1787results about "Radioactive decontamination" patented technology

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a sealing device and curing equipment. According to the sealing device and the curing equipment provided by the embodiment of the invention, the blocking assembly and the sealing assembly jointly block the first opening formed by the material treatment device, so that the material treatment device is subjected to double sealing, and the internal material treatment environment is more stable; the locking assembly is driven to move in the circumferential direction so as to fix the plugging assembly to the sealing assembly, meanwhile, the locking assembly is arranged to be axially static so as to further reinforce fixation between the plugging assembly and the sealing assembly, and the material containing device can be more stable in the material treatment device; and good sealing performance and stability in the material treatment process are ensured.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a material containing device and curing equipment. The first containing piece and the second containing piece of the material containing device are arranged to be in a detachable and separable form, so that powdery radioactive materials cannot escape from a seam, and meanwhile, after the powdery materials are pressed into solid materials, the first containing piece and the second containing piece can be separated; the solid materials contained in the first containing part can be independently transferred, the material containing device is prevented from being integrally transferred when the solid materials are transferred, and the transferring efficiency of the solid materials is improved. According to the curing equipment, the material containing device is adopted as a material conveying carrier, materials in different stages and states in the curing process can be contained, and leakage of the materials is prevented; meanwhile, in the whole curing process, form transformation of the materials can be achieved without replacing the containing device, the operation process is simplified, material spill caused by replacing the containing device is avoided, and therefore the curing efficiency is improved.

The invention provides a device and method for removing aerosol based on a charged spraying coupling pool washing mechanism, and belongs to the field of nuclear auxiliary systems. The problem that radioactive aerosol particles generated when a radioactive contamination structure in a reactor is cut underwater can be released into the external environment is solved. Wherein the underwater laser cutting assembly is used for cutting a to-be-cut piece; the auxiliary gas chamber is communicated with the laser cutting nozzle; the aerosol charging assembly can enable aerosol particles generated by underwater laser cutting to carry negative charges; the baffle can gather the aerosol particles and guide the aerosol particles to the aerosol charging assembly; the liquid drop charged spraying assembly can spray liquid drops carrying positive charges, the liquid drops carrying positive charges and aerosol particles carrying negative charges can attract each other and fall to the liquid level, and the Venturi washing assembly can extract gas above the liquid level and spray the gas below the liquid level. The device can efficiently remove radioactive aerosol particles generated by cutting and disassembling radioactive contaminated components in a nuclear power plant, and radioactive contamination to the environment is prevented.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to material treatment equipment and curing equipment. According to the material treatment equipment provided by the embodiment of the invention, the powdery material in the material accommodating device is converted into a partially molten state through the material treatment device, and the partially molten material is converted into the solid material through the pressurizing device, so that the powdery material can undergo conversion of different states in the material accommodating device; therefore, powdery materials are converted into solid materials convenient to transfer and process, the operation of replacing a container is omitted, and material processing procedures are saved. According to the curing equipment provided by the embodiment of the invention, the sealing device is used for sealing the material treatment equipment, so that the state transition process of the powdery material has better sealing performance and stability, and the stable quality of the produced solid material is ensured.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a solidification method. According to the method, a conveying and jacking device is used for conveying a material containing device to enable the material containing device to receive powdery materials, a clamping and transferring device and a lifting device are used for conveying the material containing device completing feeding into a material processing device to enable the powdery materials to be partially molten, and a pressurizing device is used for pressing and compacting the partially molten materials; and finally, ingot-shaped solid materials are formed in the material containing device, then the lifting device and the clamping and transferring device are utilized again to transfer the material containing device to the conveying and jacking device so as to transfer the ingot-shaped solid materials, in this way, the process from powder feeding to ingot forming of the materials is conducted in the material containing device, the situation that a material container is replaced in the midway is avoided, and the production efficiency is improved. Operation steps are simplified; and the clamping and transferring device, the lifting device and the conveying and jacking device all participate in the front process and the rear process of material treatment, so that reuse of equipment parts is achieved, and the equipment composition is simplified.

The invention belongs to the technical field of radioactive wastewater treatment, and particularly relates to composite aerogel for adsorbing Cs < + > and Sr < 2 + > in radioactive wastewater under an acidic condition and a preparation method of the composite aerogel. The preparation method of the composite aerogel comprises the following steps: (1) synthesizing ammonium phosphomolybdate / sodium alginate aerogel; (2) growing ZIF-8 on the surface of the ammonium phosphomolybdate / sodium alginate aerogel; and (3) modifying the surface of the material obtained in the step (2) by using potassium permanganate to generate MnO2, thereby obtaining the composite aerogel. The composite aerogel can efficiently adsorb Cs < + > and Sr < 2 + > in wastewater to realize efficient co-adsorption of double ions, and has the advantages of low energy consumption, high selective separation efficiency, capability of carrying out one-step curing separation, no secondary pollution and capability of effectively avoiding the defects of redundant separation operation and large waste liquid amount in a traditional method, and a high-capacity and easily-recycled adsorbent scheme is provided for radioactive wastewater treatment.

The invention relates to an adsorbent and a preparation method and application thereof, the adsorbent comprises a polymer matrix and a nanofiller uniformly embedded in the polymer matrix, the polymer matrix comprises a calcium / boron cross-linked polyvinyl alcohol-sodium alginate blend, and the nanofiller is sulfonic acid / carboxylic acid functionalized graphene oxide; the mass fraction of the nano filler in the adsorbent is 0.05%-0.60%; wrinkles and irregular hole structures are distributed on the surface of the adsorbent. The adsorbent is used for removing tritium in water and is high in adsorption capacity, stable in structure and good in recycling performance. The removal rate of tritium in the single-stage adsorption process is greater than 8.5%, and the removal rate of tritium in the third-stage adsorption process is 19.4-57.7%.

The invention discloses a tritiated waste ash purification method and system based on cooperation of multistage adsorption and low-temperature distillation. The method comprises the following steps: S1, sorting treatment; s2, acid leaching treatment; the waste ash to be treated is subjected to acid leaching treatment, and acid leaching slurry is obtained; s3, carrying out separation treatment; carrying out separation treatment on the acid leaching slurry to obtain acid leaching residues and leachate; s4, adsorption treatment; carrying out adsorption treatment on the leachate to obtain penetrating liquid; s5, catalytic treatment; performing catalytic treatment on the penetrating liquid to obtain tritiated water and catalytic treatment tail gas; and S6, carrying out adsorption treatment on the catalytic treatment tail gas. According to the tritiated waste ash purification method, multi-stage adsorption and low-temperature distillation cooperative treatment is adopted, and the tritiated waste ash purification efficiency is greatly improved. According to the tritiated waste ash purification system, pretreatment, adsorption-catalysis and rectification concentration unit independent packaging are achieved through modular design, and rapid disassembly and assembly and multi-line parallel treatment are supported.

The invention relates to the technical field of transmission, in particular to an annular transmission mechanism and a nuclear waste glass curing forming device. In the annular transmission mechanism, a reference shaft and a ratchet wheel are coaxially and fixedly connected, and the reference shaft is provided with a matching end used for transmission matching. The blocking arm is fixedly connected to the end, away from the reference shaft, of the swing arm. The first pawl is rotationally matched with the end, away from the reference shaft, of the swing arm and matched with a torsional spring so that the first pawl can be attached to the ratchet wheel. When the first pawl reciprocates along the ratchet wheel, the ratchet wheel can be intermittently driven. When the first pawl does reciprocating motion along the ratchet wheel, ratchets of the ratchet wheel can periodically push the first pawl to the side where the blocking arm is located, so that the first pawl can periodically extrude the pressing part. The temperature control can be synchronously completed while transmission is realized, and the matching degree between the transmission and the temperature control is further improved.

The invention relates to a universal method for co-adsorbing perrhenate or pertechnetate by using cationic dye modified activated carbon, and belongs to the technical field of water treatment. In the system provided by the invention, the cationic dye modified activated carbon is used as an adsorbent of perrhenate or pertechnetate, and the cationic dye / activated carbon composite material realizes efficient removal of pollutants by co-adsorbing the perrhenate or pertechnetate in sewage. According to the invention, 12 activated carbon is used as a porous carrier, and after five different cationic dyes are respectively adsorbed, perrhenate radicals can be effectively adsorbed. Particularly, after methylene blue dye is adsorbed, perrhenic acid radicals can be quickly adsorbed within an extremely short time, and the adsorbent has the advantages of large adsorption capacity, good pH stability, high selectivity, good radiation resistance, low cost and the like, and can be applied to actual environmental sewage.

The invention discloses a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The shot blasting particle internal circulation regeneration system comprises a smelting furnace, a melting and pumping machine and a shot blasting machine which are sequentially used according to a closed-loop sequence, a smelting cavity is formed in the smelting furnace; the melt extraction machine comprises a bottom moving mechanism, a middle lifting mechanism and an upper executing mechanism which are sequentially connected from bottom to top. The upper executing mechanism comprises a rotary driving assembly and a melting tap; the rotary driving mechanism is mounted at the upper end of the middle lifting mechanism and is associated with the melting tapping head so as to drive the melting tapping head to rotate, molten steel in a smelting cavity of the smelting furnace is thrown out in a liquid column form when the melting tapping head rotates, and shot blasting particles are obtained after the liquid column is cooled and solidified in the flying process and falls to the ground; when the shot blasting machine works, shot blasting particles manufactured by a melting and pumping machine are used. According to the method, an internal recycling regeneration system of radioactive contamination metal and shot blasting particles is constructed, the radioactive contamination metal is converted into self-consumption shot blasting particles, recycling regeneration is achieved, and the increment of radioactive waste is remarkably reduced.

The invention relates to a waste liquid treatment device for automatically separating radionuclides. The waste liquid treatment device comprises a first waste liquid collection passage and a second waste liquid collection passage, an upstream liquid supply channel shared by the two channels comprises an injection pump and a multi-way valve, and the injection pump inputs liquid into the multi-way valve. The first waste liquid collecting channel directly guides cleaning liquid, replacement liquid and the like which do not need to be reserved into a waste liquid barrel through a first output port of the multi-way valve. The second waste liquid collecting channel is sequentially connected with a plurality of resin columns, a waste liquid tank, a peristaltic pump and a waste liquid barrel through a second output port of the multi-way valve, waste liquid generated by the resin columns firstly enters the waste liquid tank for temporary storage, and when the liquid level of the waste liquid tank reaches a preset threshold value, the peristaltic pump automatically pumps and discharges the waste liquid into the waste liquid barrel for centralized collection. The device can distinguish reserved liquid from waste liquid according to steps, realizes automatic flow division, temporary storage and discharge of the waste liquid, avoids manual pouring of the waste liquid halfway, ensures continuous operation of a long-time and multi-channel separation process, and reduces the risk of personnel exposure in a radioactive waste liquid treatment process.

The invention relates to a shot blasting particle internal circulation regeneration method for decontaminating radioactive contaminated metal, which is applied to a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The invention discloses a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The shot blasting particle internal circulation regeneration system comprises a smelting furnace, a melting and pumping machine and a shot blasting machine which are sequentially used according to a closed-loop sequence, the method comprises the following steps: raw material pretreatment; smelting and decontaminating the raw materials; preparing pills by a melt extraction machine; shot-blasting and decontaminating the raw materials; and after decontamination, smelting and pelleting. The method has the advantages that radioactive contamination metal is converted into self-consumption shot blasting particles, cyclic regeneration is achieved, radioactive waste increment is remarkably reduced, near-zero emission of nuclear facility decommissioning waste is promoted, and the requirement for minimization of IAEA radioactive waste is met.

To provide a technique capable of contributing to environmental load reduction while securing performance as a water purification filter.SOLUTION: The water purification filter 11 satisfies at least one of the conditions that the increase in CO2 on the ground surface due to CO2 released at the time of disposal is not more than 240L per kilogram and that the use rate of petroleum-derived raw materials is not more than 15%.SELECTED DRAWING: Figure 3

The invention provides a method for accurately regulating and controlling pores of an MXene material by utilizing a phosphonic acid ligand, which mainly comprises the following key steps of: directionally removing a main group element (A) layer of an MAX precursor by wet etching to obtain lamellar MXene, and then introducing a protonated quaternary amine compound intercalator to strip the MXene. And finally, carrying out functional modification and conversion by adopting a phosphonic acid ligand, and stably introducing phosphonic acid groups between layers and on the surface of MXene through solvothermal reaction to realize accurate regulation and control of interlayer spacing. The prepared material can realize efficient adsorption of uranyl in an acidic environment, shows high selectivity, high adsorption capacity and good acid stability and regeneration capacity to uranyl, provides a stable and efficient selective adsorption solution for treating high-acidity uranium-containing nuclear wastewater, and has a remarkable industrial application prospect.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to curing equipment. According to the curing equipment provided by the embodiment of the invention, the powdery materials are conveyed into the material containing device through the vacuum feeding device, and the material containing device is transferred to the lifting device through the clamping and transferring device, so that the material containing device is conveyed into the material processing device through the lifting device; the sealing device is used for sealing the material treatment device, so that the material reaction process is carried out in an environment with relatively good sealing performance; the pressurizing device is used for compacting the materials so as to obtain solid materials which are easier to transfer and process compared with powdery materials; the vacuum feeding device, the conveying and jacking device, the clamping and transferring device, the lifting device, the material treatment device and the pressurizing device are fixed to different positions of the body, enough space is provided for all treatment links of materials, the operation sequence of curing treatment is met, the process is simplified, and the treatment efficiency is improved.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

This invention has an object to provide a method for producing a beryllium solution, the method being novel and having high energy efficiency. The method (M10) for producing a beryllium solution includes a main heating step (S13) of dielectrically heating an acidic solution containing a starting material so as to generate a beryllium solution, the starting material being beryllium or a substance containing beryllium.

To dismantle a nuclear facility affected by a severe accident in an underwater environment by submerging the facility in water so that the water shields radiation from the nuclear facility.SOLUTION: The method for dismantling a nuclear facility includes: stopping water leakage at a leakage portion by using a particle dispersion liquid containing fine particles having a specific gravity greater than that of water, when dismantling a nuclear facility in which the water leakage portion has occurred due to a severe accident; and submerging at least a part of the nuclear facility. This makes it possible to submerge a reactor well and to perform dismantling work from above a reactor building.SELECTED DRAWING: Figure 1

Provided in the present invention are a preparation method for a crown ether covalent organic framework material, and the use thereof in iodine adsorption. In the present invention, an 18-crown-6-ether group is introduced into the structure of a covalent organic framework (COF) material for iodine adsorption work. The covalent organic framework material can form a one-dimensional pore channel structure in order, and the 18-crown-6-ether can be selectively complexed with iodine molecules, thereby achieving the purpose of efficient iodine adsorption. The material can perform specific iodine adsorption from high-temperature iodine steam, and the iodine steam adsorption capacity of the COF material is as high as 5.56 g / g. The COF material has a high adsorption capacity, is easy to prepare and simple to operate, has a high adsorption efficiency, and is particularly suitable for adsorbing and separating radioactive iodine in the nuclear industry.

The invention discloses a covalent organic framework with oxidation-reduction activity and a bionic nano-channel structure as well as a preparation method and application of the covalent organic framework, and belongs to the technical field of environmental protection. According to the preparation method, 2, 4-dihydroxybenzene-1, 3, 5-tricarboxaldehyde and 2, 5-bis (allyloxy) terephthaloyl hydrazine are taken as raw materials, a two-dimensional covalent organic framework with oxidation-reduction activity is synthesized, and then a sulfonic acid group with negative charges is covalently grafted, so that a functional material with a bionic nano-channel structure is formed. The material has regular porous channels and rich functional sites, the porous channels provide efficient mass transfer paths and adsorption spaces for uranyl ions, and the functional sites realize specific recognition of the uranyl ions through oxidation-reduction reaction and electrostatic interaction, so that the material shows synergistic advantages of strong selectivity, high adsorption capacity and rapid adsorption kinetics on uranium. The method is simple and low in cost, and the prepared material is clear in structure, good in hydrophilicity, capable of efficiently adsorbing uranyl ions and good in application prospect.

The nuclear power station pool foreign matter collecting and transferring device comprises a shielding container and a collecting basket, the shielding container comprises a first containing cavity and is provided with shielding materials capable of shielding rays, and the collecting basket comprises a second containing cavity and can be arranged in the first containing cavity; and drainage structures are arranged on the collecting basket and the shielding container. According to the nuclear power station pool foreign matter collecting and transferring device, after the foreign matter is collected, the foreign matter does not need to be transferred underwater again, the collecting basket can be placed in the shielding container or the foreign matter is directly placed in the shielding container, and the shielding container can shield the foreign matter with high radiation dose; radiation of foreign matters to human bodies and the environment can be reduced, the operation risk of personnel is reduced, and use is simpler and more convenient; the shielding container and the collecting basket can be used in cooperation and can also be used independently, and on-site flexible use is facilitated; the arrangement of the drainage structure facilitates the discharge of radioactive residual water in the foreign matters, so as to reduce the foreign matter collection and transfer weight.

To provide a radioactive waste discharge plan preparation support system capable of efficiently processing and managing radioactive waste.SOLUTION: A radioactive waste discharge planning support system includes a storage unit that stores information on an amount of radioactivity of radioactive waste and a measurement date of the amount of radioactivity, and a discharge planning unit that predicts a time when the amount of radioactivity becomes equal to or less than a specified value based on the information on the amount of radioactivity and the measurement date of the amount of radioactivity stored in the storage unit for the radioactive waste having the amount of radioactivity equal to or more than the specified value, and creates a discharge plan of the radioactive waste based on the predicted time.SELECTED DRAWING: Figure 1

The invention discloses a method and device for reusing boric acid in waste liquid of a nuclear power plant, and the method comprises the following steps: carrying out the pretreatment of radionuclides in the waste liquid of the nuclear power plant, and obtaining first radioactive waste liquid; carrying out nanofiltration on the first radioactive waste liquid to respectively obtain separated first produced water and first concentrated water; the first produced water is subjected to first boron concentration through reverse osmosis, separated second produced water and second concentrated water are obtained, the second concentrated water is a boric acid concentrated solution, and the second concentrated water is reused in the nuclear power plant; the second produced water is subjected to second-stage boron concentration through second-stage reverse osmosis, third produced water and third concentrated water which are separated are obtained, and the third produced water is produced water meeting the preset discharge condition. According to the method, deep purification treatment is conducted on the waste liquid of the nuclear power plant, resource recycling and reuse of boric acid are achieved while the emission requirement is met, and the reuse concentration of boric acid of different reactor types can be met by adjusting technological parameters.

The present invention relates to a dispersant for graphite and graphene and its application. The composition is a synergistic combination of alkyl sulfosuccinate and polyalkylene glycol. Appropriate adding amount thereof can quickly and easily disperse graphite and graphene in the medium, improve its dispersion uniformity and stability, delay its sedimentation, and inhibit its re-accumulation. Furthermore, the present invention can apply graphite and graphene to other media besides non-water-based or organic solvents. The composition of the present invention does not contain flammable volatile chemicals, any fluorine-, silicon- or phosphorus-based compounds, or any aromatic substances. The present invention can not only reduce environmental pollution but also improve the operational safety of relevant personnel.

The invention discloses a radioactive air filtering device, and relates to the technical field of radioactive gas treatment. Comprising a particle impurity removal mechanism, a spraying mechanism and an adsorption mechanism, the particle impurity removal mechanism comprises an impurity removal barrel, and an efficient air filter screen is rotationally arranged in the impurity removal barrel; the spraying mechanism comprises a washing tank, a spraying pipe is rotatably arranged in the washing tank, a plurality of spraying heads are fixedly arranged on the lower surface of the spraying pipe, a rotary movable pipe is rotatably arranged on the upper surface of the washing tank, and the bottom end of the rotary movable pipe extends into the washing tank and is fixedly connected with the upper surface of the spraying pipe. By arranging the particle impurity removal mechanism, radioactive air can be primarily filtered through a cylindrical efficient air filter screen in an impurity removal barrel, large-particle dust and impurities in the radioactive air are effectively removed, and meanwhile radioactive aerosol in the radioactive air can be captured and adsorbed through the efficient air filter screen; and preliminary filtration of radioactive gas is realized.

To provide a container dismantling device which improves workability of container dismantling work.SOLUTION: A container dismantling device for dismantling a container contaminated with radioactive substances is provided, the device comprising a base supported at the bottom inside the container, a support member disposed along a vertical direction and supported by the base at a bottom thereof, and a cutting device supported by the support member in such a way that the cutting device is movable along the vertical direction and movable in the circumferential direction.SELECTED DRAWING: Figure 2

The invention discloses carboxyl-rich chitosan gel and preparation thereof and separation and enrichment of radioactive element thorium, and the method comprises the following steps: mixing and dissolving chitosan, water and glacial acetic acid, adding 1, 2, 3, 4-butanetetracarboxylic acid, and uniformly mixing; heating at 80 DEG C to completely volatilize moisture, and heating to 100 DEG C for reaction to obtain a solid product; taking out a solid product, soaking the solid product in deionized water, and performing freeze drying treatment to obtain the carboxyl-rich chitosan gel, namely the CCS-BTCA xerogel. The problems that an existing adsorbent is poor in stability and low in adsorption activity are solved, the prepared material has the high adsorption rate, the optimal adsorption effect can be achieved at the temperature of 298 K and the pH value of 3, the adsorption capacity is 228.9 mg / g, and the maximum theoretical adsorption capacity can reach 279.4 mg / g.

The invention discloses a mixing and clarifying tank, a liquid level adjusting method thereof and a nuclide recovery and extraction system, which can adjust the liquid level of a two-phase interface in an overflow chamber by adjusting the air pressure difference between the overflow chamber and a clarifying chamber through an air pressure adjusting assembly, thereby avoiding the increase of maintenance workload of the mixing and clarifying tank due to the increase of mechanical moving parts. The mixing and clarifying tank comprises a clarifying tank body and a liquid level adjusting device. A sealing top cover is arranged at the top of the clarifying tank body, and the clarifying tank body comprises a mixing chamber, a clarifying chamber and an overflow chamber which are sequentially communicated from front to back; the overflow chamber is defined by a front heavy-phase flow baffle, a rear sealing baffle and a sealing top cover. The liquid level adjusting device comprises an air pressure adjusting assembly. The air pressure adjusting assembly is arranged in the overflow chamber and used for adjusting the air pressure difference between the overflow chamber and the clarifying chamber so as to adjust the liquid level difference between the highest liquid level in the overflow chamber and the liquid level of the two-phase interface in the overflow chamber, and then the liquid level of the two-phase interface in the overflow chamber is adjusted to the target liquid level.

The invention relates to the technical field of radionuclide separation, in particular to an Eu (III) / An (III) separation method based on a zirconium phosphonate-based metal organic framework adsorbent, which comprises the following steps: adding the zirconium phosphonate-based metal organic framework adsorbent into an Eu (III) and / or An (III) nuclide-containing aqueous solution with the acid concentration of 0.001-3M to carry out adsorption reaction, and then carrying out solid-liquid separation, wherein the zirconium phosphonate-based metal organic framework adsorbent is a zirconium phosphonate-based metal organic framework material exchanged by metal cations M; the metal cation M is selected from one of alkali metal ions, alkaline earth metal ions or divalent transition metal ions. According to the invention, the interlayer chemical properties of the material are regulated and controlled through ion exchange, so that the adsorbent has ultrahigh selectivity, rapid adsorption kinetics, high adsorption capacity and excellent structural stability on trivalent actinide / simulated nuclides in extremely high-acid, high-salt and intense-radiation environments; the key problems of low separation efficiency and poor stability in a high-acid complex system in the prior art are solved, and the method is suitable for treating high-level liquid waste.