Method for treating magnesium-containing high-radioactivity waste liquid

Abstract

The invention discloses a treatment method of magnesium-containing high-radioactivity waste liquid, and belongs to the technical field of high-radioactivity waste treatment.The treatment method comprises the steps that the magnesium-containing high-radioactivity waste liquid is sequentially filled with first-stage, second-stage, third-stage and fourth-stage chromatographic columns with different column fillers, high-heat-release fission nuclides in the magnesium-containing high-radioactivity waste liquid are removed, the radioactivity intensity of the magnesium-containing high-radioactivity waste liquid is reduced, and the high-radioactivity waste liquid is obtained; the method comprises the following steps: adding anhydrous oxalic acid into magnesium-containing high-level radioactive waste liquid to obtain magnesium-containing low-level radioactive waste liquid, further adjusting the magnesium-containing low-level radioactive waste liquid to be alkalescent, adding anhydrous oxalic acid, removing magnesium element in the waste liquid by adopting a precipitation method, reducing the salinity of the low-level radioactive waste liquid, and converting the magnesium-containing high-level radioactive waste liquid into low-salinity and low-radioactivity waste liquid which can be safely stored or further treated. According to the method, the high-radioactivity waste liquid can be subjected to rapid degradation treatment in situ, the radioactivity intensity and salinity of the high-radioactivity waste liquid are effectively reduced, the technological process is simple, the heat release nuclide removal efficiency is high, the secondary waste amount is small, and the method is suitable for implementation and easy to popularize.

Description

Technical Field

[0001] This application belongs to the field of high radioactive waste treatment technology, and in particular relates to a method for treating magnesium-containing high radioactive waste liquid. Background Technology

[0002] High-level radioactive waste liquids are characterized by high radioactivity, strong toxicity, large heat release, corrosiveness, and long half-lives of radioactive nuclides. Their safe treatment and disposal is not only part of the closed-loop nuclear fuel cycle but also a key aspect of nuclear waste management. Currently, there are two main technical solutions for the treatment and disposal of high-level radioactive waste liquids at home and abroad: (1) Direct solidification treatment of high-level radioactive waste liquids after temporary storage and cooling, followed by deep geological disposal; (2) Separation and removal of high-heat-releasing nuclides from high-level radioactive waste liquids to reduce radioactivity levels, followed by solidification and geological disposal. my country adheres to the closed-loop nuclear fuel cycle route and adopts technical solution (2) for the treatment and disposal of high-level radioactive waste liquids. This involves first removing high-heat-releasing nuclides from the high-level radioactive waste liquids and then further processing them. For example, Tsinghua University in China has developed a trialkylphosphine oxide (TRPO) extraction process, which is mainly based on a combination of solvent extraction and ion exchange to sequentially remove transuranium elements from the high-level radioactive waste liquids. 90 Sr、 137 Cs is used to reduce the radioactivity intensity of high-level radioactive waste liquid before solidification treatment.

[0003] For high-level radioactive waste generated during the reprocessing of spent fuel from power reactors, the general approach is to first reduce the radioactivity intensity of the waste before solidification. However, for small batches of high-level radioactive waste generated during isotope production (irradiation of uranium targets), on-site temporary storage is currently used. Due to the high toxicity and strong radioactivity of this waste, long-term storage poses significant safety risks, necessitating on-site, rapid degradation treatment. Currently, no relevant reports have been found domestically or internationally. Therefore, developing an on-site, rapid degradation method for high-level radioactive waste generated during isotope production is of great significance for the safe treatment and disposal of such waste. Summary of the Invention

[0004] This application aims to solve the technical problem of rapid downgrading treatment of small batches of high-level radioactive waste liquid. To this end, this application provides a treatment method for magnesium-containing high-level radioactive waste liquid, which can rapidly downgrade the high-level radioactive waste liquid on-site, effectively reducing the radioactivity intensity and salinity of the high-level radioactive waste liquid. The process is simple, the heat-releasing nuclide removal efficiency is high, the amount of secondary waste is small, and it is suitable for implementation and easy to promote.

[0005] This application provides a method for treating magnesium-containing radioactive waste liquid, comprising:

[0006] The magnesium-containing radioactive waste liquid was injected and passed through a primary chromatographic column containing packing material for adsorbing lanthanide and yttrium elements to obtain the first residual liquid.

[0007] injecting and passing the first raffinate through a second chromatographic column containing filler that adsorbs strontium elements to obtain a second raffinate;

[0008] injecting and passing the second raffinate through a third chromatographic column containing filler that adsorbs cesium elements to obtain a third raffinate;

[0009] adding ammonia water to adjust the pH of the third raffinate to 1-2;

[0010] injecting and passing the adjusted third raffinate through a fourth chromatographic column containing filler that adsorbs ruthenium elements to obtain a fourth raffinate, and injecting into a precipitation container;

[0011] adding ammonia water to the precipitation container to adjust the pH of the fourth raffinate to 8-9;

[0012] adding anhydrous oxalic acid to the precipitation container to precipitate magnesium elements;

[0013] separating the precipitated magnesium-containing solid phase.

[0014] In some embodiments, the magnesium-containing high-level radioactive waste liquid is a 3-5 mol / L nitric acid solution system, and contains multiple elements selected from Sr, Ce, Cs, Nd, Pr, Te, Sm, Y, Ru, Rh, Zr, Rh, Mo, La, and Ba.

[0015] In some embodiments, the concentration of magnesium ions in the magnesium-containing high-level radioactive waste liquid is 16-17 g / L.

[0016] In some embodiments, the device for injecting the magnesium-containing high-level radioactive waste liquid, the first raffinate, the second raffinate, and the third raffinate is a peristaltic pump, and the column loading speed of the peristaltic pump is controlled to be 1-3 mL / min.

[0017] In some embodiments, the first chromatographic column, the second chromatographic column, the third chromatographic column, and the fourth chromatographic column are all made of quartz material, and have an inner diameter of 8-10 mm and a column height of 100-150 mm.

[0018] In some embodiments, the column filler of the first chromatographic column is DGA resin, and has a particle size of 100-150 μm.

[0019] In some embodiments, the column filler of the second chromatographic column is YS10P0 XAD resin, and has a particle size of 50-100 μm.

[0020] In some embodiments, the column filler of the third chromatographic column is YC10P0 XAD resin, and has a particle size of 50-100 μm.

[0021] In some embodiments, the column filler of the fourth chromatographic column is CL-7024 XAD resin, and has a particle size of 100-150 μm.

[0022] In some embodiments, the amount of added anhydrous oxalic acid is 65-130 g.

[0023] From the above technical solutions, the beneficial effects of the present application are:

[0024] The present application does not need to adjust the acidity of high-level waste liquid, and directly performs in-situ degradation treatment of high-level waste liquid, simplifying the process of traditional in-situ treatment and disposal of high-level waste liquid. Specifically, lanthanide elements and yttrium elements are adsorbed by a first chromatographic column, strontium elements are adsorbed by a second chromatographic column, cesium elements are adsorbed by a third chromatographic column, and ruthenium elements are adsorbed by a fourth chromatographic column under pH adaptation conditions. Different radionuclides are efficiently captured by the multi-stage chromatographic column. The entire treatment process follows only adsorption, pH adjustment, precipitation, and separation without redundant circulation steps, and is simple to operate and has a simplified process without the need for special complex equipment or process control. After the removal of radionuclides, magnesium elements are precipitated and separated by pH adjustment. Through the above multi-stage treatment process, the present application significantly reduces the types and total amount of secondary waste, has a high removal efficiency for heat-releasing nuclides, and can remove more than 95% of lanthanide elements, 90 / 89 Sr, 137 Cs and 106 / 103 Ru in high-level waste liquid, and a large amount of magnesium elements brought in by irradiated uranium targets, reduces the salinity of radioactive waste liquid, significantly reduces the radioactivity level of high-level waste liquid, realizes rapid degradation treatment of high-level radioactive waste liquid in-situ, further reduces the difficulty of subsequent treatment, reduces the activity concentration of high-level waste liquid by 5-6 orders of magnitude, and converts it into low-level waste liquid. The process flow is simple, the treatment efficiency is high, the amount of secondary waste is small, and it is suitable for implementation and easy to popularize. BRIEF DESCRIPTION OF DRAWINGS

[0025] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed in the embodiment description will be simply introduced one by one below. Obviously, the drawings in the following description are some embodiments of the present application, and other embodiments and drawings can be obtained by those skilled in the art without creating laborious work on the basis of these drawings. In the drawings, various schematic diagrams according to the embodiments of the present application are shown, which are not necessarily drawn to scale, some details are exaggerated for the purpose of clear expression, and some details can be omitted.

[0026] Figure 1 An embodiment flowchart of the treatment method of the high-level radioactive waste liquid containing magnesium according to the present application is shown.

[0027] Figure 2 An embodiment principle schematic diagram of the treatment system of the high-level radioactive waste liquid containing magnesium according to the present application is shown. DETAILED DESCRIPTION

[0028] The technical solutions in the embodiments of the present application will be described clearly and completely below with reference to the accompanying drawings of the specific embodiments of the present application. The detailed description of the embodiments of the present application provided in the accompanying drawings is not intended to limit the scope of the present application, and the described embodiments are only some of the embodiments of the present application, but not all the embodiments. Based on the embodiments in the present application, various different configurations can be arranged and designed, and all other embodiments obtained by those skilled in the art without creative efforts fall within the scope of the present application.

[0029] The present application will be described below with reference to the accompanying drawings and specific embodiments:

[0030] Please refer to Figure 1 The first aspect of the present application provides a treatment method for high-level radioactive liquid waste containing magnesium, which is suitable for complex high-level radioactive liquid waste containing magnesium generated in isotope production, having strong acid characteristics, strong radiation and multiple element coexistence. The treatment method includes:

[0031] S1, injecting and passing the high-level radioactive liquid waste containing magnesium through a first chromatographic column containing filler adsorbing lanthanide elements and yttrium elements to obtain a first residual liquid;

[0032] S2, injecting and passing the first residual liquid through a second chromatographic column containing filler adsorbing strontium elements to obtain a second residual liquid;

[0033] S3, injecting and passing the second residual liquid through a third chromatographic column containing filler adsorbing cesium elements to obtain a third residual liquid;

[0034] S4, adding ammonia water to adjust the pH of the third residual liquid to 1-2;

[0035] S5, injecting and passing the adjusted third residual liquid through a fourth chromatographic column containing filler adsorbing ruthenium elements to obtain a fourth residual liquid, and injecting the fourth residual liquid into a precipitation container;

[0036] S6, adding ammonia water to the precipitation container to adjust the pH of the fourth residual liquid to 8-9;

[0037] S7, adding anhydrous oxalic acid to the precipitation container to precipitate magnesium elements;

[0038] S8, separating the precipitated solid phase containing magnesium.

[0039] The method is aimed at the characteristics of high-level waste liquid generated in isotope production (simple system, extremely low content of transuranium elements), mainly including multiple fission fragment nuclides. The above process is a strong radioactive operation, which needs to be carried out in a hot cell suitable for operating strong radioactivity.

[0040] In some embodiments, the high-level radioactive liquid waste containing magnesium is a 3-5 mol / L nitric acid solution system, which is simple and contains very few transuranium elements. The waste solution system contains multiple kinds of fission fragment elements, including all of Sr, Ce, Cs, Nd, Pr, Te, Sm, Y, Ru, Rh, Zr, Rh, Mo, La, and Ba. The radioactivity mainly comes from lanthanide elements, 90 Sr, 137 Cs, 106 Ru, and the high salinity mainly comes from magnesium powder and magnesium oxide in the irradiated uranium target. In some embodiments, the concentration of magnesium ions in the high-level radioactive liquid waste containing magnesium is 16-17 g / L, such as 16 g / L, 16.5 g / L, or 17 g / L, and the amount of high-level radioactive liquid waste treated at a time does not exceed 2 L.

[0041] In some embodiments, the device for injecting the high-level radioactive liquid waste containing magnesium, the first residual liquid, the second residual liquid, and the third residual liquid uses a peristaltic pump, and the column loading speed of the peristaltic pump is controlled to be 1-3 mL / min. Specifically, a peristaltic pump in the box chamber is used to pass the high-level radioactive waste liquid through a first chromatographic column, and the lanthanide elements and yttrium in the waste liquid are adsorbed on the resin of the first chromatographic column, and the first residual liquid enters the intermediate bottle; the column loading speed is controlled to be 1-3 mL / min. A peristaltic pump two in the box chamber is used to pass the first residual liquid through a second chromatographic column, and the strontium in the waste liquid is adsorbed on the second chromatographic column, and the second residual liquid enters the intermediate bottle two; the column loading speed is controlled to be 1-3 mL / min. A peristaltic pump three in the box chamber is used to pass the second residual liquid through a third chromatographic column, and the cesium in the waste liquid is adsorbed on the third chromatographic column, and the third residual liquid enters the intermediate bottle three; the column loading speed is controlled to be 1-3 mL / min. A peristaltic pump three in the box chamber is used to pass the second residual liquid through a third chromatographic column, and the cesium in the waste liquid is adsorbed on the third chromatographic column, and the third residual liquid enters the intermediate bottle three; the column loading speed is controlled to be 1-3 mL / min. A peristaltic pump six outside the box chamber is used to add 170-200 mL of ammonia water from the liquid addition tank to the intermediate bottle three, and the pH of the third residual liquid is adjusted to 1-2, and the ammonia water addition speed is controlled to be 8-10 mL / min; a peristaltic pump four is used to pass the adjusted third residual liquid through a fourth chromatographic column, and the ruthenium in the waste liquid is adsorbed on the fourth chromatographic column, and the fourth residual liquid is discharged into the precipitation tank; the column loading speed is controlled to be 1-3 mL / min.

[0042] In some embodiments, the multi-stage chromatographic column described above is mainly used for removing high-heat-releasing nuclides in high-level liquid waste. The first-stage chromatographic column, the second-stage chromatographic column, the third-stage chromatographic column, and the fourth-stage chromatographic column are all made of quartz, and have an inner diameter of 8-10 mm and a column height of 100-150 mm. Different column fillers are loaded into the chromatographic columns of different stages according to the different types of nuclides removed. The fillers are loaded by a dry method. One end of the chromatographic column is provided with a glass frit. After the chromatographic column with the fillers is loaded, a small amount of glass wool is inserted into the upper end to seal the two ends of the chromatographic column, for example, by using rubber plugs and aluminum caps. In some embodiments, the column filler of the first-stage chromatographic column is DGA resin, with a particle size of 100-150 μm and a loading amount of 2-5 g. In some embodiments, the column filler of the second-stage chromatographic column is YS10P0 extraction resin, with a particle size of 50-100 μm and a loading amount of 3-5 g. In some embodiments, the column filler of the third-stage chromatographic column is YC10P0 extraction resin, with a particle size of 50-100 μm and a loading amount of 2-5 g. In some embodiments, the column filler of the fourth-stage chromatographic column is CL-7024 extraction resin, with a particle size of 100-150 μm and a loading amount of 3-5 g.

[0043] After the chromatographic columns of different stages are loaded, pre-leaching of the chromatographic columns is required. The prepared chromatographic columns are fixed on a separation support. 50 mL of 5 mol / L nitric acid is used to pre-leach the first-stage, the second-stage, and the third-stage chromatographic columns, and 50 mL of 0.05 mol / L nitric acid is used to pre-leach the fourth-stage chromatographic column. The pre-leaching speed is controlled at 5-8 mL / min. The used multi-stage chromatographic column can be recycled by regeneration treatment, thereby effectively reducing the overall cost of the degradation treatment of the high-level radioactive waste liquid containing magnesium.

[0044] In some embodiments, after the step S5, the fourth raffinate generated is discharged into a precipitation container, such as a precipitation tank. After the step S6, ammonia water is added to adjust the pH to 8-9. Specifically, 30-50 mL of ammonia water is added to the precipitation tank at a speed of 8-10 mL / min by using the peristaltic pump six outside the tank chamber, so as to adjust the pH of the fourth raffinate to 8-9. After that, anhydrous oxalic acid is added to the liquid in the precipitation tank by the step S7. The amount of the anhydrous oxalic acid added is 65-130 g. The mixture is stirred until it is uniformly mixed. At this time, the magnesium ions in the waste liquid react with the anhydrous oxalic acid to generate white magnesium oxalate precipitate, forming a white suspension.

[0045] In some embodiments, the step S8 is specifically performed by using the peristaltic pump five inside the tank chamber to transport the suspension to a precipitation filter tank for solid-liquid separation. The precipitation filter tank has a filter screen. The white magnesium oxalate solid precipitate (as a solid waste liquid for subsequent treatment) is collected by the filter screen, and the low-level radioactive waste liquid (as a low-level waste liquid for subsequent treatment) is filtered out, thereby achieving in-situ degradation treatment of the high-level radioactive waste liquid containing magnesium.

[0046] Please refer to Figure 2This application also provides a treatment system for magnesium-containing high-radioactivity waste liquid, including a primary chromatographic column, a secondary chromatographic column, a tertiary chromatographic column, a quaternary chromatographic column, intermediate bottles one, two, and three, a precipitation container, and a filter tank. The packing of each chromatographic column is carried out according to the above method. The system also includes multiple peristaltic pumps. The two ends of peristaltic pump one are connected via hoses to the supply point of the high-radioactivity waste liquid and the inlet of the primary chromatographic column, respectively. The outlet of the primary chromatographic column is connected to intermediate bottle one. The two ends of peristaltic pump two are connected via hoses to intermediate bottle one and the secondary chromatographic column, respectively. The inlet of the secondary column and the outlet of the tertiary column are connected to intermediate bottle two. The two ends of peristaltic pump three are connected to the inlets of intermediate bottle two and the tertiary column respectively via hoses. The outlet of the tertiary column is connected to intermediate bottle three. The two ends of peristaltic pump four are connected to the inlets of intermediate bottle three and the quaternary column respectively via hoses. The outlet of the quaternary column is connected to the precipitation container. The precipitation container (precipitation tank) is connected to the filter cell. Intermediate bottle three is also connected to peristaltic pump six via hose. Peristaltic pump six is ​​also connected to the precipitation tank. The inlet of peristaltic pump six is ​​connected to the liquid addition tank at the alkali supply point.

[0047] Using the above-described processing system and method, the following are examples:

[0048] Example 1

[0049] The on-site degradation treatment of magnesium-containing high-level radioactive waste liquid in this invention is a highly radioactive operation, and this method needs to be carried out in a shielded chamber or hot chamber. Prepare 1L of simulated high-level radioactive waste liquid in a 3-5mol / L nitric acid solution, containing the 14 main fragmentation elements (Sr, Ce, Cs, Nd, Pr, Te, Sm, Y, Ru, Rh, Zr, Mo, La, Ba) as well as non-radioactive elements Mg and Na. The specific concentrations of each element are shown in Table 1.

[0050] Table 1. Composition and concentration of simulated high-level radioactive waste liquid

[0051]

[0052] Prepare four chromatographic columns: a primary column (100 μm particle size) packed with 2 g of DGA resin, a secondary column (50 μm particle size) packed with 3 g of YS10P0 extraction resin, a tertiary column (50 μm particle size) packed with 3 g of YC10P0 extraction resin, and a quaternary column (100 μm particle size) packed with 3 g of CL-7024 extraction resin. After packing, insert a small amount of glass wool into the top of each column and seal both ends with rubber stoppers and aluminum caps. Fix the four prepared columns on a support and pre-wash the columns using an external peristaltic pump. Pre-wash the first to third stage columns with 50 mL of 5 mol / L nitric acid, and the fourth stage column with 50 mL of 0.5 mol / L nitric acid solution. The pre-wash rate was controlled at 5–8 mL / min. The pre-wash solution was treated as non-radioactive waste.

[0053] S1. Using the peristaltic pump in the chamber, 1L of simulated high-level radioactive waste liquid is passed through a primary chromatographic column. Based on multiple parallel experiments, more than 99.9% of the lanthanides and yttrium in the waste liquid are adsorbed on the primary chromatographic column. The first residual liquid is discharged into intermediate bottle 1. The solution loading rate is controlled at 1-3 mL / min.

[0054] S2. Using the peristaltic pump 2 in the chamber, the first residual liquid in intermediate bottle 1 is passed through a secondary chromatographic column. Based on multiple parallel experiments, more than 95.5% of the strontium in the waste liquid is adsorbed on the secondary chromatographic column. The resulting second residual liquid is discharged into intermediate bottle 2. The solution loading rate is controlled at 1-3 mL / min.

[0055] S3. Using the peristaltic pump 3 in the chamber, the second residual liquid in intermediate bottle 2 is passed through a three-stage chromatographic column. Based on multiple parallel experiments, more than 99.5% of the cesium element in the waste liquid is adsorbed on the three-stage chromatographic column. The obtained third residual liquid is discharged into intermediate bottle 3. The solution loading rate is controlled at 1-3 mL / min.

[0056] S4. Using the peristaltic pump 6 outside the chamber, add 170mL of ammonia water to intermediate bottle 3, and adjust the pH of the third residual liquid to between 1 and 2.

[0057] S5. Using the peristaltic pump 4 in the chamber, the third residual liquid in intermediate bottle 3 is passed through a four-stage chromatographic column. According to multiple parallel experiments, more than 98.0% of the ruthenium element in the waste liquid is adsorbed on the four-stage chromatographic column. The obtained fourth residual liquid is discharged into the precipitation tank. The solution loading rate is controlled at 1-3 mL / min.

[0058] S6. Using the peristaltic pump 6 outside the chamber, add 30mL of ammonia water to the sedimentation tank 3, and adjust the pH of the fourth residual liquid to between 8 and 9.

[0059] S7. Add 65g of anhydrous oxalic acid solid to the precipitation tank, stir well, and let stand for 0.5-1h to form a white suspension.

[0060] S8. Using the peristaltic pump five in the chamber, the suspension in step S8 is transferred to the filter screen to separate the magnesium oxalate precipitate from the filtrate. The speed of the peristaltic pump is controlled at 15-20 mL / min to obtain magnesium oxalate solid waste and low-salinity, low-radioactivity waste liquid.

[0061] Based on multiple parallel experiments, the magnesium oxalate precipitate, after drying, weighed 80-85g. The element removal efficiency of each step in this application is shown in Table 2 below.

[0062] Table 2. Removal efficiency of elements at each step of the process.

[0063]

[0064] Example 2

[0065] Unlike Example 1, this example treats a volume of 2L of high-level radioactive waste liquid, and the concentration of magnesium ions in the magnesium-containing high-level radioactive waste liquid is 17g / L; the particle size of the primary chromatographic column packing material DGA resin is 120μm, the particle size of the secondary chromatographic column packing material YS10P0 extraction resin is 80μm, the particle size of the tertiary chromatographic column packing material YC10P0 extraction resin is 80μm, and the particle size of the quaternary chromatographic column packing material CL-7024 extraction resin is 120μm;

[0066] In step S4, the amount of ammonia added is 200 mL;

[0067] In step S6, the amount of ammonia added is 50 mL;

[0068] In step S7, the amount of anhydrous oxalic acid added is 130g.

[0069] Following the steps outlined in this application, the final magnesium oxalate precipitate obtained weighs between 155 and 165 g.

[0070] Example 3

[0071] Unlike Examples 1 and 2, the volume of high-level radioactive waste liquid treated in this example is 1.5L. The concentration of magnesium ions in the magnesium-containing high-level radioactive waste liquid is 16.5g / L. The 1.5L simulated high-level radioactive waste liquid contains the 12 main fragmentation elements (Sr, Ce, Cs, Nd, Pr, Te, Sm, Y, Ru, Mo, La, Ba) as well as non-radioactive elements Mg and Na. The specific concentrations of each element are shown in Table 3.

[0072] Table 3. Composition and concentration of simulated high-level radioactive waste liquid

[0073]

[0074] The primary chromatographic column packing material, DGA resin, has a particle size of 150 μm; the secondary chromatographic column packing material, YS10P0 extraction resin, has a particle size of 100 μm; the tertiary chromatographic column packing material, YC10P0 extraction resin, has a particle size of 100 μm; and the quaternary chromatographic column packing material, CL-7024 extraction resin, has a particle size of 150 μm.

[0075] In step S4, the amount of ammonia added is 180 mL;

[0076] In step S6, the amount of ammonia added is 40 mL;

[0077] In step S7, the amount of anhydrous oxalic acid added is 90g.

[0078] Following the steps outlined in this application, the final magnesium oxalate precipitate obtained weighs between 110 and 120 g.

[0079] Regarding the specific implementation methods of this application, it should be noted that:

[0080] In the description of this application, unless otherwise expressly specified and limited, the terms "connection," "fixed," "connected," etc., should be interpreted broadly. For example, "fixed" can refer to a fixed connection, a detachable connection, or an integral molding; "connection" can refer to a mechanical connection or a pipe connection; it can be a direct connection or an indirect connection through an intermediate medium; it can refer to the internal connection of two components or the interaction between two components, unless otherwise expressly limited; "connected" can refer to the internal connection of two parts and the connection between the two parts, or the spatial connection between the two, whereby the two parts are directly or indirectly connected through the part forming the space. Those skilled in the art can understand the specific meaning of the above terms in this application according to the specific circumstances.

[0081] In the description of this application, the use of terms such as "some embodiments," "optional embodiments," "example," "specific example," "optional example," or "optional embodiment," etc., indicates that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of this application, but does not imply that these embodiments illustrate and describe all possible forms of the invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Furthermore, those skilled in the art can combine and integrate the different embodiments or examples described in this specification.

[0082] The present invention has been described in detail above with reference to specific embodiments and exemplary examples. The above description is exemplary and not exhaustive, and is not limited to the disclosed embodiments; the above description should not be construed as a limitation of the present invention. Technical solutions between various embodiments can be combined with each other, but must be based on the ability of those skilled in the art to implement them. When the combination of technical solutions is contradictory or cannot be implemented, it should be considered that such a combination of technical solutions does not exist and is not within the scope of protection claimed in this application. Although embodiments of the present application have been shown and described, various changes, modifications, substitutions, and variations can be made to these embodiments without departing from the principles and spirit of the present application. Those skilled in the art will understand that various other specific changes and combinations of embodiments based on the technical teachings disclosed in this application, without departing from the essence of the present application, are still within the scope of protection defined by the claims of the present invention and their equivalent technical solutions.

Claims

1. A method for treating magnesium-containing highly radioactive waste liquid, characterized in that, include: The magnesium-containing radioactive waste liquid was injected and passed through a primary chromatographic column containing packing material for adsorbing lanthanide and yttrium elements to obtain the first residual liquid; The first residual liquid was injected and passed through a secondary chromatographic column containing strontium-adsorbed packing material to obtain the second residual liquid; The second residual liquid was injected and passed through a tertiary chromatographic column containing packing material for adsorbing cesium to obtain the third residual liquid; Add ammonia to adjust the pH of the third residual liquid to 1-2; The adjusted third residual liquid was injected and passed through a four-stage chromatographic column containing ruthenium-adsorbed packing material to obtain the fourth residual liquid, which was then injected into a precipitation container. Add ammonia to the precipitate container to adjust the pH of the fourth residual liquid to 8-9; Anhydrous oxalic acid was added to the container for precipitation to precipitate magnesium. Separate the precipitated magnesium-containing solid phase.

2. The method for treating magnesium-containing radioactive waste liquid according to claim 1, characterized in that, The magnesium-containing radioactive waste liquid is a 3-5 mol / L nitric acid solution system containing multiple fragmentation elements from Sr, Ce, Cs, Nd, Pr, Te, Sm, Y, Ru, Rh, Zr, Rh, Mo, La, and Ba.

3. The method for treating magnesium-containing radioactive waste liquid according to claim 1, characterized in that, The concentration of magnesium ions in the magnesium-containing radioactive waste liquid is 16–17 g / L.

4. The method for treating magnesium-containing high-radioactivity waste liquid according to claim 1, characterized in that, The device used to transport the magnesium-containing radioactive waste liquid, the first residual liquid, the second residual liquid, the third residual liquid, and the fourth residual liquid is a peristaltic pump, and the column speed of the peristaltic pump is controlled to be 1-3 mL / min.

5. The method for treating magnesium-containing radioactive waste liquid according to claim 1, characterized in that, The primary, secondary, tertiary, and quaternary chromatographic columns are all made of quartz, with an inner diameter of 8–10 mm and a column height of 100–150 mm.

6. The method for treating magnesium-containing highly radioactive waste liquid according to claim 5, characterized in that, The primary chromatographic column is packed with DGA resin with a particle size of 100–150 μm.

7. The method for treating magnesium-containing highly radioactive waste liquid according to claim 5, characterized in that, The column packing material of the secondary chromatographic column is YS10P0 extraction resin with a particle size of 50-100 μm.

8. The method for treating magnesium-containing highly radioactive waste liquid according to claim 5, characterized in that, The column packing material of the tertiary chromatographic column is YC10P0 extraction resin with a particle size of 50-100 μm.

9. The method for treating magnesium-containing highly radioactive waste liquid according to claim 5, characterized in that, The column packing material of the four-stage chromatographic column is CL-7024 extraction resin with a particle size of 100-150 μm.

10. The method for treating magnesium-containing high-radioactivity waste liquid according to claim 1, characterized in that, The amount of anhydrous oxalic acid added is 65-130g.

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