21 results about "Radioactive Pollutants" patented technology

The invention discloses preparation of a nitrogen-rich ionic organic single crystal material and application of the nitrogen-rich ionic organic single crystal material in iodine adsorption, and belongs to the technical field of functional materials and radioactive pollutant treatment. The material is formed by self-assembly at room temperature through a solution method by taking biphenyl tetracarboxylic acid tetrabutylamine as an anion ligand and tetra (4-ethyl pyridine phenyl) ethylene bromide or tetra (4-imidazole phenyl) ethylene bromide as a cation ligand. The method is simple in preparation process, mild in condition and high in yield. The skeleton of the obtained material is rich in nitrogen sites and has a large cavity, the material shows extremely high adsorption capacity and rapid adsorption kinetics for iodine in a gas phase and a liquid phase, the maximum adsorption capacity of the material for iodine steam reaches up to 5.16 g / g, the retention rate of 95% or above can still be kept within 7 days after adsorption, and the material has good recycling performance. The material provides a novel and reliable solution for efficiently capturing and fixing radioactive iodine, and has a wide application prospect in the field of nuclear waste treatment.

The invention relates to a method for the remediation and processing of demolition material containing pollutant-containing mineral components, wherein the method comprises the following steps: breaking up the demolition material to separate the pollutant-containing mineral components; dry or wet classifying the broken-up demolition material to separate at least one fraction from it; wet sorting the separated fraction to separate it into a pollutant-free mineral part and a pollutant-containing part, wherein in the wet sorting step the separated fraction is placed in a flowing liquid to separate pollutant-free mineral and pollutant-containing components of the separated fraction according to density, and thus to obtain the pollutant-free mineral part and the pollutant-containing part from the separated fraction.Another aspect of the invention relates to a system for the remediation and processing of demolition material containing pollutant-laden mineral components. These pollutants can include, for example, asbestos or radioactive contaminants.

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 utility model discloses a surface pollution decontaminating and cleaning device for a radioactive substance storage and transportation container. The surface pollution decontaminating and cleaning device comprises a cleaning machine frame, a cleaning machine box, an outer wall cleaning spray gun, an inner wall cleaning spray gun, a dry ice cleaning machine, a dust collection fan and a container cleaning base table. The cleaning machine box is installed on the cleaning machine frame. The container cleaning base table is connected to the cleaning rack in a sliding mode and can be switched between moving in or moving out of an inner cavity of the cleaning machine box. The container cleaning base table is used for loading a cleaned container and can drive the cleaned container to rotate. The outer wall cleaning spray gun and the inner wall cleaning spray gun are arranged to spray dry ice powder output by the dry ice cleaning machine to the outer wall or the inner cavity of the cleaned container, and radioactive pollutants on the surface of the cleaned container are converted into gaseous pollutants; the gas pollutants are output in a centralized manner through the dust collection fan; and the water is filtered and collected through the filter element, so that secondary pollution to the outside is effectively avoided.

The present invention provides a treatment method that can reduce the concentration of radioactive contaminants such as Cs in the ash to be treated. [Solution] The processing method comprises a first water washing step S10 in which the ash to be treated containing the recovered radioactive material is washed with water, an acid washing step S20 in which the ash to be treated washed in the first water washing step S10 is washed with acid, and a second water washing step S30 in which the ash to be treated washed in the acid washing step S20 is washed with water.

The application discloses a cleaning agent for removing radioactive pollutants and belongs to the technical field of special decontaminants. The cleaning agent is composed of the following components and in the following mass percentages: 5-20% of a surfactant, 10-30% of a chelating agent, 0.3-2% of a natural product with a radiation prevention function, and 48-85% of deionized water. The cleaning agent for removing radioactive pollutants prepared by the application has the performance of removing radioactive metal ions, strong decontamination performance, good biological safety, and is suitable for the body surface and has the characteristics of mildness and no irritation.

The application discloses a surface pollution simulation detection method, device and system, and relates to the technical field of pollution simulation detection. The method comprises the following steps: constructing a fluid diffusion area three-dimensional space model according to space parameters of a to-be-detected area, and dividing the three-dimensional space model into a fluid domain space body grid and a ground surface boundary layer grid; adding radioactive gas particles, and setting the density and leakage rate of the radioactive gas particles; calculating the deposition velocity of the radioactive gas particles in the fluid domain space body grid and the particle concentration of the radioactive gas particles in the ground surface boundary layer grid according to a computational fluid dynamics method; further calculating the deposition flux and the deposition activity; assigning the deposition activity to NFC tags corresponding to the ground surface boundary layer grid, and detecting the NFC tags to complete surface pollution simulation detection. The embodiment of the application can more accurately predict the diffusion trend and deposition condition of radioactive pollutants, and improves the simulation accuracy.

The application discloses a sealing device for quickly sealing waste filters, and relates to the technical field of plastic bag sealing devices. The sealing device is composed of an assembled guide rail assembly, a portable sealing machine and a control device. The portable sealing machine comprises a shell and a feeding wheel, a heating block, a heat sealing wheel, a leveling wheel, a cutting wheel, a separating wheel, a synchronous gear and a stepping motor for driving the synchronous gear, which are arranged in pairs in the inner cavity of the cuboid from front to back and arranged in two layers in an up-down mode. The cutting wheel and the leveling wheel are directly connected with the synchronous gear through a synchronous belt and a synchronous pulley. The heat sealing wheel is connected with the cutting wheel through a synchronous pulley and a synchronous belt. The feeding wheel is connected with the heat sealing wheel through a synchronous pulley and a synchronous belt. The application can automatically heat seal and cut the plastic bag after the waste filter is loaded into the plastic bag, greatly improves the sealing efficiency of the plastic bag, greatly improves the forming quality and sealing performance of the sealing part of the plastic bag, and effectively reduces the risk of radioactive pollutant leakage.

The present invention relates to a particle and aerosol filter layer with particle and aerosol filter function, preferably with improved wash resistance, and with a protective function against chemical and / or biological and / or radioactive pollutants and / or warfare agents, as well as the use of carrier layers for stabilizing a functional layer having particle and aerosol filter properties and furthermore a method for stabilizing a functional layer having particle and aerosol filter properties.

The invention provides a ground alpha radioactive contamination efficient cleaning decontamination and waste liquid recovery device which comprises a cleaning disc shell, a cleaning disc, a waste liquid recovery device and a waste liquid recovery device, and the cleaning disc shell is internally provided with a cleaning cavity; the cleaning assembly is arranged in the cleaning cavity and used for cleaning the ground facing the cleaning cavity; on one hand, a gridding cleaning and decontamination operation mode is originally created, operation is carried out with a cleaning cavity coverage area as an independent grid, physical isolation from surrounding facilities and equipment is achieved, a cleaning assembly composed of atomized high-pressure water, compression type bristles and the like is originally created, efficient removal of various kinds of alpha radioactive pollutants on the ground is ensured, and the cleaning efficiency is improved; meanwhile, the generation amount of radioactive gas, liquid and solid waste is greatly reduced, and secondary pollution diffusion of radioactive waste water, radioactive dust (aerosol) and the like is reduced; and on the other hand, the remote operation mode of cleaning and decontamination operation is realized for the first time through visual remote control operation, and the physical and psychological health of operators is greatly protected.

The application discloses a double-channel separated closestool for nuclear medicine department and a radioactive waste liquid treatment system, and relates to the technical field of double-channel separated closestools. The application can realize precise classification and isolation of urine and excrement, prevent radiation, and has the functions of convenient and stable separation operation, through the cooperation of the limiting block, the separation plate and the clamping block. The application can realize classified conveying and classified decay treatment, improve the treatment efficiency of radioactive pollutants, and prevent the blockage and leakage of the sewage channels. Through the risk analysis module, the working time of the ultraviolet lamp belt is automatically controlled according to the required irradiation time calculated in real time, and the disinfection state is prompted through the red and green warning lights, so that medical staff and subsequent users can clearly judge the safe and available state of the closestool, and the risk of cross infection and radioactive residue exposure in the nuclear medicine department is effectively reduced.

The present invention relates to an integrated treatment apparatus for liquid radioactive waste generated during decommissioning of a nuclear power plant. The purpose of the disclosure is to efficiently treat liquid radioactive waste generated during decommissioning of a nuclear power plant by applying processes suitable for respective properties and conditions of liquid radioactive waste, thereby significantly reducing radioactive waste after treatment and reducing treatment costs. The integrated treatment apparatus comprises: a liquid radioactive waste storage unit (20) for separately classifying and temporarily storing low-concentration, high-concentration, and organic liquid radioactive waste; a pre-treatment unit (30) for separating and collecting foreign substances, oil, impurities, precipitates, and solids contained in the low-concentration, high-concentration, and organic liquid radioactive waste, classifying the separated foreign substances as miscellaneous solid radioactive waste to treat the classified miscellaneous solid radioactive waste, and decomposing organic compounds; a main treatment unit (40) for removing radioactive contaminants contained in the liquid radioactive waste; a post-treatment unit (50) for purifying exhaust gas and exhaust liquid; and a control panel (60) for controlling the operation of the liquid radioactive waste storage unit (20), the pre-treatment unit (30), the main treatment unit (40), and the post-treatment unit (50).

The invention provides a radioactive pollution prevention and control method for uranium-coal collaborative mining, and belongs to the technical field of radioactive pollution abatement. The method comprises the following steps: constructing an underground water pollutant migration and diffusion model; determining the overall pumping-injection ratio and the micro-unit pumping-injection ratio of the uranium mine in-situ leaching well site by using an underground water pollutant migration and diffusion model so as to reduce the influence range on the in-situ leaching peripheral underground water environment; the radioactive pollutants in the migration path are dynamically sensed and regulated, so that the water quality of the underground water is monitored in real time; when the radioactive pollutants migrate and diffuse to the environment, the radioactive pollutants are migrated reversely, and the residual radioactive pollutants are treated. According to the radioactive contamination prevention and control method for uranium-coal collaborative mining, a whole-process prevention and control system of source control, process monitoring and tail end treatment is integrally formed, the key problem of radioactive contamination diffusion in existing uranium-coal collaborative mining is solved in a targeted mode, and underground water environment safety in the mining process is guaranteed.

The invention discloses an underground water flow direction zoning staggered-time coordinated mining method for an overlapped coal-uranium orthogonal area, and belongs to the technical field of coal-uranium resource collaborative development. The method comprises the following steps: firstly, quantitatively determining a coal-uranium safe mining error distance through an established groundwater disturbance distance model; secondly, the coal mine and the uranium mine are arranged in the direction perpendicular to the regional underground water flow direction, and a buffer isolation zone is arranged; then, a mining time sequence of uranium first and coal second and dynamic staggering is planned, and uranium mine area coal resources are developed after uranium mine decommissioning and repairing; and finally, constructing an ore-bearing and water-bearing stratum water level and pollutant comprehensive monitoring-regulating system in a coal-uranium transition zone, tracking and coordinating water level change and pollutant migration characteristics in the mining buffer zone in real time, and dynamically regulating mining parameters of a coal mine and a uranium mine according to the water level change and the pollutant migration characteristics. According to the method, the problems of underground water flow field space demand conflicts and radioactive pollutant migration risks in coal-uranium co-mining can be effectively solved through a collaborative development strategy of quantitative safety staggered distance-layout orthogonal flow direction-time sequence dynamic collaboration-environment restoration connection.

An apparatus (10) is described for removing radioactive contamination, at least in part, from a first article (A1) comprising a metal, preferably wherein the metal comprises and / or is a low melting point metal for example lead and / or an alloy thereof. The apparatus (10) comprises a heated first vessel (100A) for melting the metal, at least in part, therein, thereby providing a melt (M) therefrom. The apparatus (10) comprises casting means (200) for forming a second article (A2), particularly a sheet, having a predetermined thickness (T), from the melt, preferably wherein the casting means (200) comprises and / or is a rotatable roller (210) arrangeable to contact the melt (M) to thereby form thereon the second article (A2) and a guide (220) arranged to remove the second article (A2) from the roller (210). The apparatus (10) comprises a set of radiation detectors (300), including a first radiation detector (300A), arranged to detect a first fraction of the radioactive contamination, if present, in a first part (P1) of a set of parts of the second article (A2), preferably wherein the set of radiation detectors (300) comprises opposed first and second radiation detectors (300A, 300B) arranged to receive the second article (A2) traversing therebetween. The apparatus (10) comprises a cutter (400) arrangeable to excise the first part (P1) of the second article (A2) therefrom.

Textile protective clothing (1), in particular with a protective function against chemical and / or biological and / or radioactive harmful and / or toxic substances (warning agents) (“ABC protective function or CBRN protective function”), preferably ABC protective clothing (“CBRN protective clothing”), preferably for civilian or military purposes, preferably with improved and / or increased displacement resistance (displacement resistance) of the textile layers of the protective clothing (1), wherein the protective clothing item (1) comprises or is formed from a multi-layered textile material (2), in particular in the form of a multi-layered textile structure or textile composite, wherein the protective clothing item (1) and / or the multi-layered textile material (2) is / are designed to be air-permeable, wherein the multilayer textile material (2) - a textile outer material, in particular a planar and / or two-dimensional, air-permeable outer material (3), in particular a top layer or outer fabric, and - a textile, in particular planar and / or two-dimensional, air-permeable adsorption filter (inner) material (4), in particular inner layer or inner fabric, in particular for the adsorption of chemical and / or biological and / or radioactive pollutants and / or toxins (warning agents), exhibits or is formed from this wherein the protective clothing item (1) is formed from several, in particular at least two, sections (cut pieces) (A, B) of the multilayer textile material (2), wherein adjacent and / or edge-overlapping sections (cut pieces) (A, B) are joined together to form the protective clothing piece (1) by means of sewing and / or by means of a connecting seam (5), in particular at the edge and / or in a connecting area (6) in particular at the edge; wherein the sewing is carried out in such a way and / or the connecting seam (5) is designed in such a way that the protective garment (1) is not perforated and / or seamless on the outside, in particular on the outer side facing exposure to chemical and / or biological and / or radioactive hazardous and / or toxic substances, by the sewing and / or by the connecting seam (5), and / or wherein the sewing is carried out in such a way and / or the connecting seam (5) is designed in such a way that there is no external seam formed in particular by the connecting seam (5), preferably no external seam arranged on the outside facing exposure to chemical and / or biological and / or radioactive pollutants and / or toxins, in particular formed by the connecting seam (5), and / or wherein the sewing is carried out in such a way and / or the connecting seam (5) is designed in such a way that the sewing and / or the connecting seam (5) is covered on the outside, in particular in the direction of the action of chemical and / or biological and / or radioactive pollutants and / or toxins, by the outer material (3), in particular by an outer material section (outer material cut part) (3A, 3B), preferably by a first outer material section (3A).

The application discloses a purification ventilation device, which comprises an exhaust chamber, a ventilation assembly and a driving assembly. The exhaust chamber is adapted to be installed on a factory roof. A communication port and a ventilation structure are arranged on one side of the exhaust chamber close to the roof. The communication port is adapted to be communicated with the factory, and the ventilation structure is adapted to communicate the exhaust chamber with the outside. The ventilation assembly is arranged on the ventilation structure and comprises a ventilation piece adapted to guide the pollutants to be discharged to the outside. The driving assembly is adapted to be arranged on the factory roof and connected with the ventilation piece. The driving assembly comprises a photovoltaic power supply system and / or a compressed air system, and both the photovoltaic power supply system and the compressed air system are adapted to provide power for the ventilation piece. The purification ventilation device with the above structure can still discharge radioactive pollutants to the outside when losing power, thereby avoiding the harm to the nearby personnel.

The present invention relates to a textile protective and / or filter material with particle and aerosol filter function, preferably with improved wash resistance, and with a protective function against chemical and / or biological and / or radioactive pollutants and / or combat agents, as well as its use and, furthermore, protective equipment and / or protective articles as well as protective and / or filter materials produced with the textile protective and / or filter material.

Textile protective material (1), preferably textile reactive adsorption filter material, with protective function against chemical, biological and / or radioactive pollutants or toxins, preferably against chemical warfare agents, in particular ABC and / or CBRN protective material, wherein the textile protective material (1) comprises a combination of a metal-based catalytically active component and a particulate adsorbent and wherein the textile protective material (1) has a multi-layered structure and / or is designed as a multi-layered textile multi-layer material, preferably composite material, comprising a plurality of superimposed, preferably interconnected, layers (2, 3, 4, 5), wherein the textile protective material (1) comprises the following layers (2, 3, 4, 5), preferably in the sequence listed below: (a) optionally a textile outer layer (top layer) (2), wherein the textile outer layer (2) is and / or is formed as a preferably gas-permeable textile sheet structure, (b) a textile reactive layer (3), in particular a textile reactive layer (3) arranged on one side, in particular on the inside (2a), of the textile outer layer (2), wherein the textile reactive layer (3) is and / or is formed as a preferably gas-permeable, textile sheet structure and comprises at least one metal-based catalytically active component, preferably coated and / or impregnated with the metal-based catalytically active component, preferably (only) on one side, particularly preferably (only) on the inside (3a) of the textile reactive layer (3), wherein the metal-based catalytically active component is and / or is formed in the form of a porous solid, preferably with a network-like structure, particularly preferably as a xerogel, (c) an adsorption layer (4) arranged on the textile reactive layer (3), in particular on the inside (3a) of the reactive layer (3), preferably having a discontinuous form and / or being gas-permeable, wherein the adsorption layer (4) comprises or is formed from a plurality of individual adsorber particles (4c), (d) an inner layer (5) arranged on the adsorption layer (4), in particular on the inside (4a) of the adsorption layer (4), wherein the inner layer (5) is preferably designed as a gas-permeable textile surface structure.

The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation. The application provides a pollution diffusion simulation method and device fusing dry and wet deposition and radioactive decay, and relates to the technical field of pollution diffusion simulation.

This invention provides a method for decommissioning a nuclear reactor that has experienced a core meltdown. [Solution] In the decommissioning of a reactor that has experienced a core meltdown, the melted debris is covered with gravel and cooled by immersing it in water to suppress heat generation and thus shield and seal off radiation. In the removal of the debris after filling and sealing, it is possible to excavate the gravel and debris together using a rotary excavation method (rock auger method). The auger is used to lift the contents of the casing, and the recovered debris can be transported in a sealed state by using a flexible hose and piping to transport it from the outlet at the top to the recovered debris storage facility. Next, in order to remove any radioactive contaminated material remaining inside the reactor, the material is dissolved and removed using aqua regia circulation.