otherwise explicitly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise explicitly limited. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.

[0052] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above," "over," and "on top" of the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.

[0053] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., refer to specific features, structures, materials, or characteristics described in connection with that embodiment or example, which are included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.

[0054] Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention. Those skilled in the art can make changes, modifications, substitutions and variations to the above embodiments within the scope of the present invention.

Claims

1. A fluidized bed-based radioactive wet waste treatment system, characterized in that, The system includes an air preheating module, a fluidized bed module, a plasma melting module, and a tail gas treatment module. The fluidized bed module includes a fluidized bed (21) and a collection tank (22). The outlet of the fluidized bed (21) is connected to the inlet of the collection tank (22). The plasma melting module includes a plasma melting furnace (31), a glass formulation feeding device (32), and a glass collection device (33). The air preheating module is connected to the air inlet of the fluidized bed (21) and the air inlet of the plasma melting furnace (31). The outlet of the collection tank (22) and the outlet of the glass formulation feeding device (32) are connected to the inlet of the plasma melting furnace (31). The glass collection device (33) is connected to the outlet of the plasma melting furnace (31). The tail gas treatment module is connected to the exhaust port of the plasma melting furnace (31).

2. The fluidized bed-based radioactive wet waste treatment system according to claim 1, characterized in that, The collection tank (22) and the glass formulation feeding device (32) are located above the plasma melting furnace (31), and the glass collection device (33) is located below the discharge port of the plasma melting furnace (31).

3. The fluidized bed-based radioactive wet waste treatment system according to claim 2, characterized in that, The vitreous body collection device (33) is a steel drum with a volume of 400L, and the steel drum needs to be sealed with cement.

4. The fluidized bed-based radioactive wet waste treatment system according to claim 1, characterized in that, The exhaust gas treatment module includes a heat exchanger (41), a quench tower (42), an alkaline scrubbing tower (43), a filter (44), and an exhaust fan (45) connected in sequence. The inlet of the heat exchanger (41) is connected to the exhaust port of the plasma melting furnace (31).

5. The fluidized bed-based radioactive wet waste treatment system according to claim 4, characterized in that, The heat exchanger (41) is a plate heat exchanger, which includes a liquid side and a gas side. Cooling water circulates in the liquid side. The gas inlet is connected to the exhaust port of the plasma melting furnace (31), and the exhaust port of the gas side is connected to the quench tower (42).

6. The fluidized bed-based radioactive wet waste treatment system according to claim 4, characterized in that, The quench tower (42) is equipped with a spray device inside, which is located at the top of the quench tower (42), and the air inlet of the quench tower (42) is located at the bottom of the quench tower (42).

7. A method for treating radioactive wet waste based on a fluidized bed, characterized in that, Performed by the processing system as described in any one of claims 1-6, the process includes the following steps: Step S1: In the fluidized bed (21), the radioactive wet waste is suspended and pulverized by the hot air supplied to form dry salts, which are collected by the collection tank (22); Step S2: The collection tank (22) sends the dried salt into the plasma melting furnace (31), and the glass formula feeding device (32) adds the glass formula into the plasma melting furnace (31). Under the hot air atmosphere, the dried salt and the glass formula melt in the plasma melting furnace (31) in proportion to form a fluid glass body. The glass body collection device (33) collects the fluid glass body. Step S3: The exhaust gas generated by the plasma melting furnace (31) is discharged after being cooled, alkali washed and filtered in sequence.

8. The method for treating radioactive wet waste based on a fluidized bed according to claim 7, characterized in that, In step S2, the weight ratio of dried salt to glass formulation material is 2:

1.

9. The method for treating radioactive wet waste based on a fluidized bed according to claim 7, characterized in that, In step S3, the exhaust gas is first cooled to 235℃~245℃ through a gradient process, then cooled to 55℃~65℃ through alkaline washing, and finally discharged after filtration.

10. The method for treating radioactive wet waste based on a fluidized bed according to claim 7, characterized in that, In step S2, the fluid dynamic glass flows into the glass collection device (33) by gravity and is sealed and fixed by cement.