1293 results about "Radiation protection" patented technology

The invention provides anti-ionizing radiation powder with a core-shell heterogeneous gradient structure and a preparation method and application of the anti-ionizing radiation powder, and belongs to the field of radiation protection.The preparation method of the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure comprises the following steps that high-atomic-number metal salt is added into deionized water, aging, washing, drying and primary calcination are conducted in sequence, and the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure is obtained; a core layer is obtained; the core layer and low-atomic-number metal salt are added into deionized water, aging, washing, drying and primary calcination are sequentially conducted, and preliminary wrapping powder with the high-atomic-number metal core layer wrapped by low-atomic-number metal is obtained; and adding the preliminarily wrapped powder and rare earth salt into deionized water, and sequentially performing aging, washing, drying, primary calcining, secondary calcining, airflow crushing and air rotation purging to obtain the anti-ionizing radiation powder with the core-shell heterogeneous gradient structure. Through cooperation of the core-shell heterostructure, the high-atomic-number oxide, the low-atomic-number oxide and the multi-element rare earth element, the shielding performance of the material is remarkably improved.

The invention relates to an anti-crack construction method for anti-radiation mass concrete. The anti-crack construction method comprises the following steps: 1) designing a computer tall formwork system and performing computer simulation construction; (2) optimally designing a concrete mix proportion; (3) a wall body cooling water circulating pipe and a temperature detector are installed; (4) mass concrete pouring process quality control; 5) starting a water cooling system; and (6) concrete curing. According to the method, safety calculation software is used for carrying out safety load simulation calculation, BIM simulation construction, test optimal mix proportion, raw material management and control and electronic temperature monitoring, and analysis is carried out according to the real-time temperature monitoring condition; the cooling pipe circulating water is used for reducing internal hydration heat, the geotechnical cloth and the film cover are used for heat preservation, moisture preservation and maintenance, all-around and whole-process quality control measures are taken, and it can be ensured that the mass concrete does not have the quality problems of cracking, leakage and the like which affect the radiation protection performance.

The invention belongs to the technical field of radiation protection, and particularly relates to a neutron shielding material optimization method based on machine learning and chaotic mapping NSGA-III, and the method comprises the steps: 1, determining an optimization target, and building a multi-target neutron composite shielding material attribute optimization model; step 2, building a Monte Carlo model to simulate and calculate shielding doses of the composite shielding materials with different attributes to a neutron source, and obtaining a data set with the material component proportion and thickness as characteristic attributes and the shielding doses as labels; and step 3, optimizing initial parameters of the BP neural network by adopting an improved particle swarm optimization algorithm, improving calculation precision and operation efficiency of the neural network, and training a neural network regression model by taking the data set obtained in the step 2 as a sample to complete establishment of a shielding dose prediction model and the like. An improved particle swarm optimization algorithm for improving Levy flight mechanism strategy optimization is designed to optimize initial parameters of the BP neural network, and the precision and operation efficiency of a neural network shielding dose regression prediction model are improved.

The invention belongs to the technical field of high polymer materials, and particularly relates to a PVB (Polyvinyl Butyral) film and a preparation method thereof. The PVB film provided by the invention is prepared from the following components in parts by mass: 100 parts of PVB resin, 33 to 36 parts of triethylene glycol di-2-ethylhexoate, 7 to 9 parts of integrated anti-radiation toughening filler, 1 to 2 parts of organic montmorillonite, 0.8 to 1.2 parts of composite coupling agent, 0.5 to 1 part of ultraviolet light absorber, 0.6 to 0.8 part of antioxidant and 0.8 to 1 part of heat stabilizer. The integrated anti-radiation toughening filler adopts a core-shell structure, the anti-radiation core is composed of bismuth oxide and tungsten oxide according to the mass ratio of 3: 1, and the elastic coating layer is maleic anhydride grafted modified POE. The preparation method comprises the steps of pre-dispersion treatment, component mixing, melt extrusion, film casting, graded cooling, two-way stretching and the like. Through the core-shell structure design of the integrated anti-radiation toughening filler and the optimized processing technology, the anti-radiation performance and the toughening performance are synergistically improved, and the prepared film has the advantages of excellent anti-radiation effect, high toughness and good transparency.

The invention relates to the field of shielding materials, and provides lead-free rubber with ionizing radiation shielding performance and a preparation method thereof, and the lead-free rubber is mainly prepared from barium titanate / boron nitride composite filler, barium tungstate / boron carbide composite filler, tungsten powder, bismuth powder, a rubber matrix and an auxiliary agent according to a proportion. The barium titanate particles are uniformly loaded on the surface of the flaky boron nitride, so that the gamma ray and X ray shielding performance is improved, and meanwhile, the boron nitride provides excellent neutron shielding capability; barium tungstate particles are loaded on the surfaces of the boron carbide nanowires to form a multi-scale shielding network, and the shielding effect of neutrons and ionizing radiation is remarkably enhanced. The rubber matrix endows the material with excellent flexibility and mechanical properties. By scientifically optimizing the component proportion and the preparation process, the problems that a traditional high-density shielding material is prone to agglomeration, poor in flexibility and the like are solved, and the material shows excellent performance in the fields of gamma ray, X ray and neutron shielding and is suitable for the fields of nuclear energy, medical protection, industrial radiation protection and the like.

The invention relates to a containment pressure suppression, filtration and discharge system and method and application thereof, and belongs to the field of special safety facilities and radiation protection of nuclear power devices. The containment pressure suppression, filtration and discharge system comprises a discharge valve (2), a discharge pipeline (3), a spray pipe (4), a pressure suppression pool, an expansion chamber (7), a steam-water separator (9), a metal fiber filter layer (10), a rupture disk (12), a heat exchanger and a valve. According to the containment pressure suppression filtering and discharging system, the seawater side heat exchanger and the pressure suppression pool heat exchanger are arranged, and a natural circulation loop is constructed by means of the potential difference between the seawater side heat exchanger and the pressure suppression pool heat exchanger and the temperature difference between seawater and a liquid phase in a pressure suppression pool under the accident condition; the heat of the suppression pool can be guided out without time limit under the condition of an LOCA accident or a main steam pipeline fracture accident in the containment; by adopting a pressure suppression washing method with multi-stage bubbling, rapid pressure suppression of the containment and efficient retention of airborne radioactive substances can be realized; occupation of total resources is reduced by arranging the combined metal fiber filter layer.

The invention discloses a radiation protection shielding door convenient to adjust, and belongs to the technical direction of radiation protection, the radiation protection shielding door comprises a protection door mounting frame, and the protection door mounting frame is provided with a first radiation protection shielding door, a first moving pulley, a second moving pulley and a second radiation protection shielding door; the first radiation protection shielding door is arranged on the protection door mounting frame in a sliding mode, and the second radiation protection shielding door is also arranged on the protection door mounting frame in a sliding mode and located on one side of the first radiation protection shielding door. The single door or the double doors can be selected for radiation protection shielding operation according to different sizes of entrances and exits of operation rooms, the applicability is wider, the single door or the double doors can be rapidly switched, operation is convenient and fast, the complexity is low, the sealing performance of the two groups of radiation protection shielding doors can be improved through the protection gaskets, and the service life is prolonged. Meanwhile, abrasion between the two groups of radiation protection shielding doors can be avoided, and the service life of the door body is prolonged.

The invention relates to an acid-base permeation-resistant protective glove for a glove box and a preparation method thereof, the glove adopts ethylene propylene diene monomer, butyl rubber, halogenated butyl rubber, chloroprene rubber, chlorosulfonated polyethylene rubber and other base materials to significantly improve the acid-base resistance and mechanical properties of the glove, and the glove is especially suitable for strong corrosive environments such as concentrated nitric acid and the like. The preparation method comprises a multi-step mixing process, the shielding component, the reinforcing filler and the filler are reasonably configured, and the particle size of the shielding component is controlled, so that the shielding component is uniformly dispersed in the rubber, and the permeation resistance of the glove is effectively improved. In addition, the wear-resistant furnace black, the white carbon black, the PTFE, the high-density polyethylene, the ultra-high molecular weight polyethylene and other fillers are selected, so that the glove has a higher wear-resistant grade (grade 4), and the service life is prolonged. The preparation method of the glove is simple and easy to implement, and the finished product has excellent acid and alkali permeability resistance, mechanical property, wear resistance and radiation protection property.

The invention discloses an anti-radiation aluminum-based layered composite board and an explosive welding method thereof, and belongs to the technical field of metal material welding. According to the method, aluminum or aluminum alloy serves as a base plate, tantalum or tantalum alloy serves as a compound plate, a titanium / titanium alloy middle transition layer is introduced, direct impact of explosive detonation on the compound plate is avoided through an aluminum protection plate, a powdery emulsion explosive is combined with an inert diluent to regulate and control energy parameters, and gaps between plates are accurately set based on the explosive welding window theory; and one-time forming metallurgical bonding of multiple layers of heterogeneous materials is achieved. The density of the obtained composite board is reduced by 40% compared with that of a traditional lead protection layer, and the composite board has the characteristics of radiation resistance, light weight, high strength and corrosion resistance and is suitable for manufacturing of spacecraft radiation protection layers and other deep space equipment.

The invention discloses a preparation method of a polydopamine modified boron carbide-zinc methacrylate coordination reinforced rubber-based radiation protection composite material, and relates to the technical field of radiation protection materials. The method comprises the following steps: dispersing boron carbide in a triaminomethane buffer solution containing dopamine, and carrying out surface polymerization reaction to obtain polydopamine modified boron carbide; and mixing the polydopamine modified boron carbide, zinc methacrylate and a rubber matrix, and vulcanizing to obtain the polydopamine modified boron carbide-zinc methacrylate coordination enhanced (zinc is coordinated with nitrogen / oxygen and the like on the surface of the modified boron carbide) rubber-based radiation protection composite material. Through multiple effects of coordination enhancement, chemical crosslinking and the like, the material has excellent neutron shielding performance and tensile property, the preparation method is simple, the cost is low, and the material has a wide application prospect in the field of nuclear radiation protection.

A hospital proton zone radiation protection performance intelligent monitoring and evaluation method and device relate to the radiation monitoring field, and the method comprises the following steps: carrying out three-dimensional scanning on an actual building structure and an actual device layout of a target proton treatment center to obtain three-dimensional scanning data, and correcting a preset BIM model by using the three-dimensional scanning data to obtain a three-dimensional building model; after the detection equipment is started, obtaining a measured dose rate level of the target proton treatment center at a preset target measurement point; and performing curve fitting on the measured dose rate level to obtain a measured dose rate curve, fusing the simulated dose rate level and the measured dose rate curve to obtain an actual dose rate level of each building structure position, and mapping the actual dose rate level into a three-dimensional building model to obtain a three-dimensional dose distribution diagram. By implementing the method, the radiation protection level of the proton treatment area of the hospital can be displayed more visually.

The invention discloses a reactor instant-slow source item radiation shielding design system and method, and relates to the field of computer aided design of reactor radiation protection. The reactor instantaneous-delayed source item radiation shielding design system comprises a model conversion module, a population construction module, an index calculation module, an individual evaluation module, a selective evolution module, a hierarchical sorting module and an iterative convergence module which are in data flow connection in sequence from front to back. The invention relates to a reactor instant-slow source item radiation shielding design method. The method comprises the following steps: model conversion; constructing a population; calculating indexes; performing individual evaluation; selecting evolution; layering and sorting; and carrying out iterative convergence. According to the invention, a radiation shielding design system covering the whole life cycle of reactor operation and shutdown is established, and collaborative breakthrough of light weight, high safety and efficient convergence is realized through a multi-objective optimization algorithm.

The present invention relates to a lead plate installation construction method for a radiation protection project in a radiological medical room, which mainly includes the following steps: S1. After the main structure of the radiological medical room is completed and passed the acceptance, the radiation protection project and the secondary decoration project are started; S2. The technical scheme of the radiation protection project is determined; S3. The radiation protection project is carried out on the ground; S4. The radiation protection project is carried out on the wall; S5. The radiation protection project is carried out on the ceiling; S6. The fine decoration construction is carried out according to the fine decoration construction drawing. This construction method solves the key link of the radiation protection project - the problem of lead plate installation, and can ensure that the lead plate fits the medical room without dead angles, provides all-round protection for the radiological medical room, and effectively prevents the leakage of harmful rays that endangers personal safety; at the same time, it takes into account the fine decoration construction requirements of the radiological medical room, and ensures a close connection between the radiation protection project and the fine decoration project.

The invention discloses a liquid metal-hydrogel composite radiation protection material and a preparation method and application thereof.The preparation method comprises the steps that indium, tin and bismuth are sequentially put into a flask from low melting point to high melting point to be mixed, and glycerin is added for immersion; placing the mixture in an argon atmosphere, and stirring by using a heating type magnetic stirrer; taking out the spherical liquid metal particles from the glycerol, and finally washing and drying to obtain liquid metal alloy particles; preparing a PVA (polyvinyl alcohol)-H2O solution with the mass fraction of 15% and a PVA-DMSO (dimethyl sulfoxide) solution with the mass fraction of 15%; and a PVA-H2O solution, a PVA-DMSO solution and the liquid metal alloy particles are stirred and mixed according to the mass ratio, the mixed solution is subjected to ultrasonic treatment and then poured into a mold to be frozen into gel, and the liquid metal-hydrogel composite material is obtained. By combining the advantages of the liquid metal and the hydrogel, excellent biocompatibility, adjustable mechanical property and efficient radiation shielding capability are realized, and the hydrogel can be used as a novel lead-free radiation protection material.

The invention relates to a nuclear facility radiation field model construction method and a dose evaluation system, and the system is configured to establish a three-dimensional space coordinate system, construct a three-dimensional radiation field model based on radiation field data and radiation source data, and correct the radiation field model at the current moment according to the radiation source data, introducing an attenuation coefficient of the three-dimensional nuclear facility on the original three-dimensional scene model to correct the three-dimensional scene model; correcting the radiation field model based on the corrected three-dimensional scene model; calling the three-dimensional scene model and the radiation field model according to an operation path selected by a user; and simulating the space range of each organ of the human body sweeping along with the movement of the human body in the working path in the three-dimensional scene model, obtaining the time of each organ staying on the path of the unit space, and calculating the real-time dose received by the human organ according to the radiation dose rate in the unit space. According to the invention, the change of the radiation field caused by the disassembly and assembly of the nuclear facility can be corrected, and the optimization of radiation protection is realized.

The invention discloses a robot assisted diagnosis and treatment system for a nuclear medicine ward and an application method. The robot assisted diagnosis and treatment system comprises an AI robot for non-contact assisted diagnosis and treatment; the robot library is arranged on the same layer of the nuclear medicine ward; the remote interaction platform is used for issuing related instructions and man-machine interaction to the AI robot; a radiation protection and monitoring module, an identity recognition module, a health propaganda and education module, a ferry module, a visual doctor-patient communication module, a communication module, an RFID access control module and an environment disinfection module are integrated on the AI robot; the AI robot is connected with an external subcutaneous injection module, an external intravenous injection module, an external medicine distribution module and an external living goods conveying module through corresponding switching assemblies. According to the robot-assisted diagnosis and treatment system for the nuclear medicine ward and the application method, a semi-autonomous and remote interaction mode is used for replacing medical staff to execute face-to-face diagnosis and treatment behaviors with patients, and non-contact diagnosis and treatment are achieved through human-machine-patient high cooperation in the whole diagnosis and treatment process.

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 utility model discloses a medical engineering through-wall pipeline anti-radiation protection structure which comprises a protection pipe movably arranged in a through hole of a wall in a penetrating mode, a bearing plate supported on the protection pipe is installed outside the through hole, a metal wire braid layer on the inner wall of the protection pipe is coated with an anti-radiation coating layer, and the outer wall of the protection pipe is wrapped with a lead plate layer. The pipe clamping device comprises two arc-shaped pipe pieces which are oppositely arranged, one end of each arc-shaped pipe piece is provided with a threaded hole, a threaded rod is rotatably installed at an end opening of the protection pipe, the threaded holes of the two arc-shaped pipe pieces are screwed to the threaded rod, the spiral directions of the threaded holes of the two arc-shaped pipe pieces are opposite, the two arc-shaped pipe pieces define a limiting hole, and the limiting hole and the protection pipe are arranged in the same direction; the pressing plates are elastically installed in the protection pipe, a polygonal hole channel is defined by the pressing plates, and the hole channel and the limiting hole are coaxially arranged; and the driving structure is mounted on the bearing plate. According to the utility model, the problem that the pipeline or the wall plate is easy to wear when the existing pipeline is arranged through the wall is solved.

The invention discloses an anti-radiation system construction method for a proton therapy building, and the method comprises a large-volume heavy concrete construction control method and a radiation protection wall construction control method, and the large-volume heavy concrete construction control method comprises the following steps: preparing heavy concrete; comprising the steps of concrete raw material control, concrete mix proportion design, concrete trial preparation verification and concrete durability test. Concrete pouring, wherein bottom plate concrete pouring and wall and top plate concrete pouring are included; concrete temperature measurement is carried out to reflect the highest temperature rise in the concrete pouring body, the temperature difference between the inner surface and the outer surface, the cooling rate and the environment temperature; curing the concrete; the radiation protection wall construction control method comprises the steps that a tongue-and-groove-shaped construction joint and a pre-embedded curve or broken line type sleeve are adopted to hinder linear propagation of radiation; temperature control of mass concrete is taken into consideration, radiation leakage is prevented while construction convenience and concrete uniformity are guaranteed, and the radiation protection effect of the ultra-thick concrete structure is guaranteed.

The invention relates to a method for evaluating the radiation dose of special public nearby a nuclear facility, and the method comprises the steps: estimating the concentration distribution of radionuclides in air, surface soil and a biological medium nearby the nuclear facility through collecting the radiation dose evaluation parameters of a target special public and combining an environment quality evaluation model; based on the data, the annual effective dose of the target special public at the nuclear facility boundary and the living quarter is calculated, and a plurality of ways such as inhalation internal irradiation, air immersion external irradiation, surface deposition external irradiation and ingestion internal irradiation are considered. In addition, a dynamic calculation method is also introduced, especially for the influence of year-by-year change of the cumulant of radionuclides deposited on the earth surface, factors such as decay, resuspension and infiltration into underground water of nuclides are fully considered, and the accuracy and foresight of evaluation are improved. Accurate and comprehensive technical support is provided for radiation protection of the special public around the nuclear facility, and the requirements of the nuclear facility public for dose monitoring and risk management are met.

The invention belongs to the technical field of ceramic materials, and discloses SiC-HfB2 composite ceramic as well as a preparation method and application thereof. The preparation method of the composite ceramic comprises the following steps: mixing HfSi2 powder, C powder and SiB6 powder, adding a solvent and a ball milling medium, mixing, drying and sieving to obtain ceramic powder, and carrying out SPS sintering at 1700-1900 DEG C under the vacuum degree of 10Pa and the pressure of 20-35MPa to obtain the composite ceramic. The SiC-HfB2 composite ceramic has good mechanical properties, the hardness at room temperature is 26-30 GPa, the fracture toughness is 3.5-4.5 MPa.m < 1 / 2 >, the bending strength is 450-600 MPa, and the SiC-HfB2 composite ceramic can be applied to an ultra-high temperature (2000 DEG C or above) environment or the field of radiation protection.

An inspection device in a radiation protection housing comprises an electromagnetic radiation-based inspection device, especially an X-ray device and a weighing device. The inspection device an endless conveyor belt for transporting products in a transport direction from an entry region to an inspection region, from there to a region for weighing, and from there to an exit region of the inspection device. An upper run of the endless conveyor belt in its path from the region for weighing to the exit region, traverses a height difference in in a height direction by means of an inclined region. The conveyor belt circulates around at least part of the inclined region and the weighing device, looking in the transport direction, is disposed immediately in front of the inclined region in the inspection device.

The invention discloses anti-radiation hydrogel capable of being used for interventional radiosurgery and a preparation method and application thereof.The anti-radiation hydrogel is in bridge connection with polymer chains of sodium alginate and sodium hyaluronate through the physical interaction between Fe < 3 + > and carboxyl, and the reversible interaction between Fe < 3 + > and carboxyl endows the hydrogel with the shear thinning characteristic; the injectability is ensured; the bismuth oxide nano-particles and the barium sulfate nano-particles are doped to achieve efficient attenuation of X-rays in the range of 20-100 keV, and meanwhile, the complementary K-edge absorption characteristics of the bismuth oxide nano-particles and the barium sulfate nano-particles are utilized, and the radiation absorption effect of a hydrogel network structure is combined, so that broad-spectrum radiation protection is achieved; according to the invention, acrylamide is taken as a raw material, an interpenetrating network elastic hydrogel of three polymers is formed under the action of polymerization under thermal initiation of acrylamide, the conversion from an injectable state to a solid state is realized, and at the moment, the cured hydrogel has tough mechanical properties, can also form a protective layer similar to gloves, and can be used for radiation protection in interventional operations.

The invention relates to the related technical field of radiation intensity testing, in particular to a radiation intensity testing method for radioactivity protection, and the method comprises the steps: collecting data, carrying out the two-dimensional fusion, and setting a dynamic radiation pattern; correcting space distortion, and identifying and marking hot spot coordinates; and generating a protection instruction according to a protection optimization engine, updating a weight coefficient, and establishing a mapping table and an early warning model to perform efficiency verification, thereby solving the technical problems that noise and space distortion are liable to occur in radiation detection due to environmental electromagnetic interference, the accuracy and effectiveness of radiation protection are limited, and the radioactivity protection efficiency is further influenced. The method achieves the correction of the space distortion of the dynamic radiation intensity distribution diagram, adapts to a complex and changeable radioactive environment, improves the pertinence and effectiveness of radiation protection measures, guarantees the accuracy of a radiation detection result, reduces the measurement error caused by environmental electromagnetic interference, verifies and optimizes the radioactive protection efficiency, and improves the accuracy of the radiation detection result. And the overall efficiency of radioactive protection is improved.

A portable small protective workstation for alpha nuclide operation comprises a protective cabin, a transparent window and glove holes are formed in the front side face of the protective cabin, radiation-resistant operating gloves are embedded in the glove holes in a sealed mode, a tray inlet is formed in the side face of the protective cabin, and a drawer type bracket is connected to the tray inlet in a sliding mode. The drawer type bracket comprises a tray layer, a cushion layer and a cover plate, the tray layer and the cushion layer are both vertically and fixedly connected to the side face of the cover plate, the tray layer is located above the cushion layer, a high-adsorbability radioactive water absorption pad is fixedly installed on the cushion layer, a plurality of through holes are formed in the bottom face of the tray layer, and the tray layer and the cushion layer are movably installed in the protection cabin body through a tray inlet. The cover plate abuts against the outer side face of the protection cabin in a sealed mode. An air filter box is arranged above the protective cabin body, and a filter layer is arranged in the air filter box. According to the utility model, the defects in the prior art are overcome, and the organic unification of radiation protection, pollution control and experiment convenience for operators is realized.

The invention relates to the technical field of accelerator radiation protection, in particular to an induced radioactivity assessment method suitable for a mobile accelerator component. Monte Carlo simulation software is adopted to calculate radionuclide activity concentrations in different areas of an acceleration component before movement, then radionuclides serve as radiation source items, and three-dimensional space dose rate distribution of the component and the periphery when the position of the accelerator component changes is obtained through calculation. And rapid evaluation of the received dose of the staff during maintenance and rapid formulation of a maintenance scheme are realized. The method effectively promotes the application of the Monte Carlo method in the field of radiation protection of the accelerator, provides reference for radiation hazards to workers, and provides technical support for radiation protection and operation maintenance of the accelerator.

Disclosed are a radiation protection robot and a scattered inspection apparatus. The radiation protection robot includes: a first wheel capable of allowing the radiation protection robot to move; a shielding device capable of reflecting and / or absorbing radiation; and a radiation sensor for sensing radiation. The radiation protection robot is configured to move through the first wheel towards an area where the radiation dose value sensed by the radiation sensor is increased, and shield the propagation of radiation through the shielding device.

The invention discloses a rapid large-scale calculation simulation method and system for gamma radiation dose in a dynamic environment and a storage medium, and belongs to the technical field of ionizing radiation protection. The method comprises the following steps: firstly, constructing a triangular mesh scene model containing a radioactive source and a shielding body, and discretizing the radioactive source into a local point kernel; global coordinates of the point kernel and the vertex of the triangle are calculated in parallel by using a GPU, and a maximum parallelization hierarchical surrounding structure MPBVH of the scene is constructed; ray tracing is executed in parallel on the GPU, and all intersection points of MPBVH calculation rays and the shielding body are traversed to determine the thickness and the material of each shielding layer; and finally, dose values of all counting grids are calculated in parallel by adopting a point kernel method. When a radioactive source or a shielding body in a scene is subjected to dynamic changes such as movement and rotation, geometric data can be quickly updated, and calculation can be executed again. According to the method, the speed of large-scale point kernel calculation is increased, the influence of the environmental complexity on large-scale calculation time consumption is small, and the method can be suitable for rapid large-scale calculation and dynamic updating of the radiation field in the complex dynamic environment.

The invention discloses a high-strength tungsten-boron silicone rubber radiation shielding material, which is prepared from the following ingredients in parts by weight: 100 parts of methyl vinyl silicone rubber raw rubber, 30 to 50 parts of white carbon black, 90 to 240 parts of tungsten oxide coated boron carbide heterostructure particles, 4 to 10 parts of hydroxyl silicone oil and 1 to 2.5 parts of 2, 5-dimethyl-2, 5-bis-(tert-butylperoxy) hexane. The preparation method comprises the following steps: 1, surface modification of tungsten oxide particles; 2, boron carbide surface modification; 3, grafting the surfaces of the two; and 4, mixing and vulcanizing the raw materials. White carbon black and tungsten oxide coated boron carbide heterostructure particles are introduced into the material, so that the dispersity of tungsten oxide particles in a silicon rubber matrix is improved, the interface interaction between boron carbide and the silicon rubber matrix is enhanced, the high strength of the material is ensured, and the material has excellent mechanical strength and neutron / gamma ray comprehensive shielding performance; the method is easy for mass production and can be used in the field of radiation protection.

The utility model relates to the technical field of radiation protection, and discloses an X-ray photography full-isolation radiation protection device, which comprises an X-ray photography full-isolation radiation protection device, a central beam limiting system, a beam limiting device position signal communication port, a detector height signal communication port, a peripheral shielding interlayer and an examination room. According to the X-ray photography full-isolation radiation protection device, automatic switching of the protection position and the protection state is completed in time, the shooting efficiency is not affected, and the staying and positioning time of a subject is not increased. The X-ray radiography full-isolation radiation protection device can provide a rapid, effective and accurate X-ray protection effect for DR equipment shooting, and examinees, accompanying family members and technicians do not need to wear protection equipment such as lead clothes, so that the probability that non-examined parts, especially gonads and the like, are exposed to direct X-ray irradiation and scattered ray irradiation is greatly reduced, and the X-ray radiography full-isolation radiation protection device is suitable for being used in X-ray radiography. Furthermore, effective guarantee is provided for the health of examinees and technicians, and important social benefits and popularization value are achieved.