45 results about "Radioactive Pollutants" patented technology

The invention relates to the technical field of radioactive pollutant removal, in particular to a movable surface Po-210 pollution treatment device and a testing method thereof.The pollution treatment device comprises a movable vehicle body capable of automatically moving; the positioning assembly is arranged on the mobile vehicle body and can automatically identify and identify a pollution object with the surface Po-210 pollution needing to be treated; the multi-shaft mechanical arm is mounted on the movable vehicle body; the decontamination assembly is installed at the moving end of the multi-axis mechanical arm, and the decontamination assembly comprises a film forming raw material spray head, a film uncovering scraper knife, a dirty film clamp and a coating film raw material spray head; a spraying raw material supply system; wherein the film forming raw material spray head and the coating film raw material spray head are connected with a spraying raw material supply system, the film uncovering scraper knife can be driven by the multi-axis mechanical arm to shovel up a dirty film formed by film forming raw materials on a polluted object, and the dirty film clamp can clamp the dirty film shoveled up by the film uncovering scraper knife. The testing method is used for testing the pollution treatment device.

The invention provides a nuclear radiation diffusion analysis method based on a Gaussian mixture atmospheric diffusion model. The method comprises the steps that nuclear facility source item parameters are acquired; integrating meteorological, geography, remote sensing and radiation monitoring data by using a heterogeneous data fusion engine, extracting atmospheric turbulence, terrain and building interference characteristics and source item parameters, and forming a dynamic input parameter set; constructing an unsteady state diffusion model containing a multi-modal distribution function, processing features, obtaining a mixed distribution model, and correcting the mixed distribution model; predicting spatial and temporal distribution of radiation pollutants, and generating multi-scale diffusion field simulation; and optimizing a diffusion path, and generating a three-dimensional risk field. According to the method, multi-source data are integrated, an unsteady state diffusion model is constructed, Gaussian component weights are dynamically adjusted, the model is corrected by using real-time data, and a geographic information system is coupled to carry out spatial constraint optimization. And through multi-scale feature coupling, dynamic parameter adjustment and geographic space constraint correction, the depicting capability of the atmospheric diffusion model is remarkably improved, and the nuclear radiation diffusion prediction precision is greatly improved.

The invention discloses an OpenFOAM-based urban area gaseous radioactive pollutant diffusion simulation method, and relates to the technical field of computational fluid mechanics simulation, and the method comprises the steps: S1, building a three-dimensional model of an urban area based on CAD software and a user-defined script program; s2, importing a three-dimensional city model based on an OpenFOAM open source platform, and performing pretreatment on the three-dimensional city model, the pretreatment including customizing a computational domain and a boundary condition, performing grid division on the computational domain, and performing computational domain distribution; s3, the scalar transport equation is corrected, a Radioactive ScalarTransportFoam radioactivity solver is self-defined, and parallel operation is carried out on the Radioactive ScalarTransportFoam radioactivity solver; and S4, performing simulation result viewing and data collection and analysis. According to the method provided by the invention, the diffusion process of the gaseous radioactive pollutants in the city can be more flexibly, freely and accurately simulated.

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 relates to the technical field of nuclear facility decontamination detection, and provides a radioactive pollutant detection method which comprises the following steps: stripping pollutants by adopting laser, and acquiring stripping thickness and corresponding pollution information of each time; when the pollution information reaches a set condition, stripping is stopped, and the total stripping thickness and a curve graph of each stripping thickness and the corresponding pollution information are obtained; and acquiring the pollution distribution section and the pollution depth of the pollutants based on the total stripping thickness and the curve graph. According to the radioactive pollutant detection method provided by the invention, the pollution distribution condition and the pollution degree of the pollutants can be accurately obtained.

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 a nuclear power plant pipeline ice slurry decontamination system, a decontamination method and a decontamination effect verification method. The nuclear power plant pipeline ice slurry decontamination system comprises a main loop coolant system, an ice slurry making machine, an ice slurry storage tank, a hydrogen peroxide storage tank, a boron recovery system and a waste liquid treatment system. According to the nuclear power plant pipeline ice slurry decontamination system, system operation process water is used for preparing ice slurry, after the ice slurry is injected into an in-service pipeline, the ice slurry can be well attached to the inner wall of a complex pipeline due to the high viscosity and the semi-solid property of the ice slurry, upstream water pressure pushes an ice piston, radioactive pollutants on the inner wall of the pipeline can be effectively removed through friction scouring, and the service life of the pipeline is prolonged. The radioactive pipeline cleaning agent has a good decontamination effect on a radioactive pipeline, has no adverse effect on a pipeline base material, does not need to add other chemical reagents, is good in operation condition and high in safety coefficient, and after ice slurry is naturally melted, a boron recovery system and a radioactive waste liquid treatment system are utilized for purification treatment, so that secondary radioactive waste is not newly added at all.

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 relates to a radioactive pollutant protective glove, comprising a glove body, a flexible fixing device and a locking device, wherein the glove body comprises a palm portion and an arm portion, the flexible fixing device is arranged around the arm portion and is slidably connected to the arm portion along the longitudinal direction of the arm portion, the flexible fixing device has a first opening end and a second opening end forming an opening, the locking device comprises a locking member and a matching member, the locking member is arranged at the first opening end, the matching member is arranged at the second opening end, and the locking member comprises an unlocking position separated from the matching member and a locking position matched with the matching member to close the opening. By arranging a flexible fixing device with an opening between the palm portion and the arm portion, and locking the first opening end and the second opening end by the locking device, the radial size of the flexible fixing device is adjusted, and then the flexible fixing device reliably fixes the radioactive pollutant protective glove on the palm and arm of the worker, thereby preventing the radioactive pollutant protective glove from loosening.

The utility model relates to a handheld radioactive pollutant removing device, which belongs to the technical field of radioactive pollutant removing devices and comprises an operation component, a decontamination roller and an automatic film changing mechanism, and the decontamination roller is rotatably connected onto the operation component; the automatic film changing mechanism comprises a motor, an old film cylinder and a new film cylinder wound with a decontamination adhesive film, and the motor is fixed on the decontamination roller; the old film cylinder and the new film cylinder are arranged in the decontamination roller at intervals along the axis of the decontamination roller, the old film cylinder is rotationally connected into the decontamination roller, and one end of the new film cylinder is fixed to the motor. According to the utility model, the motor is used for driving the new film cylinder to rotate, and the free end of the decontamination adhesive film penetrates through the long-strip-shaped hole around the decontamination roller and penetrates into the long-strip-shaped hole to be fixed at the peripheral side end of the old film cylinder, so that the decontamination adhesive film can be automatically replaced after the decontamination adhesive film is adhered to remove radioactive sediment pollution, and therefore, manual intervention and manual contact are reduced, and the production efficiency is improved. And meanwhile, secondary use of the decontamination adhesive film is avoided, and the cleaning efficiency and the cleaning effect are improved.

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 invention 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 three-dimensional space model of a fluid diffusion area according to space parameters of an area to be detected, and dividing the three-dimensional space model into a fluid domain space body grid and a surface boundary layer grid; radioactive gas particles are added, and the density and the leakage rate of the radioactive gas particles are set; calculating the deposition velocity of the radioactive gas particulate matters in the fluid domain space body grid and the particle concentration of the radioactive gas particulate matters in the surface boundary layer grid according to a computational fluid mechanics method; further calculating deposition flux and deposition activity; and assigning the deposition activity to the NFC label corresponding to the surface boundary layer grid, and detecting the NFC label to complete surface pollution simulation detection. According to the embodiment of the invention, the diffusion trend and deposition condition of the radioactive pollutants can be predicted more accurately, and the simulation precision is improved.

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 utility model discloses a device for cleaning pollutants on the surfaces of inner and outer shells of a sealed radioactive source. The device comprises a shell cleaning table, a dry ice manufacturing module, a shell cleaning module and a dust collection fan, the dry ice manufacturing module is used for generating dry ice particles and outputting the dry ice particles. And the cladding cleaning module comprises a limiting driving assembly and a cladding cleaning assembly. The limiting driving assembly is used for limiting the position of the cleaned cladding and driving the cleaned cladding to rotate in the circumferential direction. The cladding cleaning assembly is used for spraying dry ice particles to a cleaned cladding placed on the cladding cleaning table. And the dust collection fan is used for intensively discharging radioactive pollutants peeled off through dry ice cleaning. The two rotating shafts capable of rotating under the driving of the circumferential driving assembly are arranged on the cladding cleaning table. The two rotating shafts drive the cleaned cladding to rotate, so that the cladding cleaning assembly can evenly spray dry ice to the radioactive cladding, and residues of radioactive substances are effectively avoided.

The invention discloses an urban area gaseous non-radioactive pollutant diffusion simulation method based on OpenFOAM, and relates to the technical field of computational fluid mechanics simulation, and the method comprises the steps: S1, building a three-dimensional model of an urban area based on CAD software and a user-defined script program; s2, importing a three-dimensional city model based on an OpenFOAM open source platform, and performing pretreatment on the three-dimensional city model, the pretreatment including customizing a computational domain and a boundary condition, performing grid division on the computational domain, and performing computational domain distribution; s3, a ScalarTransportFoam solver is used for carrying out pollutant diffusion parallel operation, and the pollutant diffusion parallel operation is carried out by using the ScalarTransportFoam solver And S4, performing simulation result viewing and data collection and analysis. According to the method provided by the invention, the diffusion process of the gaseous non-radioactive pollutants in the city can be more flexibly, freely and accurately simulated.

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 the technical field of radioactive pollutant removal, and specifically to a removal mechanism and method for removing surface Po-210 contamination, wherein the removal mechanism comprises: a mobile body, which can move by itself; a positioning component, which is arranged on the mobile body and can automatically identify and mark the contaminated object with surface Po-210 contamination that needs to be treated; a multi-axis mechanical arm, which is installed on the mobile body; a decontamination component, which is installed on the mobile end of the multi-axis mechanical arm, and the decontamination component comprises a film-forming raw material nozzle, a film-removing blade and a contaminated film clamp; wherein the film-forming raw material nozzle is used to be connected to a film-forming raw material supply system, so that the film-forming raw material nozzle can spray the film-forming raw material onto the contaminated object, the film-removing blade can shovel up the contaminated film formed by the film-forming raw material on the contaminated object under the drive of the multi-axis mechanical arm, and the contaminated film clamp can clamp the contaminated film shoveled up by the film-removing blade. The removal method is based on the aforementioned removal mechanism.

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 present invention relates to a method, system, device, and medium for iterative reconstruction and uncertainty quantification of leakage sources based on spatial priors. The method comprises the following steps: preliminarily screening the leakage source locations based on the Spearman coefficient and source-receptor matrix to obtain the distribution of spatial prior information; calculating the release rate and corresponding simulation-observation error index for each prior location based on the spatial prior information and the Tikhonov regularization method, and estimating the source location; optimizing the release rate estimation based on the estimated source location using the L1 norm and total variation non-smooth constraint to obtain a time-series release rate estimation result; and designing a Bayesian framework to obtain the uncertainty distribution of the source location and release rate estimation results through Monte Carlo sampling. The present invention can be widely applied in the fields of radioactive pollutant tracing and environmental monitoring.

The invention belongs to the technical field of operation and maintenance detection of complex pipelines, and particularly relates to an easy-to-decontaminate pneumatic peristaltic pipeline robot joint. Comprising radial expansion joints and axial telescopic joints, the number of the radial expansion joints is three, the number of the axial telescopic joints is two, and every two radial expansion joints are connected through one axial telescopic joint to form an integral structure. The easy-to-decontaminate pneumatic peristaltic pipeline robot joint has the beneficial effects that a nuclear power pipeline robot adapts to a complex pipeline environment in a pipeline and executes a pipeline dredging task, and through the inner and outer double-layer structure design, the independent pneumatic telescopic unit is used for driving, so that the pipeline dredging efficiency is improved. The problem that a traditional rigid joint lacks flexible adaptive capacity in a complex pipeline is solved, the integrity and sealing performance of the outer surface of the robot are guaranteed, the risk that radiation pollutants enter the robot is reduced, and the robot can better clean and remove dirt.

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.