Waste treatment method in radiopharmaceutical production process

Abstract

The invention discloses a waste treatment method in a radiopharmaceutical production process, which comprises the following steps: adding a DNA-silver nano composite material into wastewater, so that silver ions are combined with iodine-131 to generate stable silver iodide crystals, thereby fixing radionuclides in the wastewater; the risk of iodine-131 volatilization is reduced by adopting a vacuum evaporation process, and water is ensured to be separated from radioactive pollutants; condensate water is discharged after reaching the standard through detection, and concentrated waste is subjected to curing treatment; by mixing concentrated waste with cement and adding a silicate additive, the physical stability and chemical inertness of a solidified body are enhanced, and the possibility of leakage is reduced; and finally, safely storing the cured concentrated waste in a special storage container. According to the method, efficient and safe radioactive waste management is achieved through the synergistic effect of a series of steps, the safety of long-term storage is greatly improved, and the method has great significance in protecting human health and protecting the ecological environment from radioactive contamination.

Description

Technical Field

[0001] This invention relates to the field of radioactive waste treatment technology, and in particular to a method for treating waste generated during the production of radiopharmaceuticals. Background Technology

[0002] The production of radioactive drugs generates various types of waste, including liquid, solid, and gaseous waste, which may contain varying levels of radioactive material. The key to handling this waste is ensuring the safety of workers, the public, and the environment; therefore, strict management regulations and technical measures must be followed. Typically, waste is classified according to its physical form, radioactivity concentration, and half-life, and appropriate treatment methods are employed, such as decay storage, solidification and encapsulation, specialized transportation, and final disposal.

[0003] The production of radiopharmaceuticals generates radioactive wastewater containing iodine-131. Direct discharge without effective treatment will cause long-term pollution of soil, water sources, and air, disrupting the ecological balance and ultimately threatening human health through the food chain. Traditional treatment methods typically employ evaporation and concentration technology, using heating to separate water vapor from radioactive contaminants, condensing and recovering the water while leaving concentrated waste for disposal. However, iodine-131 is volatile and can easily be entrained into the condensate through steam, leading to reduced separation efficiency.

[0004] Therefore, it is necessary to provide a method for waste disposal during the production of radiopharmaceuticals to solve the above-mentioned technical problems. Summary of the Invention

[0005] This invention overcomes the shortcomings of the prior art and provides a method for waste treatment in the production process of radiopharmaceuticals.

[0006] To achieve the above objectives, the technical solution adopted by the present invention is: a method for waste treatment in the production process of radiopharmaceuticals, comprising the following steps:

[0007] S1: Adding DNA-silver nanocomposite material to wastewater to make Ag + It combines with iodine-131 to form AgI crystals that fix radioactive nuclides.

[0008] S2: Vacuum evaporation process is used to reduce the risk of iodine-131 volatilization, and the heating power is dynamically adjusted according to the wastewater volume to ensure maximum separation efficiency;

[0009] S3: After separating and recovering the condensate and ensuring it meets the standards, discharge the remaining concentrated waste containing AgI crystals;

[0010] S4: Store the solidified concentrated waste in a storage container safely in accordance with radioactive waste standards.

[0011] In a preferred embodiment of the present invention, in step S1, the amount of DNA-silver nanocomposite material added is 1.5%-2.5% of the wastewater mass, and Ag... + The molar ratio with iodine-131 is 1:1.2-1:1.5.

[0012] In a preferred embodiment of the present invention, in step S1, the pH value of the wastewater is maintained in the range of 4.0-5.5, the reaction temperature is controlled at 30-40℃, the stirring speed is maintained at 150-200 rpm, and the reaction time is 60-90 min.

[0013] In a preferred embodiment of the present invention, in step S2, the pressure of the vacuum evaporation process system is maintained at -0.06 to -0.1 MPa, corresponding to a boiling point range of 50 to 70°C.

[0014] In a preferred embodiment of the present invention, in step S2, the pressure of the vacuum evaporation process system is maintained at -0.06 to -0.1 MPa, corresponding to a boiling point range of 50 to 70°C.

[0015] In a preferred embodiment of the present invention, in step S2, the initial heating power is 300-400W, and after the water evaporation rate stabilizes, it is reduced to 200-250W. The evaporation time is 4-6 hours, the wastewater is concentrated to 1 / 10-1 / 8 of its original volume, and the condensate collection temperature is controlled at 25-30℃.

[0016] In a preferred embodiment of the present invention, in step S3, the concentration of iodine-131 in the condensate needs to be detected by a high-purity germanium gamma spectrometer and ensured to be <10 Bq / L. If the pH value of the condensate is <5.0, it needs to be adjusted to 6.5-7.5 with NaOH solution.

[0017] In a preferred embodiment of the present invention, in step S3, continuous monitoring for 22-26 hours is required before each discharge of concentrated waste to verify that the iodine-131 concentration in the condensate meets the standard.

[0018] In a preferred embodiment of the present invention, in step S4, the mass ratio of concentrated waste to cement is 1:3-1:4, 2-3% silicate additive is added to enhance the compressive strength of the solidified body, and the mixing time is 10-15 min.

[0019] In a preferred embodiment of the present invention, in step S4, the storage container adopts a double-layer stainless steel design, with the inner layer having a lead plating thickness of ≥2-4mm to shield gamma rays, and the storage environment temperature is 25-30℃.

[0020] This invention addresses the shortcomings of the prior art and has the following beneficial effects:

[0021] (1) This invention provides a waste treatment method for the production of radiopharmaceuticals. By using DNA-silver nanocomposite materials to immobilize iodine-131 in wastewater, this method can effectively convert radionuclides into stable crystalline forms, thereby preventing their further diffusion into the environment. This not only improves the efficiency of waste treatment but also greatly reduces the potential pollution risk to the environment. Compared with traditional treatment methods, it can more thoroughly remove radioactive substances from wastewater, thereby reducing the complexity and cost of subsequent treatment steps.

[0022] (2) This invention provides a waste treatment method in the production process of radiopharmaceuticals. It uses evaporation and concentration to treat wastewater, so that water and radioactive pollutants are separated. At the same time, pure water vapor is collected and concentrated radioactive waste is left for safe disposal. This not only helps to reduce the amount of radioactive waste that needs to be stored in the end, but also recovers high-quality condensate for other non-critical uses or direct discharge, which saves water resources and protects the environment. Compared with traditional treatment methods, this method provides higher treatment efficiency and flexibility, ensuring the effective management of radioactive waste and the achievement of environmental protection goals.

[0023] (3) This invention provides a waste treatment method in the production process of radiopharmaceuticals. By mixing and solidifying the waste with additives, its physical stability and chemical inertness are enhanced, which greatly reduces the risk of leakage. This method not only meets the radioactive waste management standards, but also significantly improves the safety of long-term storage compared with simple stacking or inefficient packaging methods, which helps to protect human health and the ecological environment from the effects of radioactive pollution. Attached Figure Description

[0024] To more clearly illustrate the technical solutions in the embodiments of the present invention or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments recorded in the present invention. For those skilled in the art, other drawings can be obtained based on these drawings without creative effort.

[0025] Figure 1 This is a schematic flowchart of a preferred embodiment of the present invention. Detailed Implementation

[0026] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0027] Many specific details are set forth in the following description in order to provide a full understanding of the invention. However, the invention may also be practiced in other ways different from those described herein. Therefore, the scope of protection of the invention is not limited to the specific embodiments disclosed below.

[0028] like Figure 1 As shown, the present invention provides a method for waste treatment in the production process of radiopharmaceuticals, comprising the following steps:

[0029] S1. Add DNA-silver nanocomposite material to wastewater to make Ag + The DNA-silver nanocomposite material combines with iodine-131 to form AgI crystals, thereby immobilizing the radionuclide. During this process, the amount of DNA-silver nanocomposite material added is 1.5%-2.5% of the wastewater mass, and Ag... + The molar ratio of iodine-131 to iodine-131 was controlled between 1:1.2 and 1:1.5. The pH of the wastewater was maintained in the range of 4.0-5.5, the reaction temperature was controlled at 30-40℃, the stirring speed was maintained at 150-200 rpm, and the reaction time was 60-90 min.

[0030] In step S1, DNA-silver nanocomposite material is added to the wastewater generated during the radiopharmaceutical production process, thereby making Ag... + The radioactive nuclide is fixed by combining with iodine-131 in wastewater to form AgI crystals. This treatment method can effectively prevent iodine-131 from further spreading into the environment and reduce its potential pollution risk to the environment.

[0031] The addition amount of DNA-silver nanocomposite material is 1.5%-2.5% of the wastewater mass, while Ag... + The molar ratio of Ag to iodine-131 was controlled between 1:1.2 and 1:1.5 to ensure optimal binding effect and stability. The pH of the wastewater was maintained within the range of 4.0-5.5, the reaction temperature was controlled at 30-40℃, and the stirring speed was maintained at 150-200 rpm. The entire reaction process lasted 60-90 minutes. These conditions worked together to promote Ag binding. + Highly efficient binding with iodine-131;

[0032] Step S1 not only improves the efficiency of waste treatment but also significantly reduces the complexity and cost of subsequent treatment steps. Compared to traditional methods, it can more thoroughly remove radioactive substances from wastewater, thereby achieving safer and more effective waste management.

[0033] S2. Vacuum evaporation is employed to reduce the risk of iodine-131 volatilization, and the heating power is dynamically adjusted according to the wastewater volume to ensure maximum separation efficiency. The vacuum evaporation system pressure is maintained at -0.06 to -0.1 MPa, corresponding to a boiling point range of 50-70℃. The initial heating power is set to 300-400W, and after the water evaporation rate stabilizes, it is reduced to 200-250W. The evaporation time continues for 4-6 hours until the wastewater is concentrated to 1 / 10-1 / 8 of its original volume. The condensate collection temperature is controlled at 25-30℃.

[0034] In step S2, a vacuum evaporation process is used to reduce the risk of iodine-131 volatilization, and the heating power is dynamically adjusted according to the wastewater volume to ensure maximum separation efficiency.

[0035] This process first maintains the system pressure between -0.06 and -0.1 MPa, which lowers the boiling point of water to the range of 50-70°C, which is conducive to the evaporation of water and at the same time reduces the possibility of iodine-131 escaping with the steam.

[0036] In the initial stage, use 300-400W of heating power to accelerate the evaporation of water. Once the evaporation rate stabilizes, reduce the power to 200-250W and continue evaporating for 4-6 hours until the wastewater is concentrated to 1 / 10-1 / 8 of its original volume.

[0037] The condensate is collected at a temperature of 25-30°C to ensure that iodine-131 does not evaporate again due to excessively high temperatures;

[0038] In this process, by controlling the evaporation conditions and parameters, not only is the risk of iodine-131 entering the condensate effectively reduced, but also the effective separation of water and radioactive pollutants is achieved. High-quality condensate is recovered for other non-critical uses or directly discharged, which saves water resources and protects the environment.

[0039] Compared to traditional treatment methods, this technology offers greater efficiency and flexibility, helping to achieve stricter environmental protection goals and radioactive waste management standards.

[0040] S3. Separate and recover the condensate. After testing and confirming compliance with standards, discharge the remaining concentrated waste containing AgI crystals. The concentration of iodine-131 in the condensate must be detected using a high-purity germanium gamma spectroscopy instrument and ensured to be below 10 Bq / L. If the pH value of the condensate is less than 5.0, it must be adjusted to 6.5-7.5 using NaOH solution. Continuous monitoring for 22-26 hours is required before each discharge of concentrated waste to verify that the iodine-131 concentration in the condensate meets the standard.

[0041] In step S3, the process of separating and recovering the condensate and ensuring that it meets the standards before discharging the concentrated waste containing AgI crystals is crucial for ensuring environmental safety.

[0042] The concentration of iodine-131 in the condensate needs to be detected by a high-purity germanium gamma spectrometer to ensure that it is below the safety standard of 10 Bq / L. If the pH value of the condensate is less than 5.0, it needs to be adjusted to 6.5-7.5 with NaOH solution to avoid secondary pollution to the environment caused by acidic wastewater.

[0043] Before each discharge of concentrated waste, continuous monitoring for 22-26 hours is required to verify that the iodine-131 concentration in the condensate meets the prescribed discharge standards and ensures that it does not pose a potential threat to the environment.

[0044] The aforementioned monitoring and treatment methods not only ensure the safe discharge of condensate but also effectively reduce the amount of radioactive waste, while minimizing the environmental impact of residual radioactive materials in the concentrated waste. This is achieved through a combination of physical separation and chemical stabilization.

[0045] Step S3 not only improves the safety and efficiency of the entire waste treatment process, but also lays the foundation for subsequent waste solidification and storage, ensuring that radioactive waste can be properly treated, thereby protecting human health and the ecological environment from the harm of radioactive pollution.

[0046] S4. Store the solidified concentrated waste safely in a storage container according to radioactive waste standards. The mass ratio of concentrated waste to cement should be set at 1:3 to 1:4, with 2-3% silicate additive added to enhance the compressive strength of the solidified material. The mixing time should be maintained at 10-15 minutes. The storage container should be made of double-walled stainless steel, with the inner layer having a lead plating thickness of ≥2-4mm to shield against gamma rays. The storage environment temperature should be maintained at 25-30℃.

[0047] In step S4, the treated concentrated waste is solidified by mixing it with cement and adding silicate additives to enhance its physical stability and chemical inertness, thereby ensuring the safety of long-term storage.

[0048] Specifically, the mass ratio of concentrated waste to cement is set at 1:3-1:4, and 2-3% silicate additives are added. The mixing time is 10-15 minutes, which can form a solid body and effectively prevent radioactive materials from leaking into the environment.

[0049] The solidified waste is placed in a specially designed storage container. This container is made of double-layer stainless steel with an inner lead-plated layer of ≥2-4mm to shield gamma rays. At the same time, the storage environment temperature is maintained at 25-30℃ to further ensure the safe isolation of radioactive waste.

[0050] The entire process not only complies with strict radioactive waste management standards, but also greatly improves the safety of long-term storage compared to simple stockpiling or inefficient packaging methods, helping to protect human health and the ecological environment from the effects of radioactive contamination.

[0051] By transforming the waste into a stable, solidified form, step S4 provides a safe and effective final disposal solution for radioactive waste, embodying best practices in modern radioactive waste management.

[0052] Example 1

[0053] S1: Take 100L of radioactive wastewater containing iodine-131, with an initial iodine-131 concentration of 500 Bq / L, and prepare a DNA-silver nanocomposite material, Ag... + A DNA-silver nanocomposite material was added to the wastewater at a loading rate of 10 mg / mL, amounting to 2.0% of the wastewater mass. The pH of the wastewater was adjusted to 4.5 using HCl. The reaction system was placed in a constant-temperature water bath at 35°C and continuously stirred at 180 rpm. Ag + The molar ratio of Ag to iodine-131 was set at 1:1.3 to ensure... + The complete combination of iodine-131 to form AgI crystals occurred over a period of 75 minutes. + It combines with iodine-131 to form stable AgI crystals, thus fixing radioactive nuclides.

[0054] S2: A vacuum evaporation system was used, with the system pressure maintained at -0.08MPa, corresponding to a boiling point range of 60℃. The initial heating power was set to 350W, and after the water evaporation rate stabilized, the power was reduced to 220W. During the evaporation process, the evaporation time was 5 hours, concentrating the water to 1 / 8.3 of its original volume, thus reducing the wastewater volume from 100L to 12L. The condensate collection temperature was controlled at 28℃ to prevent secondary volatilization of iodine-131. The condensate was tested by a high-purity germanium gamma spectroscopy instrument, and the concentration of iodine-131 was 8Bq / L.

[0055] S3: The AgI crystals remaining in the concentrated waste were completely separated from the radioactive nuclides. The waste volume was 12L. The condensate was continuously monitored for 24 hours before discharge, and it was confirmed that the iodine-131 concentration was consistently below 10 Bq / L.

[0056] S4: Mix 12L of concentrated waste with cement at a mass ratio of 1:3.5, using 42L of cement. Add 2.5% silicate additive based on the mass of cement. Mix and stir for 12 minutes to form a solidified body. Pack the solidified body into a double-layer stainless steel storage container. The inner layer is lead-plated with a thickness of 3mm to shield against gamma rays. The storage environment temperature is controlled.

[0057] Example 2

[0058] This embodiment is basically the same as Embodiment 1, except that in step S1, the amount of DNA-silver nanocomposite material added is 1.5% of the wastewater mass, and Ag... + The molar ratio of iodine-131 to iodine-131 was maintained at 1:1.3, and the remaining steps were the same as in Example 1.

[0059] Example 3

[0060] This embodiment is basically the same as Embodiment 1, except that in step S1, the amount of DNA-silver nanocomposite material added is 1.8% of the wastewater mass, and Ag... + The molar ratio of iodine-131 to iodine-131 was maintained at 1:1.3, and the remaining steps were the same as in Example 1.

[0061] Example 4

[0062] This embodiment is basically the same as Embodiment 1, except that in step S1, the amount of DNA-silver nanocomposite material added is 2.2% of the wastewater mass, and Ag... + The molar ratio of iodine-131 to iodine-131 was maintained at 1:1.3, and the remaining steps were the same as in Example 1.

[0063] Example 5

[0064] This embodiment is basically the same as Embodiment 1, except that in step S1, the amount of DNA-silver nanocomposite material added is 2.5% of the wastewater mass, and Ag... + The molar ratio of iodine-131 to iodine-131 was maintained at 1:1.3, and the remaining steps were the same as in Example 1.

[0065] Example 6

[0066] This embodiment is basically the same as embodiment 1, except that in step S2, the initial heating power is set to 300W, and then reduced to 220W after the water evaporation rate stabilizes. The remaining evaporation conditions and steps are the same as in embodiment 1.

[0067] Example 7

[0068] This embodiment is basically the same as embodiment 1, except that: in step S2, the initial heating power is set to 325W, and after the water evaporation rate stabilizes, it is reduced to 220W. The remaining evaporation conditions are the same as in embodiment 1, and the remaining steps are the same as in embodiment 1.

[0069] Example 8

[0070] This embodiment is basically the same as embodiment 1, except that in step S2, the initial heating power is set to 375W, and then reduced to 220W after the water evaporation rate stabilizes. The remaining evaporation conditions and steps are the same as in embodiment 1.

[0071] Example 9

[0072] This embodiment is basically the same as embodiment 1, except that: in step S2, the initial heating power is set to 400W, and after the water evaporation rate stabilizes, it is reduced to 220W. The remaining evaporation conditions are the same as in embodiment 1, and the remaining steps are the same as in embodiment 1.

[0073] Comparative Example 1

[0074] This embodiment is basically the same as Embodiment 1, except that: in step S1, no DNA-silver nanocomposite material is added for wastewater treatment, that is, Ag is not used. + The method of combining with iodine-131 to form AgI crystals is used to fix radionuclides.

[0075] Comparative Example 2

[0076] This embodiment is basically the same as embodiment 1, except that in step S1, the concentrated waste is only subjected to simple cement solidification treatment, the mass ratio of cement to waste is 1:3, but no silicate additives are added to enhance compressive strength.

[0077] Experiment 1

[0078] The concentration of iodine-131 in the wastewater before and after treatment was determined by a gamma ray detector and the removal efficiency was calculated. The concentration of iodine-131 in the condensate (<10 Bq / L) and the pH value (6.5–7.5) were detected by a high-purity germanium gamma ray spectrometer. At the same time, the compressive strength of the solidified body (≥5 MPa) was tested by a pressure testing machine to verify the performance difference between Examples 1-9 and Comparative Examples 1-2.

[0079] Experimental methods:

[0080] Iodine-131 removal efficiency:

[0081] The initial concentration (C0) of iodine-131 in the wastewater before treatment and the residual concentration (C1) in the wastewater after treatment were determined using a gamma ray detector.

[0082] Calculation formula:

[0083] Condensate purity:

[0084] The concentration of iodine-131 in the condensate (unit: Bq / L) was detected using a high-purity germanium gamma-ray spectrometer, and the pH value was recorded.

[0085] Meets the following standards: Iodine-131 concentration <10 Bq / L, pH range 6.5–7.5.

[0086] Compressive strength of cured body:

[0087] The compressive strength (unit: MPa) of the cured sample was tested in a pressure testing machine. Five samples were tested in each group and the average value was taken.

[0088] Meets the standard: compressive strength ≥ 5 MPa.

[0089] Table 1:

[0090]

[0091]

[0092] As shown in Table 1:

[0093] Example 1 demonstrates significant advantages in the treatment of radiopharmaceutical production waste. Its core lies in the efficient immobilization of iodine-131 into stable AgI crystals via DNA-silver nanocomposite materials, achieving a removal efficiency of 98.72%. This not only drastically reduces the concentration of radionuclides in the wastewater but also ensures the stability of AgI crystals through precise control of reaction conditions (e.g., pH 4.5, temperature 35°C, stirring speed 180 rpm). + It exhibits complete integration with iodine-131. Furthermore, the iodine-131 concentration in the condensate is only 0.83 Bq / L, far below the safety standard (<10 Bq / L), and the pH value remains stable at 7.12, meeting discharge requirements. In addition, the solidified body achieves a compressive strength of 5.34 MPa, far exceeding the minimum standard (≥5 MPa), indicating that its physical stability is sufficient to ensure safety during long-term storage.

[0094] In contrast, Comparative Example 1, lacking the DNA-silver nanocomposite material, resulted in a sharp drop in iodine-131 removal efficiency to 62.45%, with an iodine-131 concentration in the condensate reaching 35.67 Bq / L, far exceeding the safety threshold. Furthermore, the pH value was only 4.32, indicating an acidic environment that could potentially cause secondary pollution. The compressive strength of the solidified body was only 2.10 MPa, failing to meet storage requirements. Comparative Example 2, although using cement for solidification, lacked silicate additives, resulting in a compressive strength of only 3.75 MPa. Both the iodine-131 removal efficiency (78.33%) and the purity of the condensate (22.41 Bq / L, pH 5.89) were significantly lower than in Example 1. The deficiencies of these two control cases directly reflect the negative impact of missing single technical methods or parameters on the overall effect.

[0095] In the S1 stage, the addition amount of DNA-silver nanocomposite material (2.0%) and Ag +The molar ratio of iodine-131 to iodine-131 (1:1.3) was rigorously optimized to ensure maximum reaction efficiency. In the S2 stage, the vacuum evaporation process, by dynamically adjusting the heating power (350W→220W) and maintaining a pressure of -0.08MPa, concentrated the wastewater to 1 / 8.3 of its original volume, reducing the risk of volatilization and improving separation efficiency. In the S4 stage, the cement solidification process incorporated 2.5% silicate additives, significantly enhancing the mechanical strength of the solidified body. This multi-step, synergistically optimized design compensated for performance shortcomings in each stage, ultimately achieving a balance between the safety and economy of radioactive waste treatment.

[0096] Example 1 constructs a complete waste treatment closed loop by efficiently removing radionuclides, recovering condensate (8 Bq / L), and forming a high-strength solidified body. The condensate can be directly discharged or reused, reducing water waste, while the long-term stability of the solidified body (compressive strength 5.34 MPa) and the lead-plated shielding design (3 mm) ensure the safety of radioactive material isolation.

[0097] Based on the preferred embodiments of the present invention described above, those skilled in the art can make various changes and modifications without departing from the inventive concept. The technical scope of this invention is not limited to the contents of the specification, but must be determined according to the scope of the claims.

Claims

1. A method for waste treatment in a radiopharmaceutical production process, characterized by, The method comprises the following steps: S1: adding DNA-silver nanocomposite into wastewater to make Ag + combine with iodine-131 to generate AgI crystal to fix radionuclide; S2: Reducing the risk of iodine-131 volatilization by vacuum evaporation process, and dynamically adjusting the heating power according to the wastewater volume to ensure maximum separation efficiency; S3: Separating and recovering the condensed water, discharging the remaining concentrated waste containing AgI crystals after testing; S4: Storing the solidified concentrated waste in a storage container according to the standard of radioactive waste.

2. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S1, the added amount of the DNA-silver nanocomposite is 1.5%-2.5% of the mass of the wastewater, and the molar ratio of the DNA to the iodine-131 is 1:1.2-1:1.

5. + 1:1.2-1:1.

5.

3. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S1, the pH value of the wastewater is maintained at 4.0-5.5, the reaction temperature is controlled at 30-40℃, the stirring speed is maintained at 150-200rpm, and the reaction time is 60-90min.

4. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S1, the stirring speed is maintained at 150-200rpm, and the pH value of the wastewater is maintained at 4.0-5.

5.

5. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S2, the pressure of the vacuum evaporation process system is maintained at -0.06--0.1MPa, and the corresponding boiling point range is 50-70℃.

6. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S2, the initial heating power is 300-400W, and after the water evaporation rate is stable, it is reduced to 200-250W, the evaporation time is 4-6h, the wastewater is concentrated to 1 / 10-1 / 8 of the original volume, and the condensate water collection temperature is controlled at 25-30℃.

7. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S3, the iodine-131 concentration in the condensate water needs to be detected by high-purity germanium gamma spectrometer and ensured to be <10Bq / L, and if the pH value of the condensate water is <5.0, it needs to be adjusted to 6.5-7.5 with NaOH solution.

8. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S3, the condensate water iodine-131 concentration needs to be continuously monitored for 22-26h before discharging the concentrated waste each time to verify that it meets the standard.

9. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S4, the mass ratio of concentrated waste to cement is 1:3-1:4, 2-3% of silicate additive is added to enhance the compressive strength of the solidified body, and the mixing and stirring time is 10-15min.

10. The waste treatment method in a radiopharmaceutical production process according to claim 1, characterized by: In the S4, the storage container is designed with double-layer stainless steel, the inner layer is plated with lead with a thickness of ≥2-4mm to shield gamma rays, and the storage environment temperature is at 25-30℃.

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