Nuclear power plant radioactive waste treatment facilities

Abstract

This utility model discloses a radioactive waste liquid treatment device for nuclear power plants, comprising, in sequence, a raw waste liquid inlet pipeline, a carrier mixing assembly, a mixed waste liquid inlet pipeline, a precipitation treatment assembly, a precipitated waste liquid inlet pipeline, a precipitation filtration device, and a waste liquid discharge pipeline. A waste liquid return pipeline connects the carrier mixing assembly and the waste liquid discharge pipeline. The precipitation treatment assembly includes a precipitation tank, a precipitant addition device, and a pH adjustment device. The precipitant addition device adds a precipitant (barium sulfide) to the precipitation tank, and the pH adjustment device adds a pH adjuster to adjust the pH value of the waste liquid in the precipitation tank. This radioactive waste liquid treatment device for nuclear power plants improves the removal rate of various radioactive ions and total radioactivity, and eliminates the need for personnel contact with the radioactive waste liquid.

Description

Technical Field

[0001] This utility model relates to the field of radioactive waste liquid treatment technology in nuclear power plants, and in particular to a radioactive waste liquid treatment device for nuclear power plants. Background Technology

[0002] Low-to-medium radioactive waste liquids are generally treated using resin ion exchange adsorption and in-tank evaporation drying, but these processes are costly and energy-intensive. Traditional chemical precipitation methods, due to their limited technical capabilities, often fail to achieve the required removal efficiency for radioactive ions and are therefore rarely used in practice, mostly serving as supplementary methods to other treatment processes. Utility Model Content

[0003] The technical problem to be solved by this utility model is to provide a device for treating radioactive waste liquid from nuclear power plants.

[0004] The technical solution adopted by this utility model to solve its technical problem is: to construct a radioactive waste liquid treatment device for nuclear power plants, which includes a raw waste liquid inlet pipeline, a carrier mixing component, a mixed waste liquid inlet pipeline, a sedimentation treatment component, a sedimentation waste liquid inlet pipeline, a sedimentation filtration device, and a waste liquid discharge pipeline connected in sequence, wherein a waste liquid return pipeline is connected between the carrier mixing component and the waste liquid discharge pipeline.

[0005] The precipitation treatment assembly includes a precipitation tank, a precipitant adding device, and a pH adjusting device. The precipitant adding device is used to add a precipitant, which is barium sulfide, to the precipitation tank. The pH adjusting device is used to add a pH adjusting agent to adjust the pH value of the waste liquid in the precipitation tank.

[0006] In some embodiments, the carrier mixing assembly includes a carrier mixing tank, a carrier stirrer, and a carrier adding device, wherein the carrier stirrer and the carrier adding device are both connected to the carrier mixing tank.

[0007] In some embodiments, the sedimentation tank is connected to a sedimentation agitator.

[0008] In some embodiments, the sedimentation tank is connected to a pH detection device.

[0009] In some embodiments, a raw waste liquid inlet control valve is provided on the raw waste liquid inlet pipeline.

[0010] In some embodiments, a mixed waste liquid inlet control valve is provided on the mixed waste liquid inlet pipeline.

[0011] In some embodiments, a precipitated waste liquid inlet control valve is provided on the precipitated waste liquid inlet pipeline.

[0012] In some embodiments, the waste liquid discharge pipeline is equipped with a radioactivity detection device.

[0013] In some embodiments, a waste liquid discharge control valve is provided on the waste liquid discharge pipeline.

[0014] In some embodiments, a waste liquid return control valve is provided on the waste liquid return pipeline.

[0015] The following are the beneficial effects of implementing this utility model: This nuclear power plant radioactive waste treatment device is a fully automated chemical co-precipitation method for treating low- and intermediate-level radioactive waste. The radioactive waste is mixed with a carrier containing a stable isotope, then transported to the precipitation treatment component. Barium sulfide is added as a precipitant to the precipitation tank, and the pH is adjusted to 7 using a pH adjustment device, allowing sulfide ions to fully precipitate the mixture of carrier and radioactive ions. The fully precipitated solid-liquid mixture is then filtered through a precipitation filtration device, and the qualified waste is discharged through a waste discharge pipeline. The entire process is fully automated with monitoring. If the treated waste does not meet discharge requirements, it is returned to the carrier mixing component for recirculation until the requirements are met. This nuclear power plant radioactive waste treatment device improves the removal rate of various radioactive ions and total radioactivity, and eliminates the need for personnel contact with the radioactive waste. Attached Figure Description

[0016] To more clearly illustrate the technical solution of this utility model, the present utility model will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show some embodiments of this utility model and should not be considered as a limitation of the scope. For those skilled in the art, other related drawings can be obtained from these drawings without creative effort. In the drawings:

[0017] Figure 1 This is a schematic diagram of the overall structure of a nuclear power plant radioactive waste liquid treatment device in some embodiments of this utility model. Detailed Implementation

[0018] To provide a clearer understanding of the technical features, objectives, and effects of this utility model, the specific embodiments of this utility model are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "upper," "lower," "left," "right," "longitudinal," "horizontal," "vertical," "horizontal," "top," "bottom," "inner," "outer," "head," and "tail" are based on the orientations or positional relationships shown in the accompanying drawings, and are constructed and operated in a specific orientation. They are only for the convenience of describing this technical solution and do not indicate that the device or component referred to must have a specific orientation; therefore, they should not be construed as limitations on this utility model.

[0019] It should also be noted that, unless otherwise explicitly specified and limited, terms such as "installation," "connection," "joining," "fixing," and "setting" 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. When an component is referred to as being "on" or "below" another component, the component can be located "directly" or "indirectly" on the other component, or there may be one or more intermediary components. The terms "first," "second," "third," etc., are only for the convenience of describing this technical solution and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Therefore, features defined with "first," "second," "third," etc., may explicitly or implicitly include one or more of that feature. For those skilled in the art, the specific meaning of the above terms in this utility model can be understood according to the specific circumstances.

[0020] Reference Figure 1 This invention relates to a radioactive waste liquid treatment device for nuclear power plants, comprising, in sequence, a raw waste liquid inlet pipeline 1, a carrier mixing assembly 2, a mixed waste liquid inlet pipeline 3, a sedimentation treatment assembly 4, a sedimentation waste liquid inlet pipeline 5, a sedimentation filtration device 6, and a waste liquid discharge pipeline 7. A waste liquid return pipeline 8 connects the carrier mixing assembly 2 and the waste liquid discharge pipeline 7. The sedimentation treatment assembly 4 includes a sedimentation tank 41, a precipitant adding device 42, and a pH adjustment device 43. The precipitant adding device 42 is used to add a precipitant, specifically barium sulfide, to the sedimentation tank 41. The pH adjustment device 43 is used to add a pH adjuster to adjust the pH value of the waste liquid in the sedimentation tank 41.

[0021] Specifically, the purpose of this invention is to provide a fully automated chemical co-precipitation device for treating low- and intermediate-level radioactive waste liquid. The radioactive waste liquid is mixed with a carrier containing a stable isotope in a carrier mixing component 2, and then transported to a precipitation treatment component 4. Barium sulfide, the precipitant, is added to a precipitation tank 41, and the pH is adjusted to 7 by a pH adjustment device 43, allowing the sulfur ions to fully precipitate the mixture of carrier and radioactive ions. The fully precipitated solid-liquid mixture is then filtered through a precipitation filtration device 6, and the qualified waste liquid is discharged through a waste liquid discharge pipeline 7. The entire process is fully automated with monitoring. If the treated waste liquid does not meet discharge requirements, it is returned to the carrier mixing component 2 for recirculation until the requirements are met. This nuclear power plant radioactive waste liquid treatment device improves the removal rate of various radioactive ions and total radioactivity, and eliminates the need for personnel contact with the radioactive waste liquid. More specifically, using barium sulfide as the precipitant, a 30-minute reaction at pH 7 effectively precipitates radioactive ions and the carrier together, especially in low- and intermediate-level radioactive waste liquids. 60 Co、 58 Co、 54 Mn, 137 Cs、 110m Ag and other major radioactive ions have excellent cleaning effects.

[0022] The carrier mixing assembly 2 includes a carrier mixing tank 21, a carrier stirrer 22, and a carrier adding device 23, both of which are connected to the carrier mixing tank 21. An appropriate amount of carrier corresponding to a stable isotope of radioactive ions can be added via the carrier adding device 23, while the carrier stirrer 22 is simultaneously activated to ensure complete and uniform mixing of the carrier and the waste liquid.

[0023] The sedimentation tank 41 is connected to a sedimentation agitator 44 to agitate the mixed waste liquid in the sedimentation tank 41, and the sedimentation tank 41 is connected to a pH detection device 45 to detect the pH value of the mixed waste liquid in the sedimentation tank 41.

[0024] A raw waste liquid inlet control valve 11 is installed on the raw waste liquid inlet pipeline 1 to control the flow of raw waste liquid into the carrier mixing tank 21. A mixed waste liquid inlet control valve 31 is installed on the mixed waste liquid inlet pipeline 3 to control the flow of mixed waste liquid into the sedimentation tank 41. A sedimentation waste liquid inlet control valve 51 is installed on the sedimentation waste liquid inlet pipeline 5 to control the flow of sedimentation waste liquid into the radioactive detection device 71 described below.

[0025] In addition, a radioactive detection device 71 is installed on the waste liquid discharge pipeline 7 to detect the waste liquid treated by the sedimentation tank 41. A waste liquid discharge control valve 72 is installed on the waste liquid discharge pipeline 7 to control the discharge of waste liquid. A waste liquid return control valve 81 is installed on the waste liquid return pipeline 8 to control the return of waste liquid to the carrier mixing tank 21. The connection point of the waste liquid return pipeline 8 is located between the radioactive detection device 71 and the waste liquid discharge control valve 72.

[0026] The specific working principle of the radioactive waste liquid treatment device of the nuclear power plant is as follows: The radioactive waste liquid to be treated enters the carrier mixing tank 21 through the original waste liquid inlet pipeline 1. When the liquid level of the carrier mixing tank 21 reaches 80% of its volume, the original waste liquid inlet control valve 11 is closed. An appropriate amount of carrier corresponding to the radioactive ion stable isotope is added through the carrier adding device 23, and the carrier agitator 22 is turned on and stirred for 30 minutes to ensure that the carrier and waste liquid are completely and uniformly mixed. The mixed waste liquid inlet control valve 31 is opened to transport the mixed waste liquid to the sedimentation tank 41. After all the waste liquid has been transported, the mixed waste liquid inlet control valve 31 is closed. The sedimentation agitator 44 is turned on, and an appropriate amount of barium sulfide precipitant is added through the precipitant adding device 42. A pH adjusting agent is added through the pH adjusting device 43, and the pH detection device 45 monitors the pH of the waste liquid in real time. When the pH is adjusted to about 7, the pH adjusting device 43 is stopped. After stirring in the sedimentation agitator 44 for 30 minutes, the sedimentation waste liquid inlet control valve 51 is opened, and the radioactive precipitate in the sedimentation waste liquid is filtered and collected through the sedimentation filtration device 6. The treated waste liquid is tested by the radioactivity detection device 71. If the total activity concentration of the waste liquid is less than 1000 Bq / L, the waste liquid discharge control valve 72 is opened to discharge the qualified waste liquid. If the total activity concentration of the waste liquid is greater than or equal to 1000 Bq / L, the waste liquid return control valve 81 is opened to return the untreated waste liquid to the carrier mixing tank 21 for recycling until the total activity concentration of the waste liquid is less than 1000 Bq / L before discharge. Then the original waste liquid inlet control valve 11 is opened to start the treatment of a new batch of radioactive waste liquid to be treated.

[0027] It is understood that the above embodiments only illustrate preferred embodiments of the present utility model, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present utility model patent. It should be noted that for those skilled in the art, the above technical features can be freely combined, and several modifications and improvements can be made without departing from the concept of the present utility model, all of which fall within the protection scope of the present utility model. Therefore, all equivalent transformations and modifications made within the scope of the claims of the present utility model should fall within the coverage of the claims of the present utility model.

Claims

1. A device for treating radioactive waste liquid from a nuclear power plant, characterized in that, The system includes a raw waste liquid inlet pipeline (1), a carrier mixing assembly (2), a mixed waste liquid inlet pipeline (3), a sedimentation treatment assembly (4), a sedimentation waste liquid inlet pipeline (5), a sedimentation filtration device (6), and a waste liquid discharge pipeline (7) connected in sequence. A waste liquid return pipeline (8) is connected between the carrier mixing assembly (2) and the waste liquid discharge pipeline (7). The precipitation treatment component (4) includes a precipitation tank (41), a precipitant adding device (42), and a pH adjusting device (43). The precipitant adding device (42) is used to add a precipitant to the precipitation tank (41), and the precipitant is barium sulfide. The pH adjusting device (43) is used to add a pH adjusting agent to adjust the pH value of the waste liquid in the precipitation tank (41).

2. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The carrier mixing assembly (2) includes a carrier mixing tank (21), a carrier stirrer (22), and a carrier adding device (23), wherein the carrier stirrer (22) and the carrier adding device (23) are both connected to the carrier mixing tank (21).

3. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The sedimentation tank (41) is connected to a sedimentation agitator (44).

4. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The sedimentation tank (41) is connected to a pH detection device (45).

5. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The original waste liquid inlet pipeline (1) is equipped with an original waste liquid inlet control valve (11).

6. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The mixed waste liquid inlet pipeline (3) is equipped with a mixed waste liquid inlet control valve (31).

7. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The precipitated waste liquid inlet pipeline (5) is equipped with a precipitated waste liquid inlet control valve (51).

8. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The waste liquid discharge pipeline (7) is equipped with a radioactive detection device (71).

9. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, Waste liquid discharge control valve (72) is installed on the waste liquid discharge pipeline (7).

10. The nuclear power plant radioactive waste treatment device according to claim 1, characterized in that, The waste liquid return pipeline (8) is equipped with a waste liquid return control valve (81).

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