271 results about "Radioactive contamination" patented technology

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 invention relates to the technical field of nuclear facility decontamination, and provides a multiphase carbon dioxide decontamination recovery system and a decontamination recovery process, the decontamination recovery system comprises a dry ice supply loop, a high pressure CO2 supply loop, a decontamination loop and a CO2 recovery loop; the tail ends of the dry ice supply loop and the high-pressure CO2 supply loop are communicated with the decontamination loop; the tail end of the decontamination loop is communicated with the CO2 recovery loop; the decontamination recovery process comprises the following steps: taking ethanol or acetone as an entrainer, dissolving a decontaminating agent by using supercritical carbon dioxide to carry out soaking decontamination pretreatment on the radioactive contamination surface, taking high-pressure carbon dioxide as power, carrying dry ice particles and spraying out from a high-pressure spraying pipe to impact the radioactive contamination surface, and recycling the radioactive contamination surface. Recycling of carbon dioxide is realized through two-stage depressurization separation and first-stage filtration; the carbon dioxide radioactive decontamination capability and efficiency can be remarkably improved, the secondary waste generation amount is reduced, and the personnel irradiation risk is reduced.

The invention discloses a positive pressure antifouling gamma-ray spectrum automatic monitoring square cabin, and relates to the technical field of nuclear emergency monitoring and square cabins, the positive pressure antifouling gamma-ray spectrum automatic monitoring square cabin comprises a cabin body, a transition cabin is arranged in the cabin body, the transition cabin divides the interior of the cabin body into a sealed measurement cabin and a sample preparation cabin, and one side of the transition cabin is provided with an air-tight door capable of communicating the sealed measurement cabin with the sample preparation cabin; a sample conveying cabin used for allowing a sample to go in and out of the sealed measuring cabin and the sample preparation cabin is arranged on the side, away from the airtight door, of the inner wall of the transition cabin, the cabin body is overall designed into three areas, and the to-be-detected sample treatment area and the electric refrigeration high-purity germanium gamma-ray energy spectrometer are effectively isolated; filtered clean air is continuously introduced into the measurement cabin, the pressure in the sealed measurement cabin is maintained to be greater than the external pressure, the requirements of air cleanliness and positive pressure are ensured, and the background of the surrounding environment of the electric refrigeration high-purity germanium gamma-ray energy spectrometer is prevented from being changed after external radioactive pollution air enters the sealed measurement cabin, so that the measurement is prevented from being influenced.

The invention discloses a nuclear accident emergency three-layer coupling network model and a construction method, and relates to the crossing field of nuclear accident emergency management and complex system risk simulation. The nuclear accident emergency three-layer coupling network model comprises an RMN layer which is used for simulating the dynamic diffusion process of radionuclides leaked by a nuclear accident in the atmosphere; the IN layer is used for constructing a spatial distribution and dependency relationship network of infrastructures; the EN layer is used for topologically defining a command or cooperation relationship of the emergency organization; according to the three-layer network coupling mechanism, when RDR of a middle grid is larger than or equal to RDRmax-1, IN-layer nodes in the middle grid at the same position are marked to be in a damaged state; and quantifying the bidirectional dependence density of the IN layer and the EN layer through the coupling strength epsilon. The method is used for predicting the direct risk of radioactive contamination in a nuclear accident and the secondary risk caused by emergency evacuation, revealing the risk evolution law, quantifying the risk diffusion scale, determining key influence factors, and providing a theoretical basis for formulating an emergency strategy.

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 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.

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.

The invention relates to a gamma radiation field simulation method, a gamma radiation monitoring simulation training system and application of the gamma radiation field simulation method and the gamma radiation monitoring simulation training system, and a three-dimensional simulation gamma radiation field and the gamma radiation monitoring simulation training system are constructed based on the Beidou positioning technology, the computer and communication technology and the action law of gamma rays and substances. The simulation training system is composed of a guide center, a Beidou positioning and communication base station, a simulation training ground, a simulation gamma radioactive source and a simulation gamma radiation monitor. The parts of the system exchange information through wired or wireless communication. The simulated gamma radiation source and the simulated gamma radiation monitor both have an accurate positioning function, and the simulated gamma radiation monitor also has a function of calculating and obtaining a gamma radiation dose rate and a dose. The problem of simulation and monitoring simulation training of a space gamma radiation field generated by a plurality of real gamma radioactive sources is solved, so that the effects of simulation training such as searching for more than one gamma radioactive source, determining gamma radioactive contamination boundaries and measuring personal accumulated doses are close to reality.

The present invention relates to the technical field of filament cathode materials, and in particular to a tungsten alloy wire, a preparation method and use thereof, and a tungsten carbide alloy filament. The tungsten alloy filament comprises the following components: the tungsten alloy comprises the following components: 0.0005-0.3wt% carbon element, 0.25-2.6wt% M element, 0.05-0.5wt% oxygen element, the remainder being tungsten element and inevitable impurities, and the components do not contain thorium element; the initial recrystallization temperature of the tungsten alloy wire is 48%Fc-56%Fc, and / or, the average size of its 80%Fc recrystallized grains is (1-15) μm. The tungsten alloy wire does not contain thorium element and does not have radioactive pollution problem. Its initial recrystallization temperature is between 48%Fc and 56%Fc. Its processing performance is greatly improved compared with thoriated tungsten material. Compared with thoriated tungsten wire, the wire has fewer flaw detection crack points. It is used as the matrix of tungsten carbide alloy filament. After carburization, the tungsten matrix has fine grains. The filament is not easy to break during the production and use of magnetron coils (i.e., filaments), and the production yield and quality are improved.

Advances in creating carbon-free emissions continue with nuclear power. This invention aims to achieve an environment with less radioactive pollution from pebble bed reactors. This invention uses stainless steel, niobium, or ferroniobium which does not form dust like carbon pebbles. The pebble bed reactor coolant will pass over the coated pebbles and not pick up radioactive dust as in old pebble models. This new design is more complicated and costs more than current designs. However, the cleanup of a used pebble bed reactor will be far less, and the health of the workers will be greatly improved through use of this invention. This practical design will enable pebble bed reactors to become approved at a faster rate than old designs.

The invention discloses a method for determining the absolute activity of Bst DNA polymerase, which comprises the following steps: by taking annular single-stranded DNA as a template, in a reaction system containing an amplification primer and dATP, initiating an extension replication reaction by using Bst DNA polymerase to be detected, and consuming dNTPs in the reaction system; the consumption of dATP is calculated according to a pre-constructed standard curve f1 representing the relationship between the concentration of dATP and the fluorescent value, the concentration of Bst DNA polymerase is calculated through a pre-constructed standard curve f2 representing the relationship between the concentration of Bst DNA polymerase and the consumption of dATP, and finally the absolute activity of the Bst DNA polymerase to be detected is calculated according to the absolute activity definition of Bst DNA polymerase. The method is free of radioactive contamination, and has the advantages of determination of the polymerization activity of the Bst DNA polymerase, absolute constant activity, simplicity and convenience in operation, rapidness, sensitivity, low cost and the like.

The present invention discloses a method for adsorbing radioactive iodide ions in radioactive wastewater, which includes the following process: adding silver copper oxide to the radioactive wastewater, and the iodide ions in the radioactive wastewater react with the silver copper oxide, so that the concentration of iodide ions in the radioactive wastewater is reduced. The adsorption of radioactive iodide ions in radioactive wastewater by the silver copper oxide of the present invention belongs to chemical adsorption, which has the characteristics of fast adsorption speed, high adsorption efficiency and adsorption capacity, the adsorbed product is not easy to desorb, is easy to solidify and dispose, is convenient for recycling, is convenient to use and is not easily affected by interfering ions and pH. The silver copper oxide has a strong selective adsorption effect on iodide ions in the wastewater environment of long half-life radioactive element iodine, and can effectively improve the radioactive pollution of iodine in the water environment, and solve the main problems of spent fuel reprocessing and radioactive water pollution.

The invention relates to the technical field of muon imaging, in particular to a cosmic ray muon distribution three-dimensional reconstruction method and system.The method comprises the steps that a monitoring environment is built, an object to be detected is placed at the circle center of an annular guide rail, two lifting platforms are fixed to the annular guide rail, supporting frames are installed on the lifting platforms respectively, and detector panels are arranged on the supporting frames; detecting position information left when muons penetrate through a detector panel, calculating muon tracks and muon flux to obtain angular distribution, and establishing point-surface images of the angular distribution and flux distribution of the muons based on the muon tracks; performing weighted summation to obtain a face-to-face image; and compressing Monte Carlo output muon position information by using an auto-encoder, obtaining momentum, time and position information of muons, and extracting angular distribution in a preset area for classifying the angular distribution and the position information according to the interval. The method is suitable for various use scenes, belongs to passive detection, does not generate radioactive contamination, and can replace industrial CT with radioactive contamination in a specific scene.

The invention discloses a pig farm sand table decontamination and pollutant monitoring early warning system, and relates to the field of pig farm early warning. Comprising a multi-modal sensor array module which comprises a biological pollution detection unit, a chemical pollution detection unit and a radioactivity detection unit and is used for collecting pig house environment and multi-dimensional pollution data in the decontamination process in real time; and the digital twinborn decontamination deduction module renders a pollution diffusion cloud picture in real time, superposes virtual actions of decontamination equipment and predicts a pollutant diffusion path. According to the pig farm sand table decontamination and pollutant monitoring and early warning system, high-frequency acquisition of biological, chemical and radioactive pollution is realized through a multi-mode sensor array, multi-dimensional pollution feature vectors are generated through wavelet transformation and Kalman filtering preprocessing, pollution risk levels are output in combination with a fuzzy logic algorithm, yellow / orange / red three-level accurate early warning is realized, and the accuracy of pig farm sand table decontamination and pollutant monitoring and early warning is improved. Compared with traditional single-index early warning, the comprehensive early warning accuracy is improved, and meanwhile the missed alarm rate is reduced.

A tungsten alloy wire, a preparation method therefor and a use thereof, and a tungsten carbide alloy filament. The tungsten alloy wire comprises the following components: 0.0005-0.3 wt% of a carbon element, 0.25-2.6 wt% of an M element, 0.05-0.5 wt% of an oxygen element and the balance being a tungsten element and inevitable impurities, and does not comprise a thorium element; and the initial recrystallization temperature of the tungsten alloy wire ranges from 48 %Fc to 56 %Fc, and / or the average size of 80 %Fc recrystallization grains is 1-15 μm. The tungsten alloy wire does not comprise the thorium element, does not cause radioactive contamination, has the initial recrystallization temperature ranging from 48 %Fc to 56 %Fc, and has the processing performance greatly improved compared with that of a thorium-containing tungsten wire; compared with a thorium-containing tungsten wire, the tungsten alloy wire has less flaw detection crack points, when the tungsten alloy wire is used as a substrate of a tungsten carbide alloy filament, grains of the carbonized substrate are fine, the filament is not easy to break in the production and use of a magnetron coil, and the production yield and quality are improved.

The invention discloses an electrochemical denucleation decommissioning facility oxide layer method based on a synergistic acidic electrolyte, and relates to the technical field of cleaning. The method comprises the following steps: by taking a polluted metal component as an anode and an inert electrode as a cathode, immersing the polluted metal component into a synergistic acidic electrolyte of a low-concentration acidic medium, and stripping an oxide layer on the surface of the polluted metal component until a clear grain boundary is exposed at the temperature of lower than 40 DEG C in a high-voltage direct-current electrolysis mode. By developing a synergistic enhanced acidic electrolyte system, high decontamination rate is realized in a low-concentration sulfuric acid medium, radionuclide stripping is accurately controlled to avoid matrix pitting corrosion damage, and high-valence nuclides in a compact oxide layer are deeply removed, so that the decontamination efficiency is improved. Finally, an efficient, low-damage and stable-process radioactive contamination metal treatment scheme is provided for nuclear facility decommissioning engineering. The method is suitable for removing radioactive contamination oxidation layers on the surfaces of the inner walls of stainless steel pipelines and reactor containers in nuclear facility decommissioning projects, and radionuclides are enriched in the oxidation layers.

The invention discloses a storage ball type spent fuel inter-process dynamic management system, and relates to the technical field of spent fuel management, the storage ball type spent fuel inter-process dynamic management system comprises a storage assembly which comprises a cylindrical storage tank with a storage cavity inside and an opening at the top, and a protective cover which is arranged at the opening at the top of the storage tank and is used for sealing the storage tank; the pipe collecting assembly comprises a spent fuel storage room with the hollow interior, and a net rack vertical shaft extending towards the position below the earth surface is arranged in the spent fuel storage room. Due to the design of the mortise and tenon joint structures of the upper wall body and the lower wall body, the strength and the shielding effect of the wall bodies are guaranteed, and convenience can be provided when equipment is dismantled in the later factory site decommissioning stage; the storage tank is stored in the net rack vertical shaft located underground, the shielding layers are arranged at the two ends of the storage tank, the radioactive contamination risk is effectively reduced, and meanwhile the space of the net rack vertical shaft provides air for the storage tank so that convection cooling can be facilitated; transfer of the storage tank is carried out in a ground translation mode, and spent fuel hoisting accidents in an existing transfer process can be avoided.

This invention discloses a method for estimating radioactive release during the preparation of radioactive metal waste, comprising the following steps: (1) conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; (2) setting up monitoring points in the radioactive metal waste areas with different pollution levels, and calculating the radioactive residue in the metal waste based on the monitoring data; (3) calculating the total release of each nuclide in the metal waste based on the above-mentioned radioactive residue in the metal waste and the obtained concentration data of radionuclides in the metal waste. By conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; setting up monitoring points in the delineated areas to obtain the radioactive residue in the metal waste; and calculating the total release of each nuclide using formulas, the process is simple, easy to operate, and can obtain effective data on the total release of nuclides, providing data support for the preparation of radioactive contaminated metal waste and supporting the assessment of the dose caused by contaminated metal waste to the public.

The application relates to an information-based decontamination square cabin integrated system, and relates to the field of the decontamination square cabin. The system comprises a cabin body, an information collection module arranged at the entrances of each walking decontamination area and stretcher decontamination area and used for collecting personal information of wounded personnel, a first injury condition collection module used for collecting the radioactive contamination value of each wounded personnel, a decontamination control module used for controlling the on-off of a medicament nozzle and a clean water nozzle in each walking decontamination area and stretcher decontamination area, and an electronic device used for determining the medicament flushing time length and the clean water flushing time length of the wounded personnel based on the radioactive contamination value of the wounded personnel, sending a control signal to the decontamination control module according to the decontamination time length, so that the decontamination control module controls the medicament nozzle in the area where the wounded personnel are located to operate for the medicament flushing time length, and controls the clean water nozzle to operate for the clean water flushing time length. The application can make the square cabin perform the decontamination operation on the wounded personnel for a proper time length, so as to improve the decontamination efficiency.

The invention relates to a method for carrying out capping rate analysis on mRNA (messenger ribonucleic acid) by using an unmarked RNase H probe and LC-MS (liquid chromatography-mass spectrometry), and belongs to the technical field of biology. A DNA-RNA probe is designed according to a to-be-detected RNA sequence, RNA molecules are cut by utilizing the specificity of RNase H, short segments are separated by virtue of specific adsorption of a silica gel column, and the molecular weight and relative proportion of a cut RNA product are detected by utilizing an LC-MS method, so that the capping efficiency is determined, quantitative detection of the RNA capping efficiency is realized, radioactive contamination can be avoided, and the detection accuracy is high. The operation is simple and the cost is low.

The utility model provides a wearable device capable of preventing urine leakage and used for nuclear medicine imaging examination. The wearable device is composed of a protective pad and a wearable structure. The protective pad comprises a waterproof bottom layer and a water-absorbing surface layer; the wearing structure is of a T-shaped structure and is composed of a wearing body, a left wing and a right wing, the two ends of the outer side of the lower edge of the wearable body are connected with the inner sides of the left wing and the right wing through first pasting areas. The rear part of the wearable structure is connected with the upper surface of the water-absorbing surface layer through a second pasting area; drawing structures are arranged at the upper end and the lower end of the protective pad and penetrated by drawing ropes. The radioactive urine absorption device can basically absorb radioactive urine overflowing from all examinees, so that the examination bed board is prevented from being subjected to radioactive contamination, radioactive secondary pollution can be prevented from being generated when a polluted wearing device is treated, and the structure of the radioactive urine absorption device is easy to disassemble and replace and convenient to use.

The present application relates to the technical field of nuclear power plant ventilation purification, and discloses an equivalent test bench for evaluating the performance of iodine removal and a verification method, the verification method comprising: obtaining three carbon samples with different iodine removal efficiencies; based on the three carbon samples, performing a first test under the French standard system, a second test under the American standard system, a third test under different humidity conditions, and a fourth test under accident conditions on the same test bench, and recording the corresponding test results; comprehensively analyzing the test results corresponding to the four tests to obtain the test equivalent relationship between the French standard system and the American standard system, the numerical relationship between humidity and iodine removal efficiency, and the change rule of iodine removal efficiency after accident radiation. The present application accurately establishes the quantitative relationship between the French standard and the American standard, humidity and iodine removal efficiency, and accident radiation and performance decay based on a unified test bench; provides a unified scientific basis for the performance evaluation of iodine adsorbers in nuclear power plants, and improves the safety and reliability of gaseous radioactive contamination protection of nuclear facilities.

The invention relates to a carbonate eluting agent and a preparation method and application thereof, and belongs to the technical field of radionuclide contaminated soil remediation and treatment. The carbonate eluting agent provided by the invention comprises carbonate, bicarbonate, an oxidizing agent, a eutectic solvent and an anionic surfactant, the oxidizing agent comprises sodium chlorite and hydrogen peroxide; the eutectic solvent comprises choline chloride and urea; the molar ratio of the carbonate to the bicarbonate to the hydrogen peroxide is (0.005 to 0.025) to (0.025 to 0.1) to (0.3 to 0.5); the molar ratio of choline chloride to urea in the deep eutectic solvent is (0.8-1.2): (0.8-1.2). The prepared eluting agent is green and mild, the removal rate of uranium in soil is remarkably increased by regulating and controlling the appropriate component proportion, and the eluting agent has important significance on safe development of the nuclear power industry and protection and treatment of the radioactive pollution environment.

The invention discloses a nuclear power radiation monitoring system and method.The nuclear power radiation monitoring system comprises an access control system, a radiation monitoring system, a cold dressing system, a channel monitoring system and a statistical prediction system.The access control system is arranged at an inlet and an outlet of a nuclear power plant, and the channel monitoring system is arranged in a channel of the nuclear power plant; the cold dressing system is arranged in the cold dressing room; the access control system is used for judging whether the personnel can enter or exit from the radiation control area according to the accumulated radiation value; the radiation monitoring system is used for collecting real-time radiation values and vital sign data of personnel; the cold dressing system is used for prompting dressing information and distributing dosimeters; the channel monitoring system is used for collecting radioactive contamination values and environmental radiation values of personnel in a channel; and the statistical prediction system is used for recording personnel identity information and predicting a future radiation value of the personnel.

The present invention relates to a method for the decontamination of radioactively contaminated concrete, comprising the following steps: a) feeding lumpy, radioactively contaminated concrete into a reactor, b) feeding a liquid process medium into the reactor before, during and / or after feeding the concrete into the reactor, c) electrohydraulic crushing of the concrete in the liquid process medium, d) separation of the crushed concrete from the liquid process medium, e) treatment of at least a portion of the crushed concrete with a mineral acid or a mixture of mineral acids and subsequent separation of the mineral acid or the mixture of mineral acids from the crushed concrete, f) partial or complete separation of radioactive nuclides from the separated mineral acid or the mixture of mineral acids and / or g) partial or complete separation of radioactive nuclides from the process medium.

1. The name of the product of this design: Radiation detection equipment (quick disassembly and assembly). 2. Purpose of the product with this design: It is used to be carried on a small drone for emergency source search, nuclear accident investigation and large-area radioactive contamination measurement on the ground. 3. The design key point of this appearance design product lies in the shape. 4. The picture or photo that best illustrates the design points: three-dimensional picture.

The invention provides a fungus crust decontaminant for surface radioactive contamination removal and a preparation method and application thereof.The fungus crust decontaminant comprises konjac glucomannan, carboxymethyl cellulose, glycerol, a fungus microbial agent with fungus thalli being aspergillus niger A3 and distilled water, and all the components are natural or biodegradable substances; by optimizing the proportion, the detergent can effectively remove radioactive substances on the surface of an object through fungal crust and reduce the risk of radioactive contamination, the use method is simple and convenient, harmful conditions such as high temperature, high pressure or strong acid and strong alkali are not needed in the decontamination process, the environmental protection property and safety of the treatment process can be ensured, secondary pollution to the environment is avoided, and the environment-friendly effect is achieved. The method is suitable for treating various material surfaces, and has the advantages of high efficiency, environmental protection and safety.

The invention provides a composite membrane for separating 226Ra and 210Pb as well as a preparation method and application thereof, and relates to the technical field of radioactive ion extraction and separation, and the preparation method comprises the following steps: mixing polyacrylonitrile, crown ether and ionic liquid to obtain a spinning solution, and spinning the spinning solution into a membrane to obtain the composite membrane. Effective extraction and separation of 226Ra and 210Pb in the uranium ore digestion solution can be realized, so that radioactive pollution in the environment is reduced, environmental resources can be recycled, meanwhile, the preparation method is simple and low in cost, and the prepared composite membrane is non-toxic and harmless and is beneficial to industrial application.

The invention discloses a preparation and use method of an antibacterial and foam-stabilizing dual-function modified biomass preparation for a radioactive contamination decontamination agent, and the preparation method comprises the following steps: adding a biomass material and a modifier into a solvent, and stirring for reaction to obtain a biomass modified product; transferring the biomass modified product into a dialysis bag for dialysis, collecting the product, and freeze-drying to obtain the antibacterial foam-stabilizing dual-function modified biomass preparation. The use method comprises the following steps: uniformly mixing and stirring the antibacterial and foam-stabilizing dual-function modified biomass preparation, the surfactant and the deionized water to obtain the modified biomass-based radioactive contamination decontaminating agent. According to the modified biomass-based radioactive contamination decontamination agent and the preparation method thereof, a biomass material is modified, so that the modified biomass material has double functions of inhibiting bacteria and stabilizing foam, the modified biomass preparation is added into the decontamination agent, and the prepared modified biomass-based radioactive contamination decontamination agent has good antibacterial activity, foam stability and radioactive contamination decontamination performance; and the hydrogel has the advantages of no skin irritation, good biocompatibility, less secondary pollution, environmental friendliness and the like.

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.