67results about How to "Improve radiation stability" patented technology

Stabilized radiopharmaceutical formulations are disclosed. Methods of making and using stabilized radiopharmaceutical formulations are also disclosed. The invention relates to stabilizers that improve the radiostability of radiotherapeutic and radiodiagnostic compounds, and formulations containing them. In particular, it relates to stabilizers useful in the preparation and stabilization of targeted radiodiagnostic and radiotherapeutic compounds, and, in a preferred embodiment, to the preparation and stabilization of radiodiagnostic and radiotherapeutic compounds that are targeted to the Gastrin Releasing Peptide Receptor (GRP-Receptor).

The invention relates to a preparation method of a vitrification substrate for radioactive nuclear wastes, which is characterized by comprising the following steps: mainly taking (NH4) H2PO4, Fe2O3 and H3BO3 as raw materials, proportioning, mixing, melting for 2-3.5 hours at the temperature of 1100-1250 DEG C, forming, and annealing, thereby preparing a vitrification body with glass of an iron-boron-phosphorus system as the substrate. The invention combines the advantages of high irradiation stability of the vitrification body of the borosilicate system and large waste-loading capacity of thevitrification body of the iron phosphate system. The prepared vitrification body has the advantages of excellent chemical stability and good thermal stability. Moreover, the invention has the advantages of simple preparation process and easy engineering, and can be widely applied in the curing treatment of radioactive nuclear wastes.

The invention relates to the use of Dispersion Ceramic Micro-Encapsulated (DCM) nuclear fuel as a meltdown-proof, accident-tolerant fuel to replace uranium dioxide fuel in existing light water reactors (LWRs). The safety qualities of the DCM fuel are obtained by the combination of three strong barriers to fission product release (ceramic coatings around the fuel kernels), highly dense inert ceramic matrix around the coated fuel particles and metallic or ceramic cladding around the fuel pellets.

The invention provides a rare-earth-based aerogel material with a radiation shielding effect and heat insulation property and preparation and application of the rare-earth-based aerogel material. Thematerial comprises an aerogel matrix material and a rare-earth-based material, wherein the rare-earth-based material is compounded with the aerogel matrix material; the rare-earth-based material is selected from one or more of rare earth zirconate, rare earth titanate, rare earth tungstate and rare earth cerate; and the content of the rare-earth-based material ranges from 1wt% to 45wt%. The radiation shielding property and the fireproof heat insulation property are effectively combined by compounding the rare-earth-based material in aerogel, and the prepared material particularly meets the requirements of radiation shielding and fireproof heat insulation in the field of nuclear engineering.

The invention discloses a modified polylactic acid material under a low irradiation dose and a preparation method thereof, wherein the preparation method comprises the following steps of: 1. extruding a polylactic acid resin raw material, a sensitizing agent and other auxiliary agents in an extruding machine, or smelting and mixing in a reaction kettle to obtain a mixture, wherein the molecular weight of the polylactic acid resin raw material is 5, 000-50, 000; and 2. then irradiating a compound in step 1 by using an electron beam or a gamma-ray to obtain the modified polylactic acid material. In the invention, the polylactic acid obtained from the modified polylactic acid material under the low irradiation dose can be used as food and medical materials, the irradiation stability of the polylactic acid material obtained after modification is increased, the molecular weight of the modified polylactic acid obtained through the invention is greatly increased and is 100, 000-350, 000, the mechanical performance is also greatly improved, and the modified polylactic acid material can be used as the safe and environment-friendly food and medical materials.

The invention discloses broadband high-gain Vivaldi antenna which a dielectric substrate, a metal patch, a quadrangular metal patch, an impedance match microstrip line and a sector-shaped metal branch. The metal patch and the quadrangular metal patch are fixed in the top side of the dielectric substrate, the impedance match microstrip line and the sector-shaped metal branch are fixed in the bottomside of the dielectric substrate, the metal patch is provided with gradual-change trough line symmetric by taking the horizontal central axis as the center and provided with a horn-shaped opening, the gradual-change trough line is of index type gradual change, the bottom end of the gradual-change trough line is provided with a circular resonant cavity, the outer sidewalls of the gradual-change trough line are provided with comb shaped grids at equal interval, the quadrangular metal patch is positioned in the opening of gradual-change trough line, one end of the L-shaped impedance match microstrip line is connected to the sector-shaped metal branch, and the impedance match microstrip line and the sector-shaped metal branch serve as a feed structure. The Vivaldi antenna of the frequency range of 2.3-8.0GH is characterized by simple structure, wide frequency band and high gain.

The invention provides a beryllium-free molten salt reactor core using beryllium oxide for moderating, the molten salt reactor core is characterized by comprising a fuel grid and a reflective layer grid, the reflective layer grid is arranged outside the fuel grid, and surrounds the fuel grid, and the grid uses the beryllium oxide as a moderator. The beryllium in the beryllium oxide in the molten salt reactor core has (n, 2n) neutron multiplication reaction, reactor core neutron economy is improved, and design of a high proliferation thorium molten salt reactor can be designed.

The present invention discloses a method for preparing a fluorapatite ceramic solidified body. The method is characterized by comprising the steps of: taking and mixing 23-76 wt.% of calcium pyrophosphate, 8-26 wt.% of calcium fluoride, 0. 02-52wt.% of samarium oxide (europium oxide, gadolinium oxide), 0-15 wt.% of sodium carbonate, 0-16 wt.% of silica to obtain a mixture; grinding, drying, granulating, molding, discharging rubber and conducting vacuum hot pressing sintering on the mixture to obtain a fluorapatite ceramic solidified body. The method not only utilizes the phosphorus in high-level radioactive waste in a recycling way, but also can address the problem of low solubility of phosphorus and minor actinides nuclide in glass solidified body. The fluorapatite ceramic cured body prepared by the invention has excellent preparation geological stability, irradiation stability, mechanical stability, chemical stability and thermal stability, and can be used as a ceramic solidified body for safe treatment of minor actinides high-level radioactive waste with high toxicity, long half-life period and strong radioactivity.

The invention relates to a rule bed module type high temperature gas-cooled reactor and fuel ball arranging method in the field of nuclear reactor technology. It arranges the helium inside the graphite block reflector. The control rod and the absorbing small ball are position inside the graphite block reflector. The flue ball is quadratic arranged on the level of the graphite block reflector hollow cavity, the center deck of each four balls can be used as the location of the second layer ball so as to form the rule bed with the up end and the down end is graphite block reflector.

The invention provides a preparation method of a solidified body used for performing glass curing process on a low-medium radioactive waste. The method comprises the following steps: taking the components SiO2, H3BO3, Na2CO3 and CaO as the raw materials, compounding and mixing, melting for 2.5-3 hours at the temperature of 1250 DEG C, after that, pouring the materials to a mold which is pre-heated to be 500 DEG C and molding, keeping the temperature at 500 DEG C for 0.5-1 hour, and then reducing the temperature to be room temperature at a rate of temperature fall of 0.5-1 DEG C / min, then the product can be prepared. The solidified body prepared by the invention can be used for performing glass curing process on the low-medium radioactive waste, realizing the volume reduction maximization of the solidified radioactive waste, more conforming to the value pursuit of waste minimization in radioactive waste treatment, and realizing the inorganization and stabilization of the solidified waste.

A method for preparing porous fluorapatite ceramic adsorbing radioactive nuclide is characterized by including: using the materials in percent by weight: 50-80% of calcium pyrophosphate, 4-26% of calcium fluoride and 16-45% of calcium carbonate, and mixing, ball-milling, drying, press-forming, calcining, grinding, and screening to obtain fluorapatite powder; mixing the fluorapatite powder with polyethylene glycol solution, methyl cellulose solution and hydrogen peroxide solution, and performing microwave assisted pore-forming, drying and the like to obtain a porous fluorapatite ceramic blank; preparing porous fluorapatite ceramic adsorbing material via normal pressure sintering. The porous fluorapatite ceramic adsorbing material prepared herein has the advantages of high radiation stability, good thermal stability, high mechanical and chemical stability and the like, also has high specific surface energy and nuclide adsorbing capacity and may be used as an efficient adsorbing material for radioactive nuclide in high-radioactive waste liquid, thus effectively protecting human health and ecological environment.

An optical recording medium for fluorescent WORM discs comprising a fluorescent dye, nitrocellulose and film-forming polymer is disclosed. The medium provides a high capacity optical memory for WORM discs, including 3-dimensional optical memory systems.

A polymerizable thioxanthone according to Formula (I):wherein A represents a thioxanthone moiety; R1 and R2 are independently selected from the group consisting of a hydrogen, an alkyl group, an alkenyl group, an alkynyl group, an aryl group, and a heteroaryl group; n represents 1 or 2; and R3 represents a moiety including at least one free radical polymerizable group selected from the group consisting of an acrylate, a methacrylate, an acrylamide, a methacrylamide, a styrene group, a maleate, a fumarate, an itaconate, a vinyl ether, a vinyl ester, an allyl ether, and an allyl ester.

The invention relates to the use of Dispersion Ceramic Micro-Encapsulated (DCM) nuclear fuel as a meltdown-proof, accident-tolerant fuel to replace uranium dioxide fuel in existing light water reactors (LWRs). The safety qualities of the DCM fuel are obtained by the combination of three strong barriers to fission product release (ceramic coatings around the fuel kernels), highly dense inert ceramic matrix around the coated fuel particles and metallic or ceramic cladding around the fuel pellets.

The invention discloses a method for increasing the irradiation stability of a cement solidified body for radioactive spent resin, which belongs to the technical field of radioactive waste treatment. The method comprises the step: the irradiation stability of the solidified body is increased by adding hairs to a resin cement solidification recipe. The addition amount of the hairs is determined according to the following preferential proportion: the mass ratio of the hairs to cement is (0.005-0.01):1. The length of the added hairs can be in the range of 1.5 to 2cm. The preferential resin cement solidification recipe comprises the following components in a mass ratio: zeolite powder, dehydrated radioactive spent resin, water and the cement, wherein the mass ratio of the components is (0.05-0.1):0.45:0.3:1. In the invention, solidified body cracking caused by resin irradiation decomposition can be prevented by adopting the method of adding the hairs to the resin cement solidification recipe, thus, the irradiation stability of the solidified body is increased.

The invention discloses a Vivaldi antenna realizing low return loss and high gain at low frequency. The Vivaldi antenna is characterized in that an exponential gradient slot is loaded on the outer side of the CAVA. An EGSA antenna comprises a dielectric substrate, metal radiation sheets, a microstrip balun, an elliptical slot line and the exponential gradient slot. The metal radiation sheet are respectively fixed on the top surface and the bottom surface of the dielectric substrate. The impedance matching microstrip balun is composed of a linear gradient microstrip line and a metal patch withan elliptical slot line. The exponential gradient slot structure (EGS) is loaded on the outer side of the metal radiation sheets, the operating bandwidth of the EGSA at S<11> < -10dB is increased to 185% of that of CAVA and the EGS structure effectively improves the return loss in low frequency band.

The invention relates to the technical field of oil and grease processing, in particular to an oil pretreatment method and an oil microwave pretreatment device for achieving the oil pretreatment method. The oil microwave pretreatment device comprises a feeding hopper, a machine frame, a box, a discharging groove, a sampling assembly, a detector assembly and a control system, wherein the box is fixed in the middle of the machine frame, the feeding hopper is arranged on the right side of the box, the discharging groove is formed in the left side of the box, the sampling assembly is arranged at the discharging groove end, materials at the discharging groove end are sucked through the sampling assembly to a detector and are detected, and photos after detected by the detector are sent to the control system and subjected to material color identification and quantitative treatment. The method for evaluating the suitability of the intensity of oil microwave pretreatment is accurate and fast, and the oil microwave pretreatment device is capable of automatically adjusting and controlling the microwave treatment intensity, small in occupied area, high in efficiency and capable of saving energy consumption.

The invention provides a driving device with a gamma ray protection function and a robot. The driving device comprises a driving mechanism, a tail-end load of the driving mechanism and an electrical appliance component used for controlling the driving mechanism, and the driving device comprises a gamma ray protection structure used for containing the electrical appliance component; the gamma ray protection structure comprises a protection shell with a cavity inside and a protection shell end cover which is arranged at the upper end of the protection shell and used for supporting the driving mechanism, and a detachable end port sealing structure is arranged between the protection shell end cover and the top of the protection shell. According to the driving device with the gamma ray protection function, the electrical appliance component is placed in the protection structure with a gamma ray protection effect, and the end port sealing structure is designed to be detachable, so that the irradiation stability of an electronic device is effectively improved, and the driving device can be convenient to disassemble.

The invention discloses a preparation method of a MoS2 / YSZ (molybdenum disulfide / yttria stabilized zirconia) composite film with high wear resistance and radiation resistance. The preparation method comprises the following steps: firstly, preparing the MoS2 / YSZ composite film by adopting a radio frequency magnetron sputtering physical vapor deposition technology, and then performing thermal annealing treatment on the film to eliminate intrinsic defects of MoS2 crystals in the magnetron sputtering growth process. The obtained film MoS2 shows (002) preferred orientation, good crystallization performance, presents low friction, high wear resistance (average friction coefficient (0.05, wear life) 2*105 turns) and high wear resistance and radiation resistance, and achieves integration of low friction and radiation-resistant self-adaptation of the MoS2 / YSZ based composite film. Therefore, the composite film can be used for lubrication of mechanical moving parts in the irradiation environments of reactors and fusion reactors.

The invention discloses a method for preparing environment-friendly high-performance PVC (polyvinyl chloride) rack adhesive powder, and belongs to the field of high-polymer material modification processing. The method includes adding, by weight, toughening agents, solid toughening agents, nucleating agents, sensitizers, lubricants and antioxidants into 100% of polyvinyl chloride powder; sufficiently mixing raw materials with one another by the aid of color master batch to obtain mixtures, feeding the mixtures into an extruder, and extruding the mixtures from the twin-screw extruder; setting the temperatures of raw materials at various sections of temperatures of the twin-screw extruder in heating procedures, extruding the raw materials and then cutting the raw materials to obtain particleswith the sizes of 3-5 mm; irradiating the obtained particles by the aid of rays in the air, then grinding the particles at the low temperatures to obtain powder and packaging the powder. The method has the advantages that the nucleating agents are added into the environment-friendly high-performance PVC rack adhesive powder, accordingly, the crystallinity of PVC materials can be improved, free radicals is guaranteed to be sufficiently cross-linked, the irradiation stability and the temperature resistance of PVC can be enhanced, and the mechanical properties and the heat resistance of the PVCcan be improved.

The invention belongs to the technical field of special rubber, and particularly relates to nuclear radiation resistant vulcanized rubber and a preparation method thereof. The radiation-resistant rubber composition comprises the following raw material components in parts by weight: 80-90 parts of EPM rubber, 30-50 parts of a radiation-resistant auxiliary agent, 40-60 parts of a filling agent, 3-8 parts of a vulcanizing agent, 1.5-3.0 parts of an accelerant, 10-20 parts of a plasticizer and 2-5 parts of an anti-aging agent, and is characterized in that the radiation-resistant auxiliary agent comprises lead oxide, bismuth oxide, barium sulfate and / or antimony trioxide. The nuclear radiation resistant vulcanized rubber obtained according to the preparation method has stable protection and shielding performance on nuclear radiation in the actual use process, also has excellent comprehensive physical performance, and has the advantages of stable performance, safety and reliability.

Applicant's invention is a radionuclide generator resin material for radiochemical separation of daughter radionuclides, particularly 213Bi, from a solution of parental radionuclides, the resin material capable of providing clinical quantities of 213Bi of at least 20-mCi, wherein the resin material comprises a silica-based structure having at least one bifunctional ligand covalently attached to the surface of the silica-based structure. The bifunctional ligand comprises a chemical group having desirable surface functionality to enable the covalent attachment of the bifunctional ligand thereon the surface of the structure and the bifunctional ligand further comprises a second chemical group capable of binding and holding the parental radionuclides on the resin material while allowing the daughter radionuclides to elute off the resin material. The bifunctional ligand has a carbon chain with a limited number of carbons to maintain radiation stability of the resin material.

The invention relates to a preparation method of a vitrification substrate for radioactive nuclear wastes, which is characterized by comprising the following steps: mainly taking (NH4) H2PO4, Fe2O3 and H3BO3 as raw materials, proportioning, mixing, melting for 2-3.5 hours at the temperature of 1100-1250 DEG C, forming, and annealing, thereby preparing a vitrification body with glass of an iron-boron-phosphorus system as the substrate. The invention combines the advantages of high irradiation stability of the vitrification body of the borosilicate system and large waste-loading capacity of thevitrification body of the iron phosphate system. The prepared vitrification body has the advantages of excellent chemical stability and good thermal stability. Moreover, the invention has the advantages of simple preparation process and easy engineering, and can be widely applied in the curing treatment of radioactive nuclear wastes.

The invention provides a novel engineering plastic and a preparation method thereof. The novel engineering plastic is prepared from the following components: waste polycarbonate, polyethylene, an organic silicon solution, formaldehyde, alkali liquor, melamine, epoxy resin, xylene, modified calcium carbonate, a cross-linking agent, a flame retardant, an antioxidant and deionized water. The preparation process disclosed by the invention is simple, low in cost, high in production efficiency and environmental-friendly, and the prepared finished product has excellent mechanical strength, impact toughness and weather resistance.

The invention belongs to the technical field of special glass, and provides anti-ultraviolet absorption space radiation-resistant glass which comprises the following raw materials in parts by mass: 1.2-5.9 parts of cerium dioxide, 0.5-4.6 parts of neodymium oxide, 0.8-3.2 parts of lanthanum oxide, 0.7-3.5 parts of ytterbium oxide, 3.4-12.3 parts of sodium carbonate, 0.4-4.7 parts of aluminum oxide, 72.2-78.3 parts of silica sand, 5.7-10.7 parts of strontium carbonate, 4.6-11.3 parts of BaCO3, 0.3-1.5 parts of SeO2, 0.9-2.5 parts of bismuth trioxide, 0.5-1.6 parts of tellurium dioxide, 4.8-10 parts of potassium nitrate, 1.2-2.5 parts of antimonous oxide and 0.7-1.6 parts of sodium pyroantimonate. According to the technical scheme, the problem that in the prior art, the anti-irradiation performance, transmittance and mechanical strength of common glass in space application cannot meet deep space exploration is solved.

The invention discloses a solar spectrum total reflection type antistatic thermal control coating and a preparation method thereof, and belongs to the field of new materials. The thermal control coating material mainly comprises an ultra-wide band gap oxide pigment, an inorganic water glass binder and a functional auxiliary agent; the coating of the ultra-wide band gap oxide pigment has excellent particle radiation protection stability; and the prepared coating is a water-based environment-friendly coating, can be subjected to air spraying, brush coating or blade coating and has the room temperature curing characteristic. The solar absorptivity of the coating is as low as 0.08-0.09, the emissivity is 0.88-0.92, the surface resistivity is 105-107 ohm m, and the coating can be applied to thermal control systems of various spacecrafts serving under the synergistic effect of complex and severe environments such as space high solar heat flow, strong particle radiation, ionized layer charging and discharging and atomic oxygen environment.

The invention provides a uranium dioxide single crystal / nano-diamond nuclear fuel pellet and a preparation method thereof. The preparation method comprises the following steps of: S1, providing a UO2single crystal; S2, carrying out heat treatment on the UO2 single crystal; S3, coating the UO2 single crystal with a coating, namely sieving the UO2 single crystal particles, selecting the UO2 singlecrystal particles with a certain particle size, and coating the surfaces of the UO2 single crystal particles with a pyrolytic carbon coatingby adopting a chemical vapor deposition method; S4, powder mixing: putting the coated UO2 single crystal particles prepared in the step S3, nano-diamond powder and a sintering agent into a mixing tank according to a certain volume ratio, and performing sealedmixing; S5, carrying out charging; and S6, densification sintering: specifically, enabling a pressed mold to be subjected to discharge plasma rapid sintering to obtain the composite fuel. According tothe method provided by the invention, the heat conductivity of the fuel pellet is obviously improved, so that the safety of the uranium dioxide fuel pellet is improved.

The invention discloses a preparation method of heat-resisting and corrosion-resisting engineering plastic. The preparation method disclosed by the invention is characterized in that a third phenolphthalein monomer is introduced in a preparation process of master batch, and a flexible diethanol part in a polyester macromolecular chain is replaced by a rigid phenolphthalein group, so that a rigid diacid monomer and rigid phenolphthalein monomer connected segment is formed, the rigidity and the crystallization performance of a whole molecule are enhanced, and glass-transition temperature and a melting point are raised. According to the preparation method disclosed by the invention, by adopting a radiation crosslinking process, heat resistance and corrosion resistance of the engineering plastic are improved; according to an adopted radiation crosslinking agent, benzene-containing anhydride is used as a synthetic raw material, and a benzene ring structure is introduced, so that the melting point of a crosslinking promoter is improved, and the radiation resisting stability of the crosslinking promoter is further improved; prepared engineering plastic adopts the radiation crosslinking promoter; having increased molecular weight, a benzene ring structure and low high-temperature volatility, the radiation crosslinking promoter has good compatibility with the engineering plastic; according to the preparation method disclosed by the invention, flame retardant materials such as graphene, titanium dioxide and halloysite nanotubes and aging-resisting materials such as wollastonite needle-like fibers form a compound synergistic effect, so that the flame retardant property and the aging resisting property of the engineering plastic are greatly improved.