132 results about "Radioactive contamination" patented technology

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 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 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.

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 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 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 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 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.

The invention discloses an infusion machine for nuclide drug therapy. The infusion machine comprises a support, a protective screen, a protective tank and an infusion pump. The infusion machine is more accurate in control over the infusion flow speed, it can be effectively ensured that medicine enters the body of a patient at the appropriate flow speed, and therefore the medicine effect can be better exerted. The infusion pump is arranged close to the puncture part of the patient in the layout position of the liquid path, so that the infusion pump can monitor the operation condition of the liquid path in real time, and the infusion pump has the functions of pipeline pressure monitoring and bubble monitoring. According to the infusion machine for nuclide drug therapy, through dual radiation protection of the protection tank and the protection screen, the radioactive contamination risk can be greatly reduced. Meanwhile, a first observation window is reserved in the protection screen, a second observation window is reserved in the protection shell of the protection tank, and the first observation window and the second observation window are made of transparent lead glass materials, so that the radioactive protection is ensured, medical staff can conveniently check the infusion state in real time, and the infusion safety is ensured.

The invention relates to the decontamination of radiation-contaminated lands with clay and loose soil, such as agricultural lands, as well as abandoned test sites, such as the Semipalatinsk test site and uranium quarries. In the method for decontaminating radioactively contaminated lands, which includes the introduction of a reagent, according to the invention, the area of ​​the land to be treated is filled with a 5-7 cm thick layer of KB3 grade barite concentrate containing at least 90% barium sulfate, or finely crushed barite-lead ore containing 70% barium sulfate and up to 1% lead sulfate, Then the land is ploughed using a heavy eight-body plow to a depth of at least 300 mm, turning over the soil layer and dumping it in an inverted position for the complete burial of the radioactively contaminated mass, after which the land is harrowed and reclaimed with the sowing of grass seeds. The developed method for decontaminating radioactively contaminated lands makes it possible to decontaminate lands over a large area and eliminates the need to extract fragments containing adsorbed radionuclides from the soil.

The application discloses a hairpin probe for detecting DNA polymerase exonuclease activity and a preparation method and application thereof. The hairpin probe comprises a region a, a region b, a region c, a region d, a region e, a region f and a region g from the 5' end in sequence, wherein the region a and the region c are reversely complementary to each other, the 5' end of the region a is marked with a first fluorescent group, and the 3' end of the region a is marked with a first quenching group; the region e and the region g are reversely complementary to each other, the 5' end of the region g is marked with a second quenching group, and the 3' end of the region g is marked with a second fluorescent group; the first fluorescent group and the second fluorescent group are different from each other. The hairpin probe can be used for detecting the 3'-5' and 5'-3' exonuclease activity of the DNA polymerase separately or simultaneously in a single system, and has the advantages of simple operation steps, high throughput, good specificity, avoidance of radioactive pollution and excellent application prospect.

The invention relates to an anti-radioactive contamination coating and a preparation method thereof, and the preparation method of the anti-radioactive contamination coating comprises the following steps: manufacturing a surface layer which is formed by carrying out a reaction on epoxy resin, monohydroxy polydimethylsiloxane, ethyl acetate and p-toluenesulfonic acid to prepare organic silicon modified epoxy resin and curing the organic silicon modified epoxy resin; the weight ratio of the epoxy resin to the ethyl acetate to the monohydroxy polydimethylsiloxane to the p-toluenesulfonic acid is (50-100): (25-125): 25: 1. According to the radioactive contamination prevention coating and the preparation method, deposition of surface radioactive contamination is reduced.

The invention relates to a water body sampling device applied to a special environment. The water body sampling device comprises a shell main body, a bottom plate, an internal control unit and a sampling and storing unit, the two side edges of the shell body are provided with hanging lugs, the hanging lugs facilitate clamping operation of a robot clamping jaw on the shell body, the bottom plate is arranged at the bottom of the shell body, the shell body and the bottom plate are matched to form a cavity, the internal control unit is arranged in the cavity of the shell body, and the internal control unit is arranged in the shell body. And the collection and storage unit is arranged on the bottom plate. According to the invention, the robot clamping jaw can be operated to carry out remote operation in dangerous environments such as radioactivity and pollution; in a narrow space environment or a conventional environment, an operator can hold the device by hand to operate the device. The water body sampling device can adapt to various use scenes.

The utility model relates to the technical field of nuclear emergency rescue, and discloses a body surface radioactive decontamination shelter device, which comprises a shelter body, an outer shelter door and a fresh air module, the shelter body comprises a cabin, the cabin comprises a changing room, a leaching room, a body drying room and a reinspection room which are communicated in sequence, the outer shelter door is movably arranged on the shelter body, and the fresh air module is arranged on the outer shelter door. The outer cabin door is used for closing or opening the cabin body, the fresh air module is arranged on the cabin body, an air inlet of the fresh air module communicates with the outside, and an air outlet of the fresh air module is formed in the reinspection room. According to the body surface radioactive decontamination shelter equipment, the body surface of a radioactive contaminated person can be decontaminated, and radioactive damage to the person caused by radioactive substances in the air in the decontamination process can be avoided.

The utility model discloses an automatic cutting device for waste with irregular wall thickness in nuclear power radiation environment, which comprises a cutting mechanism, and is characterized in that a feeding mechanism is arranged at the bottom of the cutting mechanism, a rotary worktable is arranged in the feeding mechanism, a clamping mechanism is arranged at the top of the cutting mechanism, and the rotary worktable is arranged in the clamping mechanism. A material receiving assembly is arranged at the bottom of the cutting mechanism, a waste recycling assembly is arranged on one side of the feeding mechanism, a hydraulic work station is arranged on one side of the feeding mechanism, the hydraulic work station is used in cooperation with the cutting mechanism and the clamping mechanism, and a cooling system is arranged on one side of the feeding mechanism. By means of the automatic cutting device for the irregular-wall-thickness waste in the nuclear power radiation environment, automatic cutting of irregular-wall-thickness materials with radioactive contamination can be achieved, the working efficiency is improved, the working conditions of operators are improved, and the radiation dosage of the operators is reduced.

The invention provides a radiation monitoring method and device, and relates to the field of radioactive contamination identification. The method comprises the following steps: acquiring gamma radiation data, and converting the gamma radiation data into current pulse signal data; performing amplification processing on the current pulse signal data, and extracting pulse waveform characteristics in the current pulse signal after the amplification processing; grading the current pulse signal into pulse counting data of different amplitude grades based on the pulse waveform characteristics; inputting the pulse counting data into a reference parameter comparison model, and judging whether artificial gamma radiation source data exists in the gamma radiation data or not based on the reference parameter comparison model; and if it is confirmed that the artificial gamma radiation source data exists in the gamma radiation data, carrying out classified early warning on the pollution event in a preset mode. The radiation monitoring device solves the problems that when existing portable or fixed radiation monitoring equipment faces a high-energy low-dose artificial radioactive source with remarkable background fluctuation, the situation of recognition failure or false alarm is prone to occurring, and the overall recognition accuracy is low.

This invention relates to a radioactive contamination protection airflow distribution device and self-testing method with a self-testing alarm. An air inlet is used to introduce incoming airflow; a filter is connected to the air inlet to filter the incoming airflow; a self-testing alarm is installed downstream of the filter to detect the airflow pressure and activate the alarm when the airflow pressure exceeds a threshold range; the self-testing alarm includes a pressure switch, an electrical contact pressure gauge, a normally open relay, and an alarm. The parallel connection of the relay contacts and the pressure switch, along with the relay coil, forms a self-testing circuit, while the relay contacts, the electrical contact pressure gauge, and the alarm form an alarm circuit; a diverter is installed downstream of the self-testing alarm to divide the incoming airflow into multiple outgoing airflows; and an air outlet is used to output multiple outgoing airflows. This device achieves the goal of setting up an alarm and multiple contact switches in series and parallel to form a self-testing mechanism, thereby improving the safety of workers.

The embodiment of the present application relates to the technical field of radioactive substance transfer, and particularly relates to a radioactive substance dissolving system with a drying function, which comprises a dissolving device, a drying assembly, a cover plate and a heating assembly. The dissolving device is arranged to form a dissolving tank with a top opening, the dissolving tank is arranged to receive a liquid for dissolving radioactive substances and provide a dissolving space for a radioactive sample, and the radioactive sample collects the radioactive substances. The drying assembly is used for drying the radioactive sample in the dissolving tank after dissolving. The cover plate is used for sealing the top opening of the dissolving tank. The heating assembly is arranged on the cover plate and used for heating the cover plate. The embodiment of the present application can heat the cover plate by using the heating assembly when the drying assembly is used for drying the radioactive sample, so as to improve the temperature of the cover plate, avoid the residual condensate due to the low temperature of the cover plate when the radioactive sample is dried, and avoid the radioactive pollution problem.

The invention provides a wall-climbing cleaning and decontamination robot. The wall-climbing cleaning and decontamination robot comprises a main body, a vacuum adsorption assembly and a cleaning assembly, the main body is connected with a driving part to drive the main body to move, the vacuum adsorption assembly is arranged at the bottom of the main body, the cleaning assembly comprises a shell connected with the main body through a fixed-distance lifting assembly, and a cleaning cavity with a downward opening is formed in the inner side of the shell; the shell is provided with a recycling opening used for being communicated with a recycling device, the recycling opening is communicated with the cleaning cavity, the cleaning assembly can move between the cleaning station and the moving station relative to the main body under driving of the fixed-distance lifting assembly, the shell covers the surface to be cleaned and decontaminated under the cleaning station, the cleaning cavity makes contact with the surface to be cleaned and decontaminated, and the cleaning cavity makes contact with the surface to be cleaned and decontaminated under the moving station. And under the moving station, the cleaning assembly is separated from the surface to be cleaned and decontaminated. Therefore, radioactive contamination diffusion is avoided, the generation amount of radioactive waste liquid and solid waste is reduced, and the operation safety, the environmental protection property and the cleaning efficiency are remarkably improved.

The handheld high-sensitivity radioactive contamination detector comprises a control circuit, a detection circuit, a bias power supply circuit, a display circuit and a buzzer circuit, the detection circuit, the bias power supply circuit, the display circuit and the buzzer circuit are electrically connected with the control circuit, the control circuit comprises a processor U4, and the detection circuit comprises a detector U1 and a connector JP1. The second end of the connector JP1 is electrically connected with the B1 end of the detector U1, and the B1 end of the detector U1 is electrically connected with the negative electrode input end of the signal amplifier U15. According to the handheld high-sensitivity radioactive contamination detector disclosed by the utility model, the control circuit, the detection circuit, the bias power supply circuit, the display circuit and the buzzer circuit are linked, so that high-sensitivity detection is carried out on radioactive substances, and the handheld high-sensitivity radioactive contamination detector has the advantages of stable structure, convenience in operation, high practicability and the like.

The application relates to a sample stage for X-ray diffraction, comprising a sample support and a shielding member. The sample support is used for supporting a sample; the shielding member is used for shielding the radioactivity of the sample, and the shielding member is formed with a shielding cavity, the sample support is detachably arranged in the shielding cavity, the shielding member is provided with a slit, X-rays can enter the shielding cavity via the slit to irradiate the sample, and the X-rays reflected by the sample can leave the shielding cavity via the slit. The application avoids the influence of sample radiation on the outside during X-ray diffraction analysis, and can protect on-site personnel from radioactive contamination and excessive dose irradiation.

The application provides application of a wild pea in repairing radium-polluted soil, and the wild pea is planted in radium-polluted soil for cultivation and management, when the wild pea grows to a mature stage, the aboveground part of the wild pea is removed from the polluted soil, or the wild pea is completely removed from the polluted soil; the above process is repeated until the radium content in the soil reaches an environmental safety standard. The wild pea is used to repair acidic radium-polluted soil in a subtropical monsoon climate zone, the wild pea grows normally in the acidic soil with low-level radioactive pollution and has no toxic and harmful phenomena. The wild pea at the mature stage has a high transfer coefficient and enrichment coefficient, the total radium removal amount of the aboveground part of the wild pea accounts for more than 80% of the total radium removal amount, and radium can be extracted from the low-level radium-polluted soil. The plant repair method provided by the application has simple operation process and convenient management, does not damage the basic structure and properties of the soil, and is suitable for repairing large-area acidic radium-polluted soil with low level.

The invention relates to the technical field of photocatalytic materials, in particular to a covalent organic framework material as well as a preparation method and application thereof. The covalent organic framework material has a repeating unit with a structure as shown in a formula I. A covalent organic framework material based on a benzothiadiazole (BT) core is modified through an electron donating group-OCH3, a non-uniform p-pi conjugated system is further constructed through the synergistic effect of-F and-OCH3, the electronic structure of the COF material is accurately regulated and controlled, a built-in electric field is enhanced, exciton binding energy is reduced, and the shallow trap life is prolonged; according to the preparation method, the formation of deep electron traps and charge recombination are effectively inhibited, the photocatalytic performance is improved, a novel material with enhanced performance is provided for repairing a radioactive pollution environment, and uranium (VI) reduction can be efficiently catalyzed under an illumination condition.

The present invention provides a method for simultaneously solidifying multiple nuclides in rare earth waste slag in a glass-ceramic solid body. The method comprises: mixing rare earth molten salt electrolytic slag with mineral slag to obtain a base batch material; melting the base batch material at high temperature to obtain a base glass; and crystallizing the base glass to obtain a glass-ceramic solid body. The R2O-CaO-SiO2-X glass-ceramic solid body achieves simultaneous solidification of multiple nuclides and is capable of stable solidification. Testing using the ASTM C1285-2014 standard PCT powder method revealed that the cerium and neodymium leaching rates were 1.22×10 ‑6 g·m ‑2 ·d ‑1 With 1.20×10 ‑6 g·m ‑2 ·d ‑1 , far below the national standard limit, and at the excellent level specified by the standard. It can be used to solidify radioactive nuclides in rare earth waste and solve the problem of radioactive contamination.