Treatment method of uranium-containing wastewater

Abstract

The invention discloses a uranium-containing wastewater treatment method which comprises the following steps: adsorbing uranium ions through an ion exchange tower, desorbing adsorbent resin to obtain a uranium concentrated solution, and precipitating to obtain a uranium-containing recycled material, so that harmful substances in wastewater are removed, optimal utilization of water resources is realized, separated uranium is recycled, pollution is reduced, and the uranium-containing wastewater treatment method is suitable for industrial production. And energy is saved, and the dual purposes of uranium resource recycling and environmental protection are achieved. According to the main technical scheme, the method comprises the steps that uranium-containing wastewater to be treated is pretreated, and target clear liquid is obtained; the target clear liquid is input into an ion exchange tower, and uranium ions are adsorbed through adsorption resin; desorbing the adsorption resin to obtain a uranium concentrated solution; and precipitating the uranium concentrated solution to obtain a uranium-containing recycled material. The method is mainly used for industrial wastewater treatment.

Description

Technical Field

[0001] The present invention relates to the technical field of industrial wastewater treatment, in particular to a method for treating uranium-containing wastewater. Background Art

[0002] The mining process of iron-uranium co-existing mines produces large amounts of industrial wastewater containing uranium. Traditional wastewater treatment methods primarily focus on removing harmful substances from wastewater to meet environmental emission standards, while paying insufficient attention to the recovery and utilization of uranium resources. However, as a vital nuclear energy resource, uranium has extremely high economic value and strategic significance. Enriching uranium from wastewater not only reduces radioactive contamination but also achieves efficient resource utilization, achieving both environmental and economic benefits.

[0003] In recent years, with the gradual strengthening of my country's oversight of the development and utilization of associated radioactive mineral resources, and the continuous improvement of relevant regulations and technical specifications, higher requirements have been placed on the treatment of uranium-containing wastewater and the recovery of uranium resources. Existing wastewater treatment technologies, such as lime neutralization and membrane separation, can partially remove uranium from wastewater, but they suffer from high treatment costs, large amounts of secondary waste generated, and low treatment efficiency, and they fail to fully tap the resource value of uranium. Therefore, developing a new technology that can both efficiently treat uranium-containing wastewater and effectively recover uranium resources is crucial to addressing the environmental and resource challenges associated with the development and utilization of associated radioactive mineral resources. Summary of the Invention

[0004] In view of this, in order to solve at least one of the above technical problems, an embodiment of the present invention provides a method for treating uranium-containing wastewater to solve the problem that uranium-containing wastewater cannot meet environmental emission standards and uranium resources are wasted.

[0005] To achieve the above objectives, the present invention mainly provides the following technical solutions:

[0006] The embodiment of the present invention provides a method for treating uranium-containing wastewater, which is used in a deep resource treatment system for uranium-containing wastewater from iron-uranium associated ores. The system includes an ion exchange tower, in which an adsorption resin is provided;

[0007] Methods include:

[0008] Pre-treating the uranium-containing wastewater to be treated to obtain a target clear liquid;

[0009] The target clear solution is fed into the ion exchange tower, and the adsorption resin adsorbs the uranium ions;

[0010] Desorbing the adsorption resin to obtain uranium concentrate;

[0011] The uranium concentrate is precipitated to obtain uranium-containing recovered material.

[0012] The step of pre-treating the uranium-containing wastewater to be treated to obtain the target clear liquid includes:

[0013] Adding a coagulant to the uranium-containing wastewater to be treated, backwashing the uranium-containing wastewater after the addition of the coagulant, and then discharging the settled sludge to obtain the target clear liquid;

[0014] Recycle the discharged sludge.

[0015] Wherein, the coagulant includes a mixture of polyaluminium chloride and polyacrylamide.

[0016] The system further includes a water purification device, which includes filter media. The steps of pre-treating the uranium-containing wastewater to be treated to obtain the target clear liquid include:

[0017] The particulate matter in the uranium-containing wastewater to be treated is separated by the filter material of the water purification equipment to obtain the target clear liquid;

[0018] The water purification equipment is desludged at preset intervals.

[0019] The method further comprises the following steps: feeding the target clear liquid into an ion exchange tower and allowing the adsorption resin to adsorb uranium ions.

[0020] The uranium content of the clear liquid to be determined after uranium ion adsorption is tested. When the uranium content is lower than a first preset value, the clear liquid is discharged. When the uranium content is not lower than the first preset value, the clear liquid to be determined is re-input into the ion exchange tower as the target clear liquid.

[0021] Among them, the number of ion exchange towers is not less than three, and the ion exchange towers are connected in series.

[0022] The target clear liquid is fed into an ion exchange tower, and the adsorption resin adsorbs uranium ions, comprising:

[0023] Two ion exchange towers are turned on as current ion exchange towers, and the target clear liquid is input into the current ion exchange towers. The target clear liquid passes through the two current ion exchange towers in sequence, and the adsorption resin adsorbs the uranium ions;

[0024] Determine whether the adsorption resin in the current ion exchange tower is saturated. When the adsorption resin is saturated, close the current ion exchange tower and start the ion exchange tower connected in series with another current ion exchange tower as the current ion exchange tower.

[0025] The step of desorbing the adsorption resin to obtain a uranium concentrate comprises:

[0026] inputting a desorbent into the ion exchange tower;

[0027] Determine the uranium content in the discharged analytical solution,

[0028] When the uranium content is greater than the second threshold, the analytical solution is used as a uranium concentrate. If the uranium content is not greater than the second threshold and greater than the third threshold, the analytical solution is used as a desorbent.

[0029] When the uranium content is less than the third threshold, the analysis is stopped.

[0030] The adsorption resin is a 201×7 type anion exchange resin, and the desorbent includes a sodium chloride solution and a sodium carbonate solution.

[0031] Wherein, after the step of stopping the analysis when the uranium content is less than the third threshold, the method further includes:

[0032] Backwash the adsorption resin.

[0033] The step of precipitating the uranium concentrate to obtain a uranium-containing recovered product comprises:

[0034] The uranium concentrate is precipitated with alkali to obtain sodium diuranate, and the sodium diuranate precipitate is filtered to obtain uranium-containing recovered material.

[0035] Beneficial effects

[0036] The present invention provides a method for treating uranium-containing wastewater. Conventional wastewater treatment methods primarily focus on removing harmful substances from the wastewater to meet environmental emission standards, but pay insufficient attention to the recovery and utilization of uranium resources. In this application, the uranium-containing wastewater to be treated is pretreated to achieve sedimentation and filtration of impurities. The resulting target clear liquid is passed through an ion exchange tower to adsorb uranium ions. The adsorption resin is then desorbed to obtain a uranium concentrate, which is then precipitated to obtain a uranium-containing recovered product. This removes harmful substances from the wastewater, optimizes the utilization of water resources, and simultaneously recovers the separated uranium, reducing pollution and saving energy, achieving the dual goals of uranium resource recovery and environmental protection. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] Figure 1 A flow chart of a method for treating uranium-containing wastewater provided in an embodiment of the present invention;

[0038] Figure 2 This is a process flow chart of a method for treating uranium-containing wastewater provided in an embodiment of the present invention. DETAILED DESCRIPTION

[0039] In order to further illustrate the technical means and effects adopted by the present invention to achieve the predetermined purpose of the invention, the specific implementation method, structure, characteristics and effects of the treatment method of uranium-containing wastewater proposed by the present invention are described in detail below in conjunction with the accompanying drawings and preferred embodiments.

[0040] like Figure 1 、 Figure 2As shown, an embodiment of the present invention provides a method for treating uranium-containing wastewater, which is used in a uranium-containing wastewater treatment system. The system includes a pretreatment system, a water treatment system, and a uranium recovery system, which are sequentially connected via a transmission pipeline. The pretreatment system may include a mine water tank, a mud drainage tank, a backwash water tank, a concentration tank, an intermediate water tank, water purification equipment, and various pumps, valves, reagent addition equipment, agitation equipment, filter press equipment, and connecting pipes; the water treatment system includes one or more ion exchange towers and various connecting pipes; and the uranium recovery system may include a filter press, a primary barren liquid tank, a secondary barren liquid tank, a qualified liquid storage tank, a desorbent tank, a sedimentation and stirring tank, and various pumps, valves, agitation equipment, reagent addition equipment, and connecting pipes.

[0041] The method generally involves: uranium-containing wastewater passes through a pretreatment system to obtain a pretreatment supernatant and filter residue; the pretreatment supernatant passes through a water treatment system, namely an ion exchange tower, to obtain an adsorption tail liquid, which, after analysis and compliance, is recycled as a resource. Simultaneously, uranium ions are enriched in the ion exchange tower; the uranium ions enriched in the ion exchange tower are desorbed and recovered in a uranium recovery system. The present invention utilizes a three-stage system for coordinated operation, with each system operating independently yet closely together, resulting in convenient and stable operation. Simultaneously, the wastewater is subjected to advanced treatment to meet the discharge requirement of a uranium ion content of ≤0.05 mg / L in uranium-containing wastewater, achieving the dual goals of uranium resource recovery and environmental protection.

[0042] The following describes in detail the various embodiments of the present application.

[0043] Methods include:

[0044] S1. Pre-treating the uranium-containing wastewater to be treated to obtain the target clear liquid.

[0045] Because the uranium-containing wastewater to be treated typically contains not only uranium but also impurities such as oil, silt, and sand, preliminary filtration is required to obtain a relatively clean uranium-containing clear solution. The preliminary filtration method can be single or multiple. For example, the characteristics of pit water produced by open-pit iron-uranium associated minerals under normal mining conditions show significant seasonal variations. Therefore, the pretreatment method for the uranium-containing wastewater to be treated can vary according to the water's characteristics. For example, filtration alone can be performed to remove particulate impurities in the uranium-containing wastewater, or coagulation can be performed to assist in the removal of impurities.

[0046] S2. The target clear liquid is input into the ion exchange tower, and the adsorption resin adsorbs the uranium ions.

[0047] The ion exchange tower can be a fixed bed ion exchange tower, and the adsorption resin adsorbs the uranium in the target clear liquid. The adsorption line flow rate is controlled to 60m 3 / h~90m 3 / h, the size of the ion exchange tower is Φ3000mm×6500mm, the resin filling height is 4m-5m, such as 4.5m, and the resin volume is 30m 3 -35 m 3 , such as 31.8m 3 The resin used is 201×7 resin.

[0048] To ensure continuous uranium ion adsorption and improve production efficiency, one embodiment employs at least three ion exchange towers. For example, three ion exchange towers can be connected in series, with two operating simultaneously as active ion exchange towers and the remaining closed towers acting as standby ion exchange towers. The target clear solution is fed into the active ion exchange towers and sequentially passes through the two active ion exchange towers, where the adsorption resin adsorbs uranium ions. The adsorption resin in the active ion exchange tower is determined to be saturated. If saturated, the active ion exchange tower is shut down and the standby ion exchange tower connected in series with the other active ion exchange tower is activated as the active ion exchange tower. Specifically, when the uranium ion concentration in the first tower (the front end of the two active ion exchange towers) approaches the original solution concentration, or when the uranium ion concentration in the effluent from the tail tower (the rear end) approaches 0.05 mg / L, the standby ion exchange tower is switched off as described above. The pressure in the first tower is controlled to be no greater than 0.2 MPa.

[0049] S3. Desorb the adsorption resin to obtain uranium concentrate.

[0050] The timing for desorption can be to determine when the adsorption resin in the current ion exchange column is saturated, then switch the column, and then desorb the ion exchange column where the resin has reached saturation with uranium ions. Desorption can also be performed periodically, such as after 24 or 36 hours of continuous operation, to desorb a solution containing high-concentration uranium ions, such as a uranium concentrate with a uranium ion concentration greater than or equal to 1 g / L, thereby further obtaining the product.

[0051] The adsorption resin may be a 201×7 type anion exchange resin, and the desorbent includes a 60 g / L sodium chloride solution and a 10 g / L sodium carbonate solution.

[0052] S4. Precipitating the uranium concentrate to obtain a uranium-containing recovered product.

[0053] The uranium concentrate is precipitated with alkali to obtain sodium diuranate, and the sodium diuranate precipitate is filtered to obtain uranium-containing recovered material.

[0054] The uranium concentrate from step 3, with a uranium ion concentration of 1 g / L or greater, is pumped from the qualified liquid storage tank to a precipitation agitation tank. The agitation control is activated, with a stirring speed set between 15 and 25 rpm. An alkaline precipitant, such as solid sodium hydroxide, is added to the uranium concentrate for a stirring time of at least 1 hour. When the pH reaches between 13 and 14, e.g., 13.5, the agitation control is deactivated, and the aging precipitation is allowed to proceed for a predetermined period, such as 24 hours.

[0055] The precipitated slurry after aging and settling is then pumped into a filter press for filtration and then air-dried. The feed pressure is adjusted to below a preset value, such as less than 0.8 MPa. The air-drying pressure can be between 0.5 MPa and 0.7 MPa, or 0.6 MPa, for example, for 1 to 2 hours. The sodium diuranate obtained through precipitation is then used to recover uranium resources.

[0056] The present invention provides a method for treating uranium-containing wastewater. Conventional wastewater treatment methods primarily focus on removing harmful substances from the wastewater to meet environmental emission standards, but pay insufficient attention to the recycling and utilization of uranium resources. In this application, the uranium-containing wastewater to be treated is pretreated to achieve sedimentation and filtration of impurities. The resulting target clear liquid is passed through an ion exchange tower to adsorb uranium ions. The adsorption resin is then desorbed to obtain a uranium concentrate, which is then precipitated to obtain a uranium-containing recovered product. This removes harmful substances from the wastewater, optimizes the utilization of water resources, and simultaneously recovers the separated uranium, reducing pollution and saving energy, achieving the dual goals of uranium resource recycling and environmental protection.

[0057] In one embodiment, in step S1, pre-treating the uranium-containing wastewater to be treated to obtain the target clear solution, different pre-treatments may be performed according to the season.

[0058] For example, in spring and summer, the mine water is relatively clear and free of harmful substances. No coagulant is required in S1, which reduces treatment costs and simplifies the process. The process can include:

[0059] The particulate matter in the uranium-containing wastewater to be treated is separated by the filter material of the water purification equipment to obtain the target clear liquid;

[0060] The water purification equipment is desludged at preset intervals.

[0061] That is, the uranium-containing wastewater to be treated is pretreated only by fully automatic water purification equipment to obtain the target clear liquid, which is pumped into the intermediate water pool for subsequent treatment.

[0062] The fully automatic water purification equipment can process 150t / h of water. The filter material used is high-quality sand with a filter layer thickness of 700mm. The filter material specifications include: A particle size 2mm-4mm; B particle size 1mm-2mm; C particle size 0.6mm-1.2mm.

[0063] The fully automatic water purification system includes an automatic mud discharge function, equipped with an automatic mud discharge valve and control system. The discharged mud is returned to the mine through a trench. The mud discharge cycle of the fully automatic water purifier can be referred to in Table 1 below. The mud discharge time is 1-2 minutes, which varies according to the actual water quality.

[0064] Table 1 Automatic water purifier sludge discharge period table

[0065] Influent turbidity (mg / L) 100 200 500 Mud discharge cycle (h) 24 12 8

[0066] In some embodiments, the target clear liquid is sampled at the output end of the automatic water purification device every 8 hours to check the water quality, and the purified water quality is required to be clear and transparent.

[0067] In autumn and winter, the mine water is turbid, but contains no harmful substances. Coagulants can be added to S1 to allow the harmful substances to settle.

[0068] Add coagulant to the uranium-containing wastewater to be treated, perform backwashing on the uranium-containing wastewater after adding the coagulant, wait for the sludge to settle, discharge the settled sludge, and obtain the target clear liquid. The discharged sludge is recovered.

[0069] In a more specific embodiment, the coagulant is prepared into a 5%-10% solution for standby use. After the mine water is transported to the mine water pool by a multi-stage water pump, the coagulant is added, the water inlet is reduced, and the dosage is increased to 1.5 times to 2 times the normal dosage. When the water level rises to the sedimentation outlet, forced backwashing is performed to flush out the sediment and suspended matter to prevent clogging of the filter layer. From the sedimentation outlet, the water flows through the ditch and back to the mine for further treatment. When the turbidity of the mine water drops to no more than 5 mg / L and the suspended layer is stable, the water inlet is gradually increased and the backwash is ended. At the same time, the coagulant dosage is reduced to the normal dosage.

[0070] The backwash clear liquid is then pumped into the intermediate water tank as the target clear liquid for treatment in the water treatment system, specifically into the ion exchange tower. At the inlet of the intermediate water tank, water quality is sampled every 8 hours to ensure clarity and transparency.

[0071] Backwash water flows through a trench to the backwash pool. The clear liquid above it is pumped to the mine water tank for further treatment via an automatic mixing and sludge pump. Mud discharged from the backwash pool's sludge pump flows through a trench into the sludge pool. The sludge is then pumped into a thickening tank for separation and separation by an automatic mixing and sludge scraper driven by a central hydraulic system. Polyacrylamide is also added as a sludge conditioning agent to enhance sludge concentration. The supernatant overflow from the thickening tank is sent to the mine water tank for further treatment. The sludge from the thickening tank is pumped into a belt filter press via a sludge pump, with a controlled belt speed of 1m / min to 10m / min and a processing capacity of 10m³ / h to 20m³ / h. After filtration, the clear liquid flows through a trench into the sludge pool. The filter residue is then transported to a collection tank and deposited in a tailings storage tank for recycling.

[0072] In this embodiment, the coagulants are polyaluminum chloride and polyacrylamide. The dosage of polyaluminum chloride is determined based on the turbidity of the mine water and the flocculation effect, and is generally less than 15 mg / L. The dosage concentration is configured to be 5%-10%, such as 10%, and the dosage is 100 L / h.

[0073] The concentration of polyacrylamide added is 0.1% to 0.2%, ensuring that the hydrolysis and nitrification time is not less than 45 minutes.

[0074] It can be understood that the above method of filtering through the filter material of the water purification equipment without adding coagulant, or the method of adding coagulant can be used alone in some seasons and can be set according to actual needs.

[0075] In one embodiment, after the step of inputting the target clear liquid into the ion exchange tower and allowing the adsorption resin to adsorb uranium ions, the method further includes: detecting the uranium content of the clear liquid to be determined after the uranium ion adsorption, discharging the clear liquid when the uranium content is lower than a first preset value, and re-inputting the clear liquid to be determined as the target clear liquid into the ion exchange tower when the uranium content is not lower than the first preset value.

[0076] The first preset value can be 0.05 mg / L. The clear liquid to be determined is analyzed and tested every 8 hours to ensure that the uranium ion concentration meets the discharge requirement of ≤0.05 mg / L. The clear liquid to be determined is then discharged into a reservoir and used as a resource for normal production water such as open-pit iron ore mining. If it does not meet the first preset value, re-adsorption is performed.

[0077] In one embodiment, the desorption of the ion exchange tower can be carried out using the following lean liquid circulation desorption process:

[0078] A desorbent is fed into the ion exchange tower to determine the uranium content in the discharged desorption liquid. When the uranium content is greater than a second threshold, the desorption liquid is used as a uranium concentrate. If the uranium content is not greater than the second threshold but greater than a third threshold, the desorption liquid is used as a desorbent. When the uranium content is less than the third threshold, desorption is stopped.

[0079] In a more specific embodiment, in the desorbent tank, the qualified clear liquid after uranium ion adsorption can be used to prepare a full tank of new desorbent for standby use. Then, the liquid stored in the lean liquid pool in the previous desorption cycle is first pumped into the ion exchange tower through the lean liquid pump until it submerges the resin and is desorbed and soaked for the first preset time. The first preset time can be set as needed, such as 48h. After desorption and soaking, the output liquid is instantaneously sampled and analyzed to determine the uranium ion concentration. When the uranium ion concentration is greater than or equal to 1g / L, the output liquid is used as uranium concentrate or qualified liquid, and the qualified liquid is discharged into the qualified liquid storage tank at a preset flow rate. The preset flow rate can be 7m 3 / h~10m 3 / h; if the uranium ion concentration is lower than 1g / L, stop using the feed solution in the primary barren liquid pool for analysis and switch to using the feed solution in the secondary barren liquid pool for analysis.

[0080] The liquid from the previous desorption cycle, stored in the secondary lean liquid tank, is pumped into the ion exchange tower via a lean liquid pump until the resin is submerged. This desorption soaking period is then continued for a second preset time. This second preset time can be adjusted as needed, for example, 24 hours. After desorption and soaking, the primary lean liquid is obtained. This primary lean liquid is then discharged into the primary lean liquid storage tank at a preset flow rate until the tank is full.

[0081] After the primary lean liquid storage tank is full, the new desorbent is pumped into the ion exchange tower through the lean liquid pump until it covers the adsorption resin and is desorbed and soaked for the third preset time. The third preset time can be set as needed, such as 24 hours. After desorption and soaking, the output liquid is instantaneously sampled and analyzed to determine the uranium ion concentration. When the uranium ion concentration is less than 30 mg / L, the desorption is terminated; when the uranium ion concentration is greater than or equal to 30 mg / L, the output liquid is obtained as the secondary lean liquid. The secondary lean liquid is eluted at a preset flow rate, which can be 7m 3 / h~10m 3 / h until the secondary barren liquid pool is full. If the uranium ion concentration cannot be reduced to less than 30mg / L even after the secondary barren liquid pool is full, the spare secondary barren liquid pool can be used to store the secondary barren liquid.

[0082] The above analytical method further performs adsorption resin analysis by utilizing the analytical lean solution. On the one hand, the uranium-containing analytical agent makes the analysis more effective, and on the other hand, it ensures that the uranium ion concentration of the output liquid after analysis is high.

[0083] In some embodiments, when the uranium ion concentration is lower than 30 mg / L, after desorption is completed, the lean resin can be backwashed for a fourth preset time, which can be 48 hours. The backwashing flow rate is controlled to be 15m 3 / h~20m 3 / h to remove the desorbent on the adsorption resin and loosen the resin bed to achieve better adsorption effect.

[0084] The above are merely specific embodiments of the present invention, but the scope of protection of the present invention is not limited thereto. Any modifications or substitutions that can be easily conceived by a person skilled in the art within the technical scope disclosed in the present invention should be included within the scope of protection of the present invention. Therefore, the scope of protection of the present invention should be based on the scope of protection of the claims.

Claims

1. A method for treating uranium-containing wastewater, characterized in that: A system for deep resource recovery treatment of uranium-containing wastewater from iron-uranium associated ores, the system comprising an ion exchange tower in which an adsorption resin is provided; The method comprises: Pre-treating the uranium-containing wastewater to be treated to obtain a target clear liquid; The target clear liquid is input into the ion exchange tower, and the adsorption resin adsorbs uranium ions; desorbing the adsorption resin to obtain a uranium concentrate; The uranium concentrate is precipitated to obtain a uranium-containing recovered product.

2. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The steps of pre-treating the uranium-containing wastewater to be treated to obtain the target clear solution include: adding a coagulant to the uranium-containing wastewater to be treated, performing a backwash treatment on the uranium-containing wastewater after the coagulant is added, allowing the sludge to settle, and discharging the settled sludge to obtain the target clear liquid; The discharged sludge is recovered.

3. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The coagulant comprises a mixed solution of polyaluminium chloride and polyacrylamide.

4. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The system further includes a water purification device, which includes a filter material. The steps of pre-treating the uranium-containing wastewater to be treated to obtain the target clear liquid include: Separating particulate matter from the uranium-containing wastewater to be treated by filtering the water purification equipment to obtain the target clear liquid; The water purification equipment is drained of sludge at preset time intervals.

5. The method for treating uranium-containing wastewater according to claim 1, characterized in that: After the step of inputting the target clear liquid into the ion exchange tower and the adsorption resin adsorbing uranium ions, the method further comprises: The uranium content of the clear liquid to be determined after uranium ion adsorption is detected. When the uranium content is lower than a first preset value, the clear liquid is discharged. When the uranium content is not lower than the first preset value, the clear liquid to be determined is re-inputted into the ion exchange tower as the target clear liquid.

6. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The number of the ion exchange towers is not less than three, and the ion exchange towers are connected in series. The step of inputting the target clear liquid into the ion exchange tower and allowing the adsorption resin to adsorb uranium ions comprises: The two ion exchange towers are turned on as current ion exchange towers, and the target clear liquid is input into the current ion exchange towers. The target clear liquid passes through the two current ion exchange towers in sequence, and the adsorption resin adsorbs uranium ions; Determine whether the adsorption resin in the current ion exchange tower is saturated. When the adsorption resin is saturated, close the current ion exchange tower and start an ion exchange tower connected in series with another current ion exchange tower as the current ion exchange tower.

7. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The steps of desorbing the adsorption resin to obtain a uranium concentrate include: inputting a desorbent into the ion exchange tower; Determine the uranium content in the discharged analytical solution, When the uranium content is greater than a second threshold, the analytical solution is used as the uranium concentrate; if the uranium content is not greater than the second threshold and greater than a third threshold, the analytical solution is used as the desorbent; When the uranium content is less than the third threshold, the analysis is stopped.

8. The method for treating uranium-containing wastewater according to claim 7, characterized in that: The adsorption resin is a 201×7 type anion exchange resin, and the desorbent includes a sodium chloride solution and a sodium carbonate solution.

9. The method for treating uranium-containing wastewater according to claim 7, characterized in that: After stopping the analysis when the uranium content is less than the third threshold, the method further includes: The adsorption resin is backwashed.

10. The method for treating uranium-containing wastewater according to claim 1, characterized in that: The step of precipitating the uranium concentrate to obtain a uranium-containing recovered product comprises: The uranium concentrate is precipitated with alkali to obtain sodium diuranate, and the sodium diuranate precipitate is filtered to obtain the uranium-containing recovered product.

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