61results about How to "Enhanced Radiation Protection" patented technology

The invention discloses a method for preparing anion far-infrared short fibers employing waste renewable polyester bottle flakes. The method comprises the following steps: pretreating and drying the recycled waste renewable polyester bottle flakes; carrying out drying treatment on far-infrared masterbatch and anion masterbatch; feeding the dried polyester bottle flakes, the far-infrared masterbatch and the anion masterbatch to a special metering feeder for mixing, so as to obtain a mixture; carrying out melted extrusion on the mixed mixture by a screw to obtain a melt; filtering the melt, metering and spinning, cooling by cross blowing, winding and oiling, feeding by traction, filling fibers and doffing; carrying out bundling treatment on the fibers inside a barrel, and carrying out the procedures such as drafting, oiling, fiber folding, curling, thermoforming, cutting off and the like by oil bath, so as to obtain the anion far-infrared short fibers. The method disclosed by the invention is reasonable in preparation technology, and strong in maneuverability. The product prepared by the method disclosed by the invention is lower in selling price than the product prepared from native polyester. Therefore, the method has good economic benefits and social benefits.

The invention discloses a disassembling technology and a dedicated disassembling device of detector assemblies. The disassembling technology comprises the following steps: moving a big and small vehicle assembly, releasing a gripping apparatus, lifting the gripping apparatus after gripping and disassembling one detector assembly, and clamping and cutting off the detector assembly by a shearing andshrinking assembly; putting the end part of the detector assembly into a low-level waste container; driving the detector assembly to rotate by a winding module in the shearing and shrinking assembly,pulling out the detector assembly from a guiding structure under the action of the shearing and shrinking assembly, coiling the detector assembly after winding into a tubular shape, and descending into a temporary storage container; disassembling other detector assemblies in the same group by repeating the steps; moving the big and small vehicle assembly after completing disassembly, winding thedetector assemblies, and descending into high-level waste containers; continuously disassembling detector assemblies in other groups by repeating the steps; recovering components to original storage places after completing the disassembly of all detector assemblies. According to the disassembling technology disclosed by the invention, a whole pull-out process is reasonably designed, the operatingtime is shortened, and good radiation protection is achieved by utilizing the shield of water in a refueling pool.

The invention relates to a rare-earth-based flexible nuclear radiation protection material, and a preparation method and application thereof. The nuclear radiation protection material is a medium-heavy rare earth powder coated with a coupling agent and a defoamer, and the medium-heavy rare earth powder has a particle size less than 10 microns, the coupling agent is 0.5-2.0% the mass of the total medium-heavy rare earth powder, and the defoamer is 0.2-1.0% the weight of the total heavy rare earth powder. During the preparation, a medium-heavy rare earth powder is dried, and the dried medium-heavy rare-earth powder is coated with the coupling agent and the defoamer. According to the present invention, the rare earth composite material with good neutron absorption performance, no secondary radiation pollution, light weight and cheap price is selected for replacing an existing heavy metal composite material, and medium-heavy rare earth is used as a neutron absorption body for preparing theradiation protection product. The neutron shielding performance is higher than the shielding performance of traditional lead, boron carbide and other heavy elements; the protection effect on gamma ray is superior to those of lead, boron carbide and other heavy elements, and the protection material disclosed by the invention has good nuclear radiation shielding performance, mechanical properties and construction performance, and has advantages of crack resistance, corrosion resistance and heat resistance.

The invention provides a multiphase flow flowmeter which comprises an each-phase-content measuring device and a multiphase flow velocity measuring device. The each-phase-content measuring device comprises an emitting device, a detector and a processor, wherein the emitting device can emit X rays of different energies to a multiphase flow body, the detector is used for detecting X rays exiting from the multiphase flow body, and the processor can calculate the content of each phase according to the attenuation coefficient of the X rays and the correlation between liquid content and oil-water ratio; and the processor is connected with the detector. The multiphase flow flowmeter provided by the invention can be used for metering the flow rate of oil, water and gas multiphase flow and can realize full non-contact measurement.

The invention discloses a radiation-proof thermal control coating. A low-atomic-number material is utilized as a surface coating of the thermal control coating, a medium-atomic-number material is utilized as an intermediate coating of the thermal control coating, and a high-atomic-number material is utilized as a bottom coating of the thermal control coating. Compared with a ZnO coating, the coating disclosed by the invention has the advantages that the radiation protection capability is improved by over 10%, the solar absorption ratio alpha s of the coating is about 0.152 and the thermal emissivity epsilon is about 0.886 and is equivalent to that of a ZnO white paint under the same surface density.

The invention discloses a preparation method of carbon nanotube-conducting high-polymer material / ferrite composite polyurethane for radiation protection, which comprises the following steps: (1) synthesis of M-type ferrite hollow spheres; (2) preparation of conducting high-polymer material / ferrite composite hollow microspheres; (3) preparation of nickel composite carbon nanotube material; (4) preparation of block polyurethane solution; and (5) preparation of carbon nanotube-conducting high-polymer material / ferrite composite polyurethane. By improving the key material composition, the parameters in the treatment and preparation techniques (such as raw material varieties and proportioning, reaction temperature and time and the like) and the like, compared with the prior art, the method disclosed by the invention can effectively solve the problem of narrow absorption frequency band of the existing radiation protection material. The material has small effective thickness for radiation protection, is convenient for actual use, and is low in preparation technique cost.

The invention discloses an automatic synthesis device for [<18F>]AlF aluminum fluoride labeled radiopharmaceuticals, and belongs to the field of nuclear medicine and molecular imaging. The device structurally comprises an injection pump, a one-way n distribution valve, a two-position ten-way valve, a two-position three-way valve, a product purification solid-phase extraction column, a micro anionexchange column for <18>F concentration, a waste liquid bottle, a product collection bottle and a heating marking assembly, and is used for realizing the processes of <18>F ion concentration leaching,heating labeling, product purification and the like. Compared with devices in the prior art, the automatic radiopharmaceutical synthesis device has the advantages of realization of efficient and automatic synthesis of [<18>F]AlF type positron imaging agents, great improvement of the reproducibility and reliability of radiopharmaceutical production, great reduction of the radiation dosage of operators, and provision of equipment guarantee for research, development and clinical conversion of positron imaging agents.

The invention relates to the field of wireless monitoring, in particular to a staff safety defending system based on a ZigBee wireless sense network. The system comprises n sensor nodes, a gateway node, an inspection workshop monitoring centre, pre-programmed monitoring software arranged on the inspection workshop monitoring centre, and an inspection workshop access control system, an inspection operation table and an acousto-optic alarm device which are connected with the inspection workshop monitoring centre, wherein n is a positive integer; the sensor nodes are connected with the gateway node through a ZigBee wireless communication protocol; the gateway node is accessed into the inspection workshop monitoring centre through an Ethernet network; and the inspection workshop monitoring centre is used for operating the monitoring software and correspondingly controlling the access control system, the inspection operation table and the acousto-optic alarm device according to the data treatment result of the monitoring software. According to the method provided by the invention, an inspection workshop wireless monitoring network is designed, so that the radiation protection capability of inspection workshop staffs is enhanced and the safety of staffs is improved.

The invention provides a natural composition for improving the health condition of skin. The natural composition is prepared from the following raw materials in parts by weight: 3-8 parts of pomegranate peel extract, 3-8 parts of centella extract, 1-5 parts of radix sophorae flavescentis extract, 1-5 parts of mangosteen extract and 8-15 parts of grifola frondosa extract. The natural composition is prepared from plant-source natural ingredients with a reasonable proportion, has the effects of bacterium resistance, allergy resistance, oxidation resistance and radiation resistance, and can be used for improving the health condition of skin from inside to outside. When being added into a skin-care product, the natural composition is safe to use and wide in functions, can be used for resisting radiation, alleviating senescence, reducing skin sensitivity, preventing the skin from being injured by internal and external inflammatory factors, repairing wounds, relieving itching and the like, can effectively improve the health condition of skin, and is a safe and effective skin-care product.

The invention provides an electric heating garment. The electric heating garment comprises a garment body and a heating device, wherein the heating device at least comprises a battery, a starting switch, a controller and a plurality of heating pieces, the battery is installed at a specific position in the garment body; the starting switch and the controller are integrated in a special soft switchshell, and the battery is started and power supply modes are switched by touching and pressing the soft switch shell; the heating pieces are arranged in a plurality of areas of the garment body, and the areas of the garment body are heated after being powered by the battery. The problem that for the electric heating garment, battery working time is short under high-power heating battery is solved,the working capacity of the battery in severe cold areas is improved, the high-standard thermal comfort requirement is simultaneously met, and the thermal comfort of the electric heating garment is improved.

The invention belongs to the field of radiation protection materials, and discloses a tritium protection material and a preparation method thereof. By combination of reinforcing, toughening and tritium-penetration-delaying performances of a micro-nano inorganic matter and the radiation protection performance of a micro-nano metal compound containing metal elements namely lead and bismuth, and by adoption of a blending method, the micro-nano inorganic matter and the micro-nano metal compound are added into a rubber latex for molding and vulcanization to form a product through the methods of impregnation, coating and the like. According to the invention, by combination of the reinforcing, toughening and tritium-penetration-delaying performances of the micro-nano inorganic matter and the radiation protection performance of the micro-nano metal compound containing metal elements like lead and bismuth, the permeability, mechanical properties and radiation protection performance of tritium are simultaneously improved; with the rubber latex as a substrate, the micro-nano inorganic matter and the metal compound are conveniently and uniformly dispersed, and molding of the tritium protectionmaterial with various shapes is conveniently realized; meanwhile, energy consumption in the processing process of the material is reduced; etc.

The invention discloses a radioactive drug subpackaging hot cell. The radioactive drug subpackaging hot cell comprises an outer box body and a liner located in the outer box body. A protecting door, adrug feeding drawer and a drug discharging drawer are separately arranged on the front side wall of the outer box body, the protecting door corresponds to the liner, the drug feeding drawer and the drug discharging drawer are located below the liner, an operating hand hole is formed in the protecting door, an operating glove which stretches into the liner and corresponds to the operating hand hole is arranged on the front side wall of the liner, a drug feeding inner door and a drug discharging inner door are separately arranged on the bottom wall of the liner, the drug feeding inner door corresponds to the drug feeding drawer, the drug discharging inner door corresponds to the drug discharging drawer, and an air intake and exhaust system is arranged on the outer box body. The air cleanliness in the radioactive drug subpackaging hot cell can reach a hundred level, and it is unnecessary to concern that the inside purified environment is destroyed to affect the quality of the nuclide drug in the normal operation process. The radioactive drug subpackaging hot cell is reasonable in structural design and safe and convenient to operate, and functions of the radioactive drug subpackaginghot cell meet the industrial criterion.

The invention relates to an X-ray blood irradiator, belonging to the technical field of medical equipment for blood irradiation. The irradiator comprises an irradiation rack body, on which an irradiation chamber and an X-ray generation device are arranged. A rotary drum is arranged in the irradiation chamber and connected with a driving assembly of the rotary drum. An X-ray ball pipe is arranged on the rotary drum and connected with an X-ray generation device which is a high-voltage generator. An X-ray cooling unit and a control system are arranged on the irradiation rack body. The control system is connected to the driving assembly of the rotary drum and the X-ray generation device. The X-ray blood irradiator has the following beneficial effects: the high-voltage generator is utilized for generating high-voltage effect on a ball pipe; X rays generated are used for irradiating blood products; and no ray exists without a working condition.

The invention relates to the technical field of medical supplies, in particular to a lift type lead apron. At present, radiological protection for patients is not carried out in place during radiological examination in most medical institutions due to busy work, and accordingly hidden danger is remained for the patients. The technical scheme includes that the lower end of a screw support is assembled on an underframe, a screw is inserted into the screw support, a transmission gear is assembled in the middle of the screw, the screw is matched with a sleeve in a threaded manner, the upper end of the sleeve is fixed into a fixing seat, and a lead cloth suspension rod is connected with the fixing seat; a T-shaped connector is further sleeved on the outside of the sleeve, the upper end of a sleeve support rod is connected with a transverse connector of the T-shaped connector, and the lower end of the sleeve support rod is fixedly connected with the underframe in a threaded manner; the lower end of a worm support is connected with the underframe, and a worm is nested in a fixing ring at the upper end of the worm support; the worm is meshed with the transmission gear, and one end of the worm is connected with a crank. The lift type lead apron has the advantage that the crank can rotate clockwise (anticlockwise), so that the lift type lead apron can easily ascend and descend.

A supported radiation protective garment is presented that can be worn by a medical provider under a standard surgical gown during procedures that involve the use of radiation. When used by the provider, the protective garment is lifted by vertical support members which can be extended downward and retracted upward. Rolling or sliding means at the lower end of the vertical support members allow the provider to move unhindered while wearing the radiation protective garment. The provider has access to a control mechanism that allows the shifting between retracted and extended positions of the vertical support members without breaking sterility. An alternative embodiment presents an upper apron portion of the protective garment, which can be manually connected by an assistant to a lower rolling base portion. The invention allows the provider to wear a heavy protective garment, offering significantly better radiation protection than standard ‘lead aprons’, while not being burdened by the weight of the garment. Further, the invention allows to maintain sterility at all times, and gives two or more providers, each wearing this protective garment, the option to work and move in close spatial proximity to each other.

Belonging to the technical field of cosmetics, the invention discloses a skin care product for antiallergic repair and a preparation method thereof. The skin care product for antiallergic repair comprises the following components: stem cell exocrine factor lyophilized powder, stem cell inclusion lytic factor lyophilized powder, hyaluronic acid, butanediol, an olive leaf extract, a purslane extract, an evening primrose extract, chamomile hydrolat and purified water. The stem cell secretion factor and stem cell inclusion lytic factor contained in the skin care product provided by the invention are prepared by low temperature freeze drying of a cell culture solution and a cell suspension, and the contained various stem cell secretion factors can promote the repair and regeneration of cells; the olive leaf extract, the purslane extract, the evening primrose extract and the chamomile hydrolat can relieve sensitive skin symptoms and improve skin resistance. The skin care product disclosed bythe invention can rapidly and effectively relieve anaphylactic reaction, improve the resistance of the body itself, and also can play a repair role.

The invention discloses a functionalized carbon nanotube modified resin-based composite radiation protection material and a preparation method thereof. The material is formed by jointly curing a radiation protection element / carbon nanotube compound, epoxy resin, a curing agent and a coupling agent. The preparation method comprises the following steps: dispersing the carbon nanotube in sulfuric acid, performing gamma-ray irradiation, conducting dispersing in acetone, adding various radiation protection function elements and a coupling agent, and fully conducting stirring and performing ultrasonic dispersion to obtain a radiation protection function element / carbon nanotube compound; and adding the carbon nanotube compound dispersed in acetone into epoxy resin, adding a curing agent, and carrying out vacuum curing to obtain the material. Through the synergistic effect of various radiation protection functional elements and the special structure of the carbon nano tube, the composite material has excellent radiation protection and radiation resistance, has good mechanical properties and low density, can be applied to the fields of nuclear energy, nuclear technology, aerospace engineering and the like, and provides effective radiation protection for workers and instruments and equipment.

The invention relates to an 11C-labelled EGFR positron tracer and a preparation method and application thereof, and belongs to the technical field of medicinal chemistry. The 11C-labelled EGFR positron tracer is shown in the formula I. The tracer can completely reflect physiological and biochemical processes of clinical medication AZD9291 in cell tissue, by using the tracing effect of positron radionuclide, the pharmaceutical metabolism process in tumor cells and tissue is reflected, and the tracer has an important significance in research on tumor mechanisms, evaluation of medicinal cure effects and treatment monitoring. Especially for positron emission tomography (PET / CT), 11C-labelled AZD9291 is a developer high in practical value.

The invention discloses a shielding structure and a shielding system for dismounting a reactor detector assembly and a using method, a left shielding body and a right shielding body are arranged in aleft-right layout form, when an actuator is in driving connection with a driving body A or / and a driving body B, the left shielding body and the right shielding body are driven to rotate around a leftshielding shaft and a right shielding shaft respectively; when the detector assembly is grabbed, the left side shielding body and the right side shielding body are driven to rotate reversely, so thata gap capable of passing through the detector assembly gripper and the detector assembly is formed between the left side shielding body and the right side shielding body;after the detector assembly is lifted to a certain height by the detector assembly gripping apparatus; the detector assembly is sheared off by using a shearing tool; and at the moment, the left side shielding body and the right side shielding body are driven to rotate oppositely, and the gap between the left side shielding body and the right side shielding body is closed to form an integral shielding structure.

The invention discloses a nuclear reactor detector assembly dismounting device. According to the device, firstly, a large and small vehicle assembly is used for coarse positioning to the position above a to-be-dismounted detector assembly, then, a visual centering device is used for fine positioning to the position over the to-be-dismounted detector assembly, then, a detector assembly gripping apparatus is hoisted to the large and small vehicle assembly, and the detector assembly is pulled out of a reactor internals to a preset height; the shearing and winding device shears off the detector assembly, and the low-level section is hoisted by the detector assembly gripping apparatus under the cooperation of a crane and is stored in the low-level container; the high-level section is wound intomultiple layers by a shearing winding device and is stored in a temporary storage container; after the four storage containers are full, the four storage containers are integrally transferred into ahigh-level storage container; and the high-level storage container is transferred into a spent fuel pool after the high-level storage container is completely disassembled. The nuclear reactor detectorassembly dismounting device is good in reliability, high in efficiency, simple to operate and good in radiation protection performance.

The invention provides a multiphase flow flowmeter which comprises an each-phase-content measuring device and a multiphase flow velocity measuring device. The each-phase-content measuring device comprises an emitting device, a detector and a processor, wherein the emitting device can emit X rays of different energies to a multiphase flow body, the detector is used for detecting X rays exiting from the multiphase flow body, and the processor can calculate the content of each phase according to the attenuation coefficient of the X rays and the correlation between liquid content and oil-water ratio; and the processor is connected with the detector. The multiphase flow flowmeter provided by the invention can be used for metering the flow rate of oil, water and gas multiphase flow and can realize full non-contact measurement.

The invention relates to an apparatus for protecting eyes from radiation, in particular for protecting the lenses of medical staff from X-ray or other ionizing radiation during medical examinations. The aim of the invention is to devise an apparatus which is easy to use and ensures that eyes are shielded from X-ray radiation but that the wearer nevertheless has the best working and visual conditions. This is achieved in that a housing (1) consists of a shell-like frame (2) which surrounds the eye region and, laterally, the temples of the wearer, in that the shell-like frame is provided with aholding device (3) for placement on the head and with a bridge part (4) for positioning on the bridge of the nose, in that the frame (2) is provided with a front-side opening (5) in which a shield (6)that is impermeable to X-ray radiation is fitted and in that at least one reproduction device (9) for stereoscopically reproducing video information is provided within the frame (2) on the rear sideof the shield (6) facing the eyes, said reproduction device being coupled to an optical recording device or a camera (10) which is provided on the side of the shield (6) facing away from the eyes of the wearer.

The invention relates to a radiation-shielded door, especially for use in an X-ray testing device. Radiation shielded closures in the form of lead curtains are disadvantageous in that they graze the object to be tested, thereby impairing the same and no longer covering the entire opening of the radiation tunnel. These disadvantages can be avoided by using a radiation-shielded door which is configured by at least two movably arranged, radiation-absorbing lamellae (2) forming the door (1), the faces of which are levers interlinked to give a lazy tongs-type mechanism.

The invention discloses an arranging method of a main workshop group of a Tokamak magnetically-confined fusion power station. The arranging method of the main workshop group of the Tokamak magnetically-confined fusion power station comprises the steps that a Tokamak workshop is taken as a center, and a neutral beam power-source workshop, a magnet power-source workshop, a heating workshop, an auxiliary workshop, a tritium workshop, a hot cell, a steam turbine workshop and an electric workshop are arranged in a ring shape around the periphery of the tokamak workshop. The invention further discloses a structure of the main workshop group of the Tokamak magnetically-confined fusion power station. The requirements of commercial nuclear power stations can be met, and the space utilization rate and safety of the nuclear power stations are improved.

The invention discloses a detector component dismantling process and its special dismantling equipment. The large and small car components are moved and the gripper is lowered, and the gripper is lifted after the detector component is removed. The component is cut off; the end of the detector component is put into the low-level waste container; the winding module inside the shearing and shrinking component drives the detector component to rotate, and the detector component is pulled out from the guide structure under the action of the shearing and shrinking component, and wound The final detector assembly forms a cylindrical reel and falls into the temporary storage container; repeat the above action to remove other detector assemblies in the same group; move the large and small car assemblies after dismantling, roll the detector assembly and drop it into the high release container; repeat The above actions continue to remove other groups of detector components; after all the detector components are removed, restore the components to their original storage positions. The technology design of the whole extraction process of the invention is reasonable, the operation time is shortened, and the shielding of the water in the refueling pool is used to achieve good radiation protection.

The invention provides an Ir-192 radioactive source transportation protection device. The Ir-192 radioactive source transportation protection device comprises a vehicle body, wheels, a drawer and leadplates. The Ir-192 radioactive source transportation protection device is of a trolley structure. The wheels are respectively arranged on four corners of the bottom of the vehicle body, and the wheels are turnable wheel sets. The drawer is arranged in an inner cavity of the vehicle body, and the lead plates are arranged around the drawer. A radioactive source is placed in the drawer. An environmental dose alarm device is fixed to the vehicle body. According to the Ir-192 radioactive source transportation protection device, accidents such as loss and falling of the radioactive source can be effectively prevented, so that the radioactive source is safely, conveniently and efficiently transported and can easily cross a ground process pipeline.

The invention relates to a multimedia speech table for providing a green biochemical working environment, belonging to the field of office furniture. A prior multimedia speech table which is providedwith a CRT display and widely used in universities and other similar institutions has the design defect in the aspect of radiation protection, so that the invention aims at solving the problem. In thestructure of the speech table, a position between a kinescope and a keyboard below the table surface of the speech table is provided with an air isolation baffle; and the surface of the side of the air isolation baffle facing to the kinescope is provided with a metal lead plate in an adhibit way. With the utilization of the structure, the radiation protection of the sides and the back of the kinescope is effectively enhanced, and the related radiation biochemical harm is restrained. In addition, the air isolation baffle also contributes to guiding smelly hot gas from the CRT display toward the direction away from an operator. The multimedia speech table is beneficial to improving the working environment of a table user.

The invention relates to the technical field of high-voltage conveying, in particular to a high-voltage bushing for 35KV transmission. The bushing comprises a sleeve body and a central conductor, oneend of the sleeve body is provided with a high-potential connecting flange, the other end of the sleeve body is provided with a low-potential connecting flange, the central conductor is arranged in the sleeve body, the bushing further comprises a first shielding cylinder and a second shielding cylinder, the first shielding cylinder sleeves the central conductor, and the second shielding cylinder sleeves the first shielding cylinder. The central conductor positioned in the sleeve body is completely positioned in the first shielding cylinder; the first shielding cylinder is completely located inthe second shielding cylinder, the first shielding cylinder and the second shielding cylinder form two radiation protection layers, the radiation protection effect of the high-voltage bushing can besignificantly improved, the influence of the high-voltage central conductor on the body health of an electrical operator is reduced, and the first shielding cylinder and the second shielding cylinderare simple in structure and convenient to install, and the popularization and promotion are facilitated.

The invention discloses a method for disposing of low- and medium-level radioactive waste in rock caves, which includes the following steps: S1, setting up a disposal roadway in an underground cavern, and setting a unit cell at the lower part of the disposal roadway; S2, disposing the radioactive waste according to the radioactivity The level of radioactive waste is divided into three levels, which are medium-level radioactive waste, low-level radioactive waste, and very low-level radioactive waste. In the cells of the disposal roadway, the very low level radioactive waste is placed on the top of the cells of the disposal roadway until the disposal roadway is filled; S3, the disposal roadway is backfilled and sealed. The invention also discloses a structure for disposal of low and medium level radioactive waste in rock caves. The invention can effectively improve the space utilization rate of rock cave disposal.

The present invention relates to a fluoropyrrolopyrimidine compound and its preparation method and application. The fluoropyrrolopyrimidine compound has the structure shown in formula I. The present invention uses pyrrolopyrimidine compounds as 18 F-labeled precursors, a positron tracer of LRRK2 prepared by a nucleophilic substitution reaction, can accurately reflect differences in LRRK2 expression levels in LRRK2 wild-type transgenic mice and G2019S mutant transgenic mice without significant bone uptake , indicating that the compound has high specificity and sensitivity, is stable in vivo, is not easy to defluorinate, and can be quickly cleared through metabolic organs. The fluoropyrrolopyrimidine compounds provided by the invention can be used for PET imaging of LRRK2, and are of great significance for the research of neurodegenerative diseases.