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 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 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 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.

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 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 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 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.