100 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 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 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 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.

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 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.

This invention provides a method for 226 Ra and 210 This invention relates to the field of radioactive ion extraction and separation, specifically a composite membrane for Pb separation, its preparation method, and its applications. The method includes the following steps: mixing polyacrylonitrile, crown ether, and an ionic liquid to obtain a spinning solution; spinning this solution to form a composite membrane. This invention enables the separation of Pb from uranium ore digestion solutions. 226 Ra and 210 The effective extraction and separation of Pb reduces radioactive pollution in the environment and enables the recycling of environmental resources. At the same time, the preparation method is simple and low-cost, and the resulting composite membrane is non-toxic and harmless, which is conducive to industrial application.

The present application belongs to the field of radiation environment measurement, and particularly relates to a method for simulating radionuclide surface contamination wiping efficiency by using rhenium element 90 Sr- 90 Y research surface contamination wiping efficiency method. Through the radioactive characteristics of rhenium element, combined with radiation counting device for quantitative analysis, the present application can accurately evaluate the removal effect of radioactive contamination on different surface materials, and the present application provides a method for simulating and researching radionuclide surface contamination wiping efficiency by using non-radioactive element rhenium element 90 Sr- 90 Y surface contamination wiping efficiency method, reduces the use of radionuclide, is simple and easy to operate, is friendly and safe to personnel and environment, reduces research cost, has various material applicability and operability; the present application can accurately evaluate the removal effect of radioactive contamination on different sample materials, has wide applicability, and can provide technical support for actual scientific decontamination and cleaning work.

The invention provides a pollution diffusion prediction method and device based on gamma radioactivity and a wind field, and relates to the technical field of pollutant monitoring, and the method comprises the steps: carrying out the feature peak extraction, nuclide recognition and concentration calculation of a gamma radioactivity energy spectrum data set, and obtaining a nuclide concentration set; constructing a three-dimensional wind field diffusion field through the topographic data and the wind field data set; performing coupling calculation and correlation matching on the nuclide concentration set and the three-dimensional wind field diffusion field through a Gaussian diffusion model, and constructing a correlation matrix of the nuclide concentration and the wind field; obtaining a nuclide half-life period, a gamma-ray emissivity and a terrain, and performing weighted fusion on elements in the incidence matrix through the nuclide half-life period and the gamma-ray emissivity to obtain a fusion coefficient; correcting the fusion coefficient through the terrain to obtain a diffusion trend coefficient set; and constructing a radioactive pollution prediction model, and according to the diffusion trend coefficient set, performing diffusion prediction in a future time period through the radioactive pollution prediction model to obtain a pollution diffusion prediction result.

The present application relates to a kind of tritium separation method of tritium-containing wastewater and its reactor system, application, the tritium separation method of tritium-containing wastewater of the present application is ultraviolet irradiation promotes separation method, comprising: step 1) tritium-containing wastewater is introduced into the reaction containment of reactor system and is contacted with adsorption material to form liquid-solid two-phase contact system, step 2) after ultraviolet light is irradiated to liquid-solid two-phase contact system, make tritium enrich in adsorption material;Step 3) after the liquid-solid two-phase contact system of irradiation is completed, solid-liquid separation is obtained to low concentration tritium treatment water and tritium-rich adsorption material.The method of the present application is irradiated by ultraviolet light, accelerates hydrogen / tritium isotope exchange and adsorption process, can obtain higher tritium removal rate and adsorption amount under the same processing time.The present application belongs to energy-saving and environmental protection industry, especially in wastewater environmental control and nuclear pollution wastewater treatment in the environmental protection application of the recovery treatment of nuclear radioactive pollution elements plays a key role.

The invention relates to a comprehensive recovery method for valuable metals in zirconium crystallization mother liquor. The method comprises the following steps: S1) separating and enriching iron and uranium; s2) separating and enriching scandium; s3) enriching zirconium, hafnium, titanium and thorium; and S4) separating and enriching rare earth. According to the method, radioactive pollution of the zirconium crystallization mother liquor is reduced, classified recycling of uranium and thorium is achieved by optimizing the recycling process sequence, and the amount of radioactive waste residues is greatly reduced; and meanwhile, scandium and high-purity rare earth are efficiently recovered, and the resource channel is widened, so that the problems of associated resource waste and radioactive pollution are solved, full-process recovery of valuable metals is realized, and the economic and environmental benefits of the zirconium crystallization mother liquor are remarkably improved.

The present application relates to a kind of large-area radioactive contamination distribution fast measurement system and method based on optical fiber, belong to radioactive contamination measurement technical field, the system includes optical fiber detection subsystem and pollution distribution positioning subsystem, and optical fiber detection subsystem uses scintillation optical fiber to determine the relative position information of radioactive contamination;Pollution distribution positioning subsystem respectively through satellite navigation positioning module and ranging module determines the geographical position information of radioactive contamination, and the distance information of optical fiber detection subsystem and radioactive contamination area;Pollution distribution imaging module is fused by the relative position information of radioactive contamination and spatial position information, finally determines the distribution of radioactive contamination and is displayed.The system and method provided by the present application can realize the monitoring and fast positioning of X, γ, β pollution level of large-scale area pollutant.

The invention provides a combined thermal regeneration nuclear power plant secondary loop radioactive contaminated water treatment method and device. The method comprises the steps that S1, secondary loop contaminated water is conveyed into a raw water tank; s2, conveying the waste liquid in the raw water tank to an amphoteric resin bed, and purifying radionuclides in the waste liquid; s3, conveying produced water generated after the amphoteric resin bed treatment to a first-stage membrane unit, and purifying radionuclides; s4, concentrated water generated after treatment of the first-stage membrane unit is conveyed to a cesium removal medium bed for impurity removal, and then the concentrated water is conveyed to a concentrated water tank; and S5, conveying the concentrated solution in the concentrated water tank to a second-stage membrane unit for cyclic concentration until the concentration of non-radioactive impurities in the concentrated solution reaches a target value, and conveying produced water generated after treatment of the second-stage membrane unit back to the raw water tank. The liquid effluent discharge standard requirement can be met through single-time treatment, and meanwhile the liquid effluent treatment device has the advantages of being small in arrangement space requirement, small in solid waste generation amount, easy to operate and maintain and the like.

The present invention relates to a three-dimensional radioactivity measurement and visualization method based on shape recognition of equipment or structures to be decommissioned in nuclear-related facilities. To this end, the present invention comprises: (a) a three-dimensional modeling step using a three-dimensional scanner for equipment or structures to be decommissioned within nuclear-related facilities; (b) an optimization and material implementation step based on data meshing and reverse engineering for 3D modeling; (c) a three-dimensional modeling lattice structure-based characteristic information and measurement information storage database (DB) system construction step; (d) a three-dimensional modeling lattice structure-based physical characteristic information and major nuclides' unique characteristic information database (DB) storage step; (e) a measurement, correction, and storage step for the radioactivity of a measurement target using a radioactivity measurement apparatus linked to a three-dimensional scanning technology; and (f) a step of visualization according to radioactive waste level standards based on radioactivity measurement information. The purpose of the present invention configured as described above is to: provide an efficient and more accurate radioactivity measurement method by using a radioactivity measurement technology linked to a three-dimensional scanning technology, for the purpose of evaluating radiological characteristics required when establishing a decommissioning strategy and plan, such as a decommissioning method, decommissioning schedule, and decommissioning cost calculation for radioactive contaminated equipment or structures during decommissioning in nuclear-related facilities; enable the improvement of safety and work efficiency of a radiation worker through a series of automated processes of remote control, radioactivity measurement, and analysis; and enable the provision of efficient, safe, and more accurate radiological characteristic information with a system configuration that provides visualization information for each radioactive waste level by using a database system for storing and managing radioactivity measurement information based on a three-dimensional modeling lattice structure for a radioactivity measurement target.