A method for treating uranium-containing wastewater

Abstract

The application discloses a kind of treatment methods of uranium-containing wastewater, by ion exchange tower to uranium ion is adsorbed, by to adsorption resin is desorbed, the uranium concentrate liquid obtained, and then precipitate obtains uranium-containing recovery, realize the removal of harmful substances in wastewater, realize water resource optimization utilization simultaneously, to the uranium separated is recycled, reduce pollution, energy saving, realizes the recycling of uranium resources and the dual goal of environmental protection.The main technical scheme of the application is: the pretreatment of the uranium-containing wastewater to be treated is carried out, and the target clear liquid is obtained; the target clear liquid is input into the ion exchange tower, and the adsorption resin is used to adsorb uranium ions; the adsorption resin is desorbed, and the uranium concentrate liquid is obtained; the uranium concentrate liquid is precipitated, and the uranium-containing recovery is obtained.The application is mainly used for industrial wastewater treatment.

Description

Technical Field

[0001] This invention relates to the field of industrial wastewater treatment technology, and in particular to a method for treating uranium-containing wastewater. Background Technology

[0002] The mining of iron-uranium associated minerals generates large quantities of industrial wastewater containing uranium. Traditional wastewater treatment methods primarily focus on removing harmful substances to meet environmental emission standards, while paying insufficient attention to the recycling and utilization of uranium resources. However, uranium, as an important nuclear energy resource, has extremely high economic value and strategic significance. Enriching uranium from wastewater can not only reduce radioactive pollution but also achieve efficient resource utilization, offering both environmental and economic benefits.

[0003] In recent years, with the gradual strengthening of my country's supervision 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, while capable of partially removing uranium from wastewater, suffer from high treatment costs, large amounts of secondary waste generation, and low treatment efficiency, and fail to fully exploit 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 for addressing the environmental and resource issues in 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-mentioned technical problems, embodiments of the present invention provide a method for treating uranium-containing wastewater, thereby solving the problems of uranium-containing wastewater failing to meet environmental emission standards and uranium resource waste.

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

[0006] This invention provides a method for treating uranium-containing wastewater, which is used in a deep resource utilization treatment system for uranium-containing wastewater from iron-uranium associated minerals. The system includes an ion exchange tower, and the ion exchange tower is equipped with adsorption resin.

[0007] The methods include:

[0008] The uranium-containing wastewater to be treated is pretreated to obtain the target clear liquid;

[0009] The target solution is fed into the ion exchange tower, where the adsorption resin adsorbs uranium ions.

[0010] The uranium concentrate obtained by desorbing the adsorption resin;

[0011] The uranium enrichment solution was precipitated to obtain uranium-containing recovery material.

[0012] The step of pretreating the uranium-containing wastewater to obtain the target clarified liquid includes:

[0013] Coagulant is added to the uranium-containing wastewater to be treated, and the uranium-containing wastewater after the addition of coagulant is backwashed. After the sludge settles, the settled sludge is discharged to obtain the target clear liquid.

[0014] Recycling of discharged sludge.

[0015] The coagulant includes a mixture of polyaluminum chloride and polyacrylamide.

[0016] The system also includes a water purification device, which includes filter media, and a step for pretreating the uranium-containing wastewater to obtain the target clarified liquid, including:

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

[0018] Sludge is removed from the water purification equipment at preset intervals.

[0019] The process, after the step of feeding the target purified solution into the ion exchange tower and the adsorption resin adsorbing uranium ions, also includes:

[0020] The uranium content of the uranium-containing liquid after uranium ion adsorption is detected. If the uranium content is lower than the first preset value, it is discharged. If it is not lower than the first preset value, the uranium-containing liquid is fed back into the ion exchange tower as the target liquid.

[0021] The number of ion exchange towers shall not be less than three, and the ion exchange towers shall be connected in series.

[0022] The steps of feeding the target purified solution into the ion exchange tower and adsorbing uranium ions onto the adsorption resin include:

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

[0024] Determine whether the adsorption resin in the current ion exchange tower is saturated. If the adsorption resin is saturated, shut down 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 the uranium enrichment includes:

[0026] Input the desorbent into the ion exchange tower;

[0027] Determine the uranium content in the discharged eluent.

[0028] If the uranium content is greater than the second threshold, the eluent is used as uranium enrichment solution; if the uranium content is not greater than the second threshold but greater than the third threshold, the eluent is used as desorbent.

[0029] Analysis is stopped when the uranium content is less than the third threshold.

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

[0031] The step of stopping analysis when the uranium content is less than the third threshold also includes:

[0032] The adsorption resin is backwashed.

[0033] The step of precipitating uranium enrichment to obtain uranium-containing recoveries includes:

[0034] Sodium diuranate was obtained by adding alkali to the uranium concentrate and precipitating it. The sodium diuranate precipitate was then filtered to obtain uranium-containing recovered material.

[0035] Beneficial effects

[0036] This invention provides a method for treating uranium-containing wastewater. Traditional wastewater treatment methods mainly focus on removing harmful substances from wastewater to meet environmental emission standards, while paying 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 clear liquid is then passed through an ion exchange tower to adsorb uranium ions. By desorbing the adsorption resin, a uranium concentrate is obtained, which is then precipitated to obtain uranium-containing recovered material. This method removes harmful substances from the wastewater, optimizes water resource utilization, and recovers the separated uranium, reducing pollution and saving energy. It achieves the dual goals of uranium resource recovery and environmental protection. Attached Figure Description

[0037] Figure 1 A flowchart illustrating a method for treating uranium-containing wastewater according to an embodiment of the present invention;

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

[0039] To further illustrate the technical means and effects adopted by the present invention to achieve the intended purpose, the following detailed description of the specific implementation method, structure, features and effects of the uranium-containing wastewater treatment method proposed according to the present invention, in conjunction with the accompanying drawings and preferred embodiments, is provided below.

[0040] like Figure 1 , Figure 2As shown, this embodiment of the invention provides a method for treating uranium-containing wastewater, used in a uranium-containing wastewater treatment system. The system includes a pretreatment system, a water treatment system, and a uranium recovery system connected sequentially via pipelines. The pretreatment system may include a mine pit water tank, a sludge discharge tank, a backwash water tank, a thickening tank, an intermediate water tank, water purification equipment, and various pumps, valves, reagent addition equipment, agitators, filter presses, and connecting pipes. The water treatment system includes one or more ion exchange towers and various connecting pipes. The uranium recovery system may include a filter press, a primary lean liquid tank, a secondary lean liquid tank, a qualified liquid storage tank, a desorbent tank, a sedimentation and stirring tank, and various pumps, valves, agitators, reagent addition equipment, and connecting pipes.

[0041] The method generally includes: uranium-containing wastewater is pretreated to obtain pretreated clarified liquid and filter residue; the pretreated clarified liquid is then processed through a water treatment system, namely an ion exchange tower, to obtain adsorbed tailings, which are then utilized after meeting the standards. Simultaneously, uranium ions are enriched in the ion exchange tower; the uranium ions enriched in the ion exchange tower are then desorbed and recovered from the uranium resource through a uranium recovery system. This invention relies on a three-stage system operating collaboratively, with each system operating independently yet closely coordinated, ensuring convenient operation and stable performance. It also provides advanced treatment of the wastewater, meeting the discharge requirement of uranium ion content ≤0.05 mg / L, thus achieving the dual goals of uranium resource recovery and environmental protection.

[0042] The various embodiments of this application are described in detail below.

[0043] The methods include:

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

[0045] Since the uranium-containing wastewater to be treated usually contains impurities such as oil, sludge, and sand in addition to uranium, preliminary filtration is required to obtain a relatively clean uranium-containing solution. Preliminary filtration can be a single method or a combination of methods. For example, the characteristics of mine water from open-pit iron-uranium associated mines under normal mining conditions exhibit significant seasonal variations. Therefore, the pretreatment method for the uranium-containing wastewater to be treated can vary according to the characteristics of the water. For instance, filtration alone can be used to remove particulate impurities from the uranium-containing wastewater, or coagulation can be used to assist in removing impurities.

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

[0047] The ion exchange tower can be a fixed-bed ion exchange tower, where the adsorption resin adsorbs uranium from the target solution. The adsorption line flow rate is controlled at 60 m³ / s. 3 / h~90m 3 / h, the ion exchange tower dimensions are Φ3000mm×6500mm, the resin filling height is 4m-5m, or 4.5m if possible, and the resin volume is 30m³. 3 -35 m 3 For example, it could be 31.8m 3 All resins used are 201×7 resin.

[0048] To ensure continuous uranium ion adsorption and improve production efficiency, in one embodiment, the number of ion exchange towers is no less than three, and can be three in series. Two ion exchange towers are simultaneously activated as the current ion exchange towers, while the other closed towers serve as standby ion exchange towers. The target purified solution is input into the current ion exchange towers, passing sequentially through the two current ion exchange towers, where the adsorption resin adsorbs uranium ions. The saturation of the adsorption resin in the current ion exchange tower is determined. If the resin is saturated, the current ion exchange tower is shut down, and the standby ion exchange tower connected in series with the other current ion exchange tower is activated as the current ion exchange tower. Specifically, the saturation of the adsorption resin in the current ion exchange tower is determined by using two towers in series. Specifically, when the uranium ion concentration in the first tower (located at the front end) is close to the original solution concentration, or the uranium ion concentration in the effluent from the last tower (located at the rear end) is close to 0.05 mg / L, the standby ion exchange tower is switched 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 of the desorption can be either as described above, where the adsorption resin in the ion exchange tower is determined to be saturated, and the tower is switched off, then desorption is performed on the ion exchange tower where the resin has reached saturation. Alternatively, desorption can be performed periodically, such as after 24 hours or 36 hours of continuous operation, followed by active tower switching and desorption. This desorption aims to remove a solution containing a high concentration of 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 can 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. The uranium enrichment solution is precipitated to obtain uranium-containing recovery material.

[0053] Sodium diuranate was obtained by adding alkali to the uranium concentrate and precipitating it. The sodium diuranate precipitate was then filtered to obtain uranium-containing recovered material.

[0054] The uranium enrichment solution with a uranium ion concentration greater than or equal to 1 g / L from step 3 above is pumped to a sedimentation tank using a qualified liquid storage pump. The stirring device is turned on for stirring, with a stirring speed set to 15-25 r / min. An alkaline substance, such as solid sodium hydroxide, is added to the uranium enrichment solution for precipitation. The stirring time is greater than 1 hour. When the pH value is between 13 and 14 (e.g., 13.5), the stirring device is turned off, and aging precipitation is allowed for a certain period, such as 24 hours.

[0055] Further, the aged precipitate slurry is pumped into a filter press for filtration and then dried by blowing air. The feed pressure is adjusted to be lower than the preset pressure value, such as less than 0.8 MPa. The blowing pressure can be 0.5 MPa-0.7 MPa, or even 0.6 MPa, and the blowing time is 1 to 2 hours. The sodium diuranate obtained through precipitation enables the recovery of uranium resources.

[0056] This invention provides a method for treating uranium-containing wastewater. Traditional wastewater treatment methods mainly focus on removing harmful substances from wastewater to meet environmental emission standards, while paying 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 clear liquid is then passed through an ion exchange tower to adsorb uranium ions. By desorbing the adsorption resin, a uranium concentrate is obtained, which is then precipitated to obtain uranium-containing recovered material. This method removes harmful substances from the wastewater, optimizes water resource utilization, and recovers the separated uranium, reducing pollution and saving energy. It achieves the dual goals of uranium resource recovery and environmental protection.

[0057] In one embodiment, step S1, the method of pretreating the uranium-containing wastewater to be treated to obtain the target clear liquid, can be to perform different pretreatments according to the season.

[0058] During spring and summer, mine water is relatively clear and free of harmful substances. No coagulants need to be added to S1, reducing treatment costs and simplifying the process, which may include:

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

[0060] Sludge is removed from the water purification equipment at preset intervals.

[0061] This means that the uranium-containing wastewater to be treated is pretreated using fully automated water purification equipment to obtain the target clear liquid, which is then pumped into an intermediate water tank for further treatment.

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

[0063] The fully automatic water purification equipment includes an automatic sludge discharge function, equipped with an automatic sludge discharge valve and its control system. The discharged sludge is returned to the mine pit through a ditch. The sludge discharge cycle of the fully automatic water purifier can be referenced in Table 1 below, with a discharge time of 1-2 minutes, depending on the actual changes in the quality of the incoming water.

[0064] Table 1. Automatic Water Purifier Sludge Removal Cycle

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

[0066] In some implementations, the target purified water is sampled and tested for quality at the output of the automatic water purification equipment every 8 hours, and the purified water is required to be clear and transparent.

[0067] In autumn and winter, the mine water is relatively turbid, but contains no other harmful substances. Harmful substances in S1 can be settled by adding coagulants. Specifically:

[0068] A coagulant is added to the uranium-containing wastewater to be treated. The wastewater after adding the coagulant is backwashed. After the sludge settles, the settled sludge is discharged, and the target clear liquid is obtained. The discharged sludge is recycled.

[0069] In a more specific implementation, the coagulant is prepared as a 5%-10% solution for later use. After the mine water is pumped to the mine water tank by a multi-stage pump, the coagulant is added, and the influent flow rate is reduced while the dosage is increased to 1.5-2 times the normal dosage. When the water level rises to the sedimentation outlet, forced backwashing is performed to flush away sediment and suspended solids, preventing clogging of the filter layer. The water flows from the sedimentation outlet through a drainage ditch back into 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 influent flow rate is gradually increased and the backwashing is stopped. Simultaneously, the coagulant dosage is reduced to the normal dosage.

[0070] The resulting backwash solution enters an intermediate water tank, where it is further pumped into the water treatment system for further processing, specifically into an ion exchange tower, as the target solution. Water quality is sampled and checked every 8 hours at the inlet of the intermediate water tank to ensure the purified water is clear and transparent.

[0071] Backwash water flows through a ditch to the backwash pool, and the clear liquid above it is sent to the mine pit water tank for reprocessing via an automatic stirring and sewage pump. Sludge discharged from the sludge pump in the backwash pool flows through a ditch into the sludge discharge pool, where it is then pumped into a thickening tank for concentration and separation by an automatic hydraulically driven scraper. Simultaneously, polyacrylamide is added as a sludge conditioning agent to enhance the sludge concentration effect. The supernatant overflowing from the thickening tank is sent to the mine pit water tank for reprocessing. The sludge from the thickening tank is pumped into a belt press filter, with the filter belt speed controlled at 1m / min to 10m / min and a processing capacity of 10m³ / h to 20m³ / h. After pressing, the filtrate flows through a ditch into the sludge discharge pool, and the filter residue is transported to a collection tank and stored in the tailings sludge storage for recycling.

[0072] In this embodiment, the coagulant is 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 concentration is configured to be 5%-10%, or 10%, with a dosage of 100 L / h.

[0073] The concentration of polyacrylamide should be 0.1% to 0.2%, and the hydrolysis and nitrification time should be no less than 45 minutes.

[0074] It is understandable that the above methods, which do not require the addition of coagulants and rely solely on filtration through the filter media of the water purification equipment, or methods that involve adding coagulants, can be used alone in certain seasons and can be set according to actual needs.

[0075] In one embodiment, after the step of feeding the target clear liquid into the ion exchange tower and the adsorption resin adsorbing uranium ions, the method further includes: detecting the uranium content of the undetermined clear liquid after uranium ion adsorption; discharging the undetermined clear liquid when the uranium content is lower than a first preset value; and feeding the undetermined clear liquid back into the ion exchange tower as the target clear liquid when the uranium content is not lower than the first preset value.

[0076] The first preset value can be 0.05 mg / L. The solution to be analyzed and tested every 8 hours to ensure that the uranium ion concentration meets the discharge requirement of ≤0.05 mg / L. The solution to be analyzed and tested is then discharged into a storage tank for normal production water use in open-pit iron ore mining and other operations, thus being used as a resource. If the first preset value requirement is not met, re-adsorption is performed.

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

[0078] Desorbent is introduced into the ion exchange tower, and the uranium content in the discharged eluent is determined. If the uranium content is greater than the second threshold, the eluent is used as uranium enrichment. If the uranium content is not greater than the second threshold but greater than the third threshold, the eluent is used as desorbent. If the uranium content is less than the third threshold, the desorption is stopped.

[0079] In a more specific implementation, in the desorbent tank, the qualified clear liquid after uranium ion adsorption can be used to prepare a full tank of new desorbent for later use. Then, the feed solution from the previous desorption cycle, stored in the primary lean solution tank, is pumped into the ion exchange tower via a lean solution pump until the resin is submerged, and the desorption soaking is performed for a first preset time. The first preset time can be set as needed, such as 48 hours. After desorption soaking, the output liquid is sampled and analyzed instantaneously to determine the uranium ion concentration. When the uranium ion concentration is greater than or equal to 1 g / L, the output liquid is used as uranium concentrate or qualified liquid, and discharged into the qualified liquid storage tank at a preset flow rate, which can be 7 m³ / L. 3 / h~10m 3 / h; if the uranium ion concentration is below 1g / L, the solution in the primary lean solution tank is no longer used for analysis, and the solution in the secondary lean solution tank is used instead.

[0080] The feed solution stored in the secondary lean solution tank from the previous desorption cycle is pumped into the ion exchange tower until it covers the resin, and then desorbed and soaked for a second preset time. The second preset time can be set as needed, such as 24 hours. After desorption and soaking, a primary lean solution is obtained. The primary lean solution is discharged into the primary lean solution storage tank at a preset flow rate until the tank is full.

[0081] After the primary lean solution storage tank is full, new desorbent is pumped into the ion exchange tower via the lean solution pump until it covers the adsorption resin, followed by a third preset desorption soaking time. This third preset time can be set as needed, such as 24 hours. After desorption soaking, the output liquid is sampled and analyzed instantaneously to determine the uranium ion concentration. Desorption ends when the uranium ion concentration is less than 30 mg / L; when the uranium ion concentration is greater than or equal to 30 mg / L, the output liquid is obtained as the secondary lean solution. The secondary lean solution is leached out at a preset flow rate, which can be 7 m³ / L. 3 / h~10m 3 The process continues at a rate of / h until the secondary lean solution tank is full. If the uranium ion concentration is still less than 30 mg / L even after the secondary lean solution tank is full, the backup secondary lean solution tank can be used for secondary lean solution storage.

[0082] The above-mentioned analysis method utilizes a lean analysis solution for further analysis with adsorption resin. On the one hand, the uranium-containing analysis agent makes the analysis more effective, and on the other hand, it ensures a high uranium ion concentration in the output solution after analysis.

[0083] In some embodiments, when the uranium ion concentration is below 30 mg / L, after desorption is completed, a backwashing operation for a fourth preset time can be performed on the lean resin. This fourth preset time can be 48 hours. The backwashing flow rate is controlled at 15 m³ / L. 3 / h~20m 3 / h, to remove the desorbent from 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 variations or substitutions that can be easily conceived by those 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 determined by the scope of the claims.

Claims

1. A method for treating uranium-containing wastewater, characterized in that, A system for deep resource utilization treatment of uranium-containing wastewater from iron-uranium associated minerals, the system including an ion exchange tower, the ion exchange tower being equipped with adsorption resin; The method includes: Pretreatment of uranium-containing wastewater to be treated: After the mine water is transported to the mine water pool by multi-stage water pumps, coagulant is added and backwashing is performed. The resulting backwash liquid enters the intermediate water pool as the target liquid. The backwash water flows to the backwash pool, and the clear liquid above is sent to the mine pit water pool for reprocessing. The sludge discharged from the backwash pool flows into the sludge discharge pool. The sludge is pumped into the thickening pool for concentration and separation. Sludge conditioning agents are added. The supernatant in the thickening pool overflows and is sent to the mine pit water pool for reprocessing. The sludge in the thickening pool is pumped into a belt press filter for filtration. After pressing, the clear liquid flows into the sludge discharge pool through the ditch. The filter residue is transported to the collection bucket and stored in the tailings sludge storage. The target clear liquid is fed into the ion exchange tower, where the adsorption resin adsorbs uranium ions; The adsorption resin is desorbed to obtain uranium concentrate; The feed solution stored in the primary lean solution tank is sent to the ion exchange tower. After desorption and soaking, if the uranium ion concentration of the output liquid is greater than or equal to 1 g / L, the output liquid is used as the uranium concentrate. If the uranium ion concentration is less than 1 g / L, the feed solution stored in the secondary lean solution tank is sent to the ion exchange tower. After desorption and soaking, the primary lean solution is discharged into the primary lean solution tank. After the primary lean solution tank is full, new desorbent is introduced into the ion exchange tower. After desorption and soaking, if the uranium ion concentration is less than 30 mg / L, desorption is terminated; if the uranium ion concentration is greater than or equal to 30 mg / L, the output liquid is discharged into the secondary lean solution tank as secondary lean solution. The uranium concentrate was precipitated to obtain uranium-containing recovered material.

2. The method for treating uranium-containing wastewater according to claim 1, characterized in that, The coagulant comprises a mixture of polyaluminum chloride and polyacrylamide.

3. The method for treating uranium-containing wastewater according to claim 1, characterized in that, The system also includes a water purification device, which includes filter media, and a step of pretreating the uranium-containing wastewater to obtain the target clarified liquid includes: The particulate matter in the uranium-containing wastewater to be treated is separated by the filter media of the water purification equipment to obtain the target clear liquid; The water purification equipment is sludge removed at preset intervals.

4. The method for treating uranium-containing wastewater according to claim 1, characterized in that, After the step of feeding the target purified solution into the ion exchange tower and the adsorption resin adsorbing uranium ions, the method further includes: The uranium content of the uranium-containing purified liquid after uranium ion adsorption is detected. If the uranium content is lower than a first preset value, it is discharged. If the uranium content is not lower than the first preset value, the uranium-containing purified liquid is reintroduced into the ion exchange tower as the target purified liquid.

5. The method for treating uranium-containing wastewater according to claim 1, characterized in that, The number of ion exchange towers is not less than three, and the ion exchange towers are connected in series. The step of feeding the target purified solution into the ion exchange tower, and the adsorption resin adsorbing uranium ions, includes: Two ion exchange towers are turned on as current ion exchange towers, and the target purified solution is input into the current ion exchange towers. The target purified solution 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. If the adsorption resin is saturated, shut down 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.

6. The method for treating uranium-containing wastewater according to claim 1, characterized in that, The adsorption resin is a 201×7 type anion exchange resin, and the desorbent includes sodium chloride solution and sodium carbonate solution.

7. The method for treating uranium-containing wastewater according to claim 1, characterized in that, After stopping the desorption step when the uranium content is less than 30 mg / L, the procedure further includes: The adsorbent resin is backwashed.

8. The method for treating uranium-containing wastewater according to claim 1, characterized in that, The step of precipitating the uranium enrichment to obtain uranium-containing recoveries includes: Sodium diuranate is obtained by adding alkali to the uranium concentrate and precipitating it. The sodium diuranate precipitate is then filtered by pressure to obtain the uranium-containing recovered product.

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