539 results about "Radiation shield" patented technology

The invention provides a samarium / europium / gadolinium-containing zirconium hydride block as well as a preparation method and application thereof, and relates to the technical field of radiation shielding materials. The zirconium hydride block containing samarium / europium / gadolinium comprises the following elements in percentage by mass: 95% < = Zr < = 99.5%, 0% < = Gd < = 5%, 0% < = Sm < = 5%, 0% < = Eu < = 5% and 0% lt. Gd + Sm + Eu < = 5%. The preparation method comprises the following steps: respectively hydrogenating sponge zirconium, metal gadolinium, metal europium and metal samarium to respectively obtain corresponding hydride powder; weighing zirconium hydride powder, gadolinium hydride powder, europium hydride powder and samarium hydride powder according to a required proportion, and uniformly mixing under a protective atmosphere; and carrying out pressure sintering on the mixed powder, and carrying out secondary hydrogenation to obtain the zirconium hydride block containing samarium / europium / gadolinium. According to the invention, the absorption of the material to low-energy-segment neutrons can be obviously improved; and the preparation of the zirconium hydride block containing samarium / europium / gadolinium and the accurate regulation and control of doped elements are realized.

The invention provides a thermal radiation shielding assembly and a thermal radiation shielding system of a star imitator, the thermal radiation shielding assembly comprises a plasma container and a Dewar tank surrounding the periphery of the plasma container, and a first thermal radiation shielding part is arranged in an annular cavity formed between the plasma container and the Dewar tank; the first heat radiation shielding part is fixedly arranged on the periphery of the plasma container in a surrounding mode and comprises a cold pipe assembly, a first heat insulation assembly, a first cold shield assembly and a first supporting assembly; the cooling pipe assembly comprises a cooling pipe which surrounds and is attached to the peripheral wall of the plasma container to extend; the first heat insulation assembly extends around the plasma container, and the inner side surface of the first heat insulation assembly is attached to the peripheral wall of the cooling pipe assembly. The first cold shield assembly and the first heat insulation assembly extend around the plasma container at an interval; the first cold shield assembly is fixed to the outer wall of the plasma container through the first supporting assembly to form multiple heat radiation shielding layers, and high-temperature heat radiation from the plasma container can be isolated.

The present disclosure relates to an X-RAY detector including a base substrate and a plurality of detection units arranged on the base substrate. Each detection unit includes a light conversion element and a switching transistor, the light conversion element is configured to convert an optical signal into an electrical signal, and the switching transistor is configured to output the electrical signal to a reading signal line. Each detection unit further includes a radiation shielding structure located at a light-entering side of the detection unit, and an orthogonal projection of the radiation shielding structure onto the base substrate fully covers an orthogonal projection of the switching transistor onto the base substrate. The present disclosure further relates to a method for forming the X-RAY detector.

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 invention discloses a nuclear power plant secondary side cleanliness evaluation and radiation shielding method. The method comprises the following steps that S1, whole secondary circuit system equipment of a steam generator is washed; s2, full-coverage cleanliness inspection is carried out in the range from a filter screen of the electric main water feeding pump system to the secondary side of the steam generator, and meanwhile, if foreign matter is found, a cleaning tool is used for picking up the foreign matter; s3, evaluating the cleanliness condition, and if the cleanliness is qualified, ending; if the cleanliness is not qualified, returning to the step S1; s4, if the foreign matter falls off after the steam generator runs, stopping the equipment, and filling the secondary side of the steam generator with water to a preset position for reducing the radiation dose; and S5, picking up foreign matters by using a cleaning tool. Full-coverage cleanliness inspection is carried out in the range from the filter screen of the electric main feed pump system to the secondary side of the steam generator, effective verification of the secondary loop foreign matter flushing effect and radiation shielding when necessary are achieved, and foreign matter remaining on the secondary side of the steam generator is avoided.

The invention relates to an intelligent design method of a radiation shielding material based on cross-scale error feedback lock step, which comprises the following steps: determining a material component set and acquiring an atomic-scale graph structure of the material component set, and extracting intrinsic performance parameters such as heat conductivity and attenuation coefficient through an atomic-scale prediction module; and then, constructing a design variable vector in combination with a multi-physical field condition, calculating equivalent performance parameters of the composite material, establishing a cross-scale lock step mechanism, and triggering a molecular dynamics and Monte Carlo recalculation module to carry out correction when the deviation between a predicted value and a mesoscopic recalculation result exceeds a limit. Based on the correction parameters, a candidate material scheme is generated by using a multi-objective optimization algorithm; and performing gamma-ray and neutron shielding performance simulation on the candidate schemes through a Monte Carlo radiation transfer model accelerated by a deep neural network, and comparing with an experimental result to realize self-adaptive material design driven by cross-scale errors. According to the method, the design precision and efficiency of the radiation shielding material are remarkably improved.

A system configured to reduce scatter radiation around a surgical table during a medical procedure that may include at least one radiation shield configured to be connected to a surgical table with an attachment mechanism, wherein the at least one radiation shield includes one or more adjustable radiation shield segments coupled or releasably coupled to the at least one radiation shield. A device may include a pump in fluid communication with the one or more adjustable radiation shield segments comprising a pneumatic channel that is configured to at least partially inflate the pneumatic channel such that at least a first portion of the at least one radiation shield extends vertically above at least a portion of the surgical table, wherein a second portion of radiation shield is configured to extend below the surgical table. A device may include a controller configured to activate the pump.

The invention provides a floating nuclear power platform and a radiation shielding system thereof. The radiation shielding system comprises a primary shielding structure, a combined shielding structure and a containment shielding structure, the primary shielding structure covers the outer side of a reactor pressure vessel to perform primary shielding on the reactor pressure vessel, the combined shielding structure sleeves a loop pipeline and accessory equipment thereof, and the containment shielding structure is arranged in the containment structure; the primary shielding structure comprises a first heat preservation layer wrapping the outer side of the pressure vessel shell, a shielding water tank covering the first heat preservation layer and a shielding material layer covering the outer side of the shielding water tank, and the shielding water tank is hollow to contain water. The combined shielding structure comprises a high-density alloy layer and a second thermal insulation layer; the high-density alloy layer is sleeved outside the loop pipeline and accessory equipment thereof; the second thermal insulation layer is sleeved outside the high-density alloy layer; the containment shielding structure comprises a lead plate, a polyethylene plate layer, a boron-containing polyethylene plate layer and an outer steel plate layer which are arranged in the containment structure. According to the radiation shielding system provided by the invention, the total radiation shielding weight can be reduced by 20-40% while the radiation shielding effect is guaranteed.

An antenna apparatus includes a radiation shield between an antenna element and at least one radio frequency integrated circuit (RFIC) coupled to the antenna element. An antenna substrate includes a first dielectric layer having opposite first and second surfaces, and a first metallization layer attached to the second surface to form a ground plane. A base substrate includes at least one second dielectric layer having opposite third and fourth surfaces, and a second metallization layer having a first side attached to the third surface and a second side attached to the first metallization layer to form the radiation shield. The RFIC is RF coupled to the antenna element through at least one via extending through the base substrate and a coupling element within aligned openings of the first and second metallization layers.

This invention provides an adjustable radiation shielding device for radiology departments, relating to the field of radiology. It includes a bed frame with a radiation shielding mechanism. The radiation shielding mechanism comprises a fixed part, a displacement winding part, an auxiliary rotating rail, a locking mechanism, and a radiation shielding cloth. The fixed part is rotatably connected to the bed frame. The displacement winding part extends to both sides of the bed frame. One end of the locking mechanism is on the fixed part, and the other end is on the displacement winding part. The auxiliary rotating rail is fixed to the lower end of the bed frame and presses against the displacement winding part. A sliding block slides on the bed frame and is connected to the displacement winding part. One end of the radiation shielding cloth is fixed to the fixed part, and the other end is wound around the displacement winding part. The displacement winding part rotates with the assistance of the auxiliary rotating rail to wind up the radiation shielding cloth and move it to the end of the bed frame. Through the locking mechanism, the fixed part and the displacement winding part are connected together, and under external drive, the cloth rotates to the lower end of the bed frame for storage.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography.

The invention provides a radiation detection device and method for measuring ultra-wide-range gamma rays, and relates to the technical field of radiation detection.The radiation detection device comprises a detection assembly, a radiation shielding assembly and a signal processing assembly, and the signal processing assembly is located in the radiation shielding assembly; the detection assembly comprises three GM counting tubes with different measuring ranges and an acquisition circuit, and the acquisition circuit is used for converting signals output by the GM counting tubes into voltage counting signals; the signal processing assembly comprises a high-voltage control circuit, a power supply processing circuit, a pre-amplification circuit and a processor, the power supply processing circuit is used for converting a direct-current power supply signal and then transmitting the converted direct-current power supply signal to the high-voltage control circuit and the acquisition circuit, and the high-voltage control circuit is used for outputting a high-voltage power supply signal to each GM counting tube; the pre-amplification circuit is used for filtering and amplifying the voltage counting signals, and the processor is used for determining a target radiation dose rate according to the processed voltage signals. The radiation detection device provided by the invention has a relatively wide measuring range and relatively high measurement precision.

The invention relates to the technical field of materials for anti-nuclear radiation clothes, in particular to ethylene propylene rubber for anti-nuclear radiation clothes and a preparation method of the ethylene propylene rubber. A composite multi-walled carbon nanotube subjected to pretreatment; an accelerant; a fiber; a plasticizer; an anti-aging agent; stearic acid; through an innovative raw material formula and a corresponding preparation process, the novel ethylene propylene rubber material for the nuclear radiation prevention clothing is mainly researched and developed. In the aspect of raw materials, the radiation shielding performance of the ethylene propylene rubber is remarkably improved by introducing the specially pretreated composite multi-walled carbon nanotubes and reasonably matching the nano zinc oxide. Meanwhile, the specific dosage ratio of the ethylene propylene rubber, the accelerant, the fiber, the plasticizer and other raw materials ensures that the product has excellent shielding performance and also has good weather resistance, flexibility and comfort.

A radiation safety apparatus for a semiconductor processing system has a safety fence with a support frame and radiation shields defining containment regions associated with load ports of the semiconductor processing system. The containment regions are associated with radioactive sources that emit radioactive radiation, where radiation shields attenuate the radiation to a region external to the containment regions. The radiation shields have access doors movably coupled to the support frame to provide access to the containment regions. Interlocks are provided with the access doors to selectively lock the access doors in a closed position to control the access to the containment regions from the external region through the access doors. A controller controls the interlocks based on a radiation decay associated with each of the radioactive sources and a predetermined safe radiation exposure level.

The invention provides a radiation shielding assembly, a drug vial assembly system, a method of dispensing a drug vial assembly system, and a radiopharmaceutical infusion device. The radiation shielding assembly is used for shielding a medicine bottle assembly containing radiopharmaceuticals, and the medicine bottle assembly is provided with a puncture communication piece capable of transversely moving. The shielding body is provided with a top opening, a small bottle containing cavity and a combination port, and the medicine bottle assembly is contained in the containing cavity through the top opening. The containing cavity is provided with a circumferential matching wall, the distance between the matching wall and the vertical center line is gradually decreased from the starting end to the tail end, and a moving path is provided for assembly. The medicine bottle is guided to move along the wall, and the bottom puncture communicating piece is guided to transversely move inwards and is in butt joint with the combination port when reaching the assembly completion position. After assembly is completed, the puncture communicating piece is in butt joint with the combination port. According to the invention, only one needle puncturing the top of the medicine bottle is used as an inflow channel. Needle adjustment is not needed when medicine is nearly empty, operation is simplified, and the error rate is reduced.

The invention provides a doped yttrium hydride neutron moderation material and a preparation method and application thereof, and belongs to the technical field of radiation shielding materials. At least one of samarium, europium and gadolinium is doped in yttrium hydride in the form of hydride, and the mass ratio of metal yttrium to metal gadolinium to metal europium to metal samarium is controlled, so that the neutron moderation effect of the neutron moderation material can be improved. According to the invention, at least one of gadolinium hydride, europium hydride and samarium hydride is mixed with yttrium hydride under the protective atmosphere, so that the mass content of each element in the doped yttrium hydride neutron moderation material can be accurately controlled. According to the invention, the mixture is sintered and molded, and the sintering parameters of sintering and molding are controlled, so that the components of the mixture are sintered in a compact state, cracks generated by thermal expansion and cold contraction can be reduced, and the doped yttrium hydride keeps high density and has fewer cracks and defects.

The invention discloses a radiation shielding method and a radiation shielding body based on a multi-physics field synergistic effect, and the radiation shielding body is used for shielding a neutron-gamma mixed radiation field, and the radiation shielding method based on the multi-physics field synergistic effect comprises the steps: a first stage, absorbing neutrons and gamma rays at a radiation initial position through a first composite material; in the second stage, energy spectrum adaptive attenuation is carried out on the first residual radiation passing through the first stage through a second composite material, and the amount of the second composite material is gradually decreased in a gradient mode in the radiation propagation direction; and a third stage of performing path scattering on the second residual radiation passing through the second stage through a third composite material. According to the invention, the technical problem of insufficient shielding capability caused by difficulty in adapting to the dynamic shielding requirement of a neutron-gamma mixed radiation field when a traditional anti-radiation shielding body faces the neutron-gamma mixed radiation field generated in a BNCT treatment scene is solved.

The present invention relates to the technical field of polymer materials, and specifically to a tungsten-containing lead-free radiation-proof rubber glove and a preparation method thereof. The present invention overcomes the disadvantages of poor radiation-proof ability and poor anti-permeability performance. After the modified ethylene propylene diene monomer rubber is plastified, an activator and an antioxidant are added for the first stage of internal mixing, then carbon black, a composite reinforcing agent, a radiation shielding powder, and a dispersant are added for the second stage of internal mixing, and finally paraffin oil is added for the third stage of internal mixing to obtain a crude mixed rubber; the crude mixed rubber, the radiation shielding powder, the dispersant, a vulcanizing agent, and a vulcanization aid are mixed and open-milled to obtain a rubber sheet; after the rubber sheet is parked, filtered, injection molded, second-stage vulcanized, cleaned, and dried, a tungsten-containing lead-free radiation-proof rubber glove is obtained. The tungsten-containing lead-free radiation-proof rubber glove prepared by the present invention has strong radiation-proof performance and strong anti-permeability performance, and is suitable for the protection of complex radiation environments.

The invention discloses a radiation shielding case for charging equipment of an automobile battery swap station, and belongs to the technical field of radiation shielding cases, the radiation shielding case comprises a bottom plate, the upper surface of the bottom plate is in bolted connection with a battery swap station, the upper surface of the bottom plate is in welded connection with a vertical plate, and the upper surface of the bottom plate is in bolted connection with a motor; the device further comprises a rotating shaft, the rotating shaft is rotationally arranged in the vertical plate, and the tail end of the rotating shaft is fixedly connected with a fan. According to the radiation shielding cover for the charging equipment of the automobile battery swap station, at the beginning, the long pin is located at the position close to the connecting shaft, an operator can conveniently and rapidly change the battery through the battery bin, after battery changing, the motor is started and drives the threaded rod to rotate, at the moment, the long pin moves in the vertical direction under the action of the long plate and the limiting column, and when the long pin descends, the long pin moves in the vertical direction. When the shielding case is unfolded, the shielding case body on the surface of the connecting shaft is pulled open, even if the shielding case body is unfolded, the long pin moves to the lower side of the vertical plate finally, the shielding case body is completely unfolded, and the anti-radiation purpose is achieved.

A magnetic resonance imaging apparatus according to an exemplary embodiment includes a superconducting coil, a first container, a radiation shield, a second container, first to third pipes, and a switching assembly. The first container houses the superconducting coil which is immersed in refrigerant liquid, and also contains refrigerant gas generated by vaporization of the refrigerant liquid. The radiation shield houses the first container. The second container houses the radiation shield. The first pipe directs the refrigerant gas in the first container into an outside of the radiation shield. The second pipe allows the refrigerant gas from the first pipe, to pass through so as to enable the refrigerant gas to exchange heat with the radiation shield. The third pipe discharges the refrigerant gas from the first pipe, to an outside. The switching assembly directs the refrigerant gas from the first pipe, into the second pipe or the third pipe.

The invention discloses a continuous efficient heat storage and exchange converter and method based on convection-radiation conversion, and belongs to the technical field of industrial energy conservation. The converter is of a three-dimensional spiral body structure, and the spiral body is formed by stacking 300-500 layers of shaftless equal-diameter spiral wires; the key structure sizes of the spiral wire comprise a wire diameter d, a spiral diameter D and a screw pitch B; wherein the thread diameter d of the spiral thread is 0.5-1 mm, and the spiral thread diameter D and the thread pitch B are respectively 1-2 mm; the specific surface area of the spiral body is 1800-3000m < 2 > / m < 3 >, so that the high convection heat exchange area is ensured; the thickness of the spiral body is 300-500mm, so that the radiation emissivity is close to 1; the porosity of the spiral body is gradually changed from 0.5 to 0.9 from the center to the heat exchange surface, so that radiation shielding in the three-dimensional spiral body is reduced. The device has the advantages that the device is suitable for efficient recycling of flue gas waste heat of various industrial furnaces, and the waste heat recycling efficiency can be effectively improved to 75% or above; particularly, a heat accumulating type heating furnace capable of reversing periodically can be replaced, the problems of furnace temperature and pressure fluctuation, flue gas waste heat loss and the like caused by frequent reversing in the traditional heat accumulating type heating process are solved, and continuous and efficient production of an industrial furnace is achieved.

The invention discloses an epoxy composite coating with radiation attenuation performance and a preparation method thereof. The preparation process of the composite coating comprises the following steps: firstly, preparing a core-shell structure anti-radiation filler of a silicon dioxide shell layer through auxiliary ball milling of tetraethoxysilane, and then preparing a modified anti-radiation filler through further surface treatment of gamma-aminopropyltriethoxysilane (KH550); and finally, mixing the modified filler with epoxy resin to obtain the epoxy composite coating with the radiation shielding performance. The prepared composite coating has good thermal stability and adhesive strength, has excellent X / gamma ray attenuation performance and can be used for radiation attenuation of the surface of metal equipment.

Valve (1) for closing a passage between a heating chamber (100) and a reaction chamber (120), comprising a housing part (3) forming a valve chamber (5), with a first opening (7) having a first opening edge (7a) oriented towards the heating chamber (100), and a second opening (9) having a second opening edge (9a) oriented towards the reaction chamber (120), wherein the first opening (7) and the second opening (9) together with the valve chamber (5) form a transport channel (11) between the heating chamber (100) and the reaction chamber (120) when open, and comprising a first locking flap (13) for closing the first opening (7), wherein the first locking flap (13) is pivotably arranged in the valve chamber (5) and is pivotable from an open position to a closed position, wherein the first locking flap (13) in the closed position abuts the first opening edge (7a) in a sealing manner.wherein a sealing device (17) is arranged on the first locking flap (13), which can be pressed against the first opening edge (7a) in the closed position, and with a second locking flap (19) for closing the second opening (9), wherein the second locking flap (19) is pivotably arranged in the valve chamber (5) and can be pivoted from an open position to a closed position, wherein the second locking flap (19) rests against the second opening edge (9a) on the side facing the valve chamber (5) in the closed position, wherein in the open position the second locking flap (19) is arranged in front of the first locking flap (13) in the direction of the transport channel (11) and forms a heat radiation shield for the sealing device (17) against heat radiation from the transport channel (11).

The invention discloses a composite shielding collimator suitable for a complex mixed radiation field, belongs to the technical field of radiation shielding and measurement, and mainly solves the problems of low signal-to-noise ratio, high space background and mixed energy spectrum caused by the mixed radiation field of high-energy neutrons, gamma rays and the like in a fusion device and the problem that traditional equipment is heavy and difficult to flexibly adjust. The composite shielding collimator adopts a cylindrical shielding structure formed by aluminum oxide, boron-containing polyethylene, boron carbide and lead from outside to inside, and background interference and secondary radiation are remarkably inhibited by moderating and absorbing neutrons step by step and effectively shielding gamma rays; the neutron and gamma ray detector is integrally integrated on a rotatable supporting mechanism, unification of excellent radiation shielding performance and detection flexibility is achieved, and the neutron and gamma ray detector is mainly used for high-precision neutron and gamma ray diagnosis in complex radiation environments such as a magnetic confinement fusion device.

The invention relates to a preparation method of a liquid metal reinforced radiation shielding coating material, and belongs to the technical field of radiation shielding materials. The liquid metal is subjected to ball milling for a period of time at a certain rotating speed under the nitrogen protective atmosphere to enable the particle size to be 1t; 10 [mu] m; then the liquid metal is placed in a silane coupling agent solution according to a certain solid-to-liquid ratio and runs in a constant-temperature oscillator at a certain oscillation frequency for a period of time, and the surface of the liquid metal is coated with a layer of siloxane for modification treatment; weighing the modified liquid metal and barium sulfate according to a certain mass ratio, and carrying out ball milling in a planetary stirrer at a certain ball milling rate so as to uniformly mix the modified liquid metal and the barium sulfate; and mixing the obtained mixture with talcum powder and water according to a certain mass ratio, and uniformly stirring to obtain the liquid metal reinforced base radiation shielding coating material. The modified liquid metal is uniformly distributed in the barium sulfate matrix to serve as the composite coating, so that the lead equivalent and the radiation shielding performance are remarkably improved.

The invention relates to the technical field of radiation protection, in particular to tungsten-containing lead-free rubber with a radiation shielding function and a preparation method of the tungsten-containing lead-free rubber. The tungsten-containing lead-free rubber overcomes the problems of poor shielding performance and poor mechanical performance of the existing tungsten-containing lead-free rubber. The preparation method comprises the following steps: firstly, carrying out maleic anhydride grafting modification on ethylene propylene diene monomer, and carrying out silane coupling agent treatment and polydopamine coating coating on a composite tungsten filler; then, multiple components such as the modified rubber and the composite fibers are sequentially put into an internal mixer to be subjected to rough mixing and refined mixing, and then the tungsten-containing lead-free rubber is obtained through open mixing and vulcanization treatment. All the materials and the process have a synergistic effect, so that the rubber has excellent radiation shielding performance and mechanical performance, can replace a traditional lead rubber material, and has a good application prospect.

A radiation shield assembly is described, configured to block radiation emanating from a radiation source from reaching a user. Two shields are supported by a support arm, and are configured to rotate and translate relative to one another about the support arm's longitudinal axis. This allows the shield to be easily configured and reconfigured as necessary to visualize various parts of a patient's body via radiography.

A cryogenic cooling module comprises a vacuum chamber mmoodduullee (501) and, sup¬ ported therein, thermal stages (301, 302, 303) spatially displaced from each other in a first direction (310) and one or more heat radiation shields (304, 305, 306) corresponding to at least a subset of said thermal stages (301, 302, 303). A shape of said vacuum chamber module (501) is at least partly defined by one or more planar sides extending in said first direction (310). The vvaaccuuuumm chamber module (501) has an opening on one planar side, with a vacuum finish arrangement on edges (502) of said opening for enabling gastight closing. The thermal stages (301, 302, 303) reach, in a second direction (311) perpendicular to said first direction (310), to a first common interface plane (503) at or close to a plane defined by the edges (502) of the opening. Each of said one or more heat radiation shields has a respective second opening, edges of which reach to said first ccoommmmoonn inter- face plane (503).

The invention discloses preparation of flexible multifunctional anti-radiation shielding polyester filament yarn, and relates to the technical field of polyester. A ceramic filler precursor is prepared through electrostatic spinning, and nano lignin, polysilazane and aluminum oxide are used. A precursor is pretreated before calcination, carbides are formed through hot pressing, and meanwhile, a compact and continuous physical barrier can be formed in the shielding filler by means of the continuity of fibers and the cross-linking effect between the fibers. After high-temperature pyrolysis, lignin is converted into amorphous carbon, silicon carbide and silicon nitride ceramic grains are wrapped, a filler containing Si, Al and N is formed, radiation is effectively attenuated, and the shielding effect is enhanced. In addition, through combined use of the silane coupling agent and the compatilizer, the dispersity of the filler in the polyester chips is improved, the high-content polyester master batch is prepared, and the radiation shielding performance of the polyester fiber is further enhanced.

This utility model relates to the field of experimental analytical instruments technology, and discloses an easy-to-clean experimental analytical instrument, including an analyzer body. A display is fixedly connected to the top of the analyzer body, control buttons are provided on the surface of the analyzer body, a rotating shaft is fixedly connected to the top of the analyzer body, a cover is fixedly connected to the surface of the rotating shaft, a rear plate is provided at the rear of the analyzer body, and support feet are fixedly connected to the bottom of the analyzer body. A limiting plate is fixedly connected inside the analyzer body. This utility model allows the curved plate to be rotated out from inside the limiting plate by pressing the handle. Under the action of a spring, the entire placement plate is removed from inside the analyzer body, facilitating subsequent cleaning and maintenance. By incorporating a radiation shield, the radiation generated inside the analyzer body during operation is isolated inside the analyzer body, preventing harm to the human body.