12 results about "Thorium oxide" patented technology

This invention provides a 210 The purification method for Po includes: under vacuum, distilling irradiation of a thorium oxide target to generate distilled gas, condensing the distilled gas in a collecting pan to obtain a distillate; soaking the collecting pan in nitric acid solution to obtain a soaking solution, evaporating it to obtain a dried product, dissolving the dried product in hydrochloric acid solution to obtain a leachate; pouring the leachate into a chromatography column packed with chloride-form anion exchange resin, rinsing the chromatography column with hydrochloric acid solution, and draining the liquid; rinsing the chromatography column with hydrochloric acid solution to allow the chloride-form anion exchange resin to react with the thorium oxide. 210 Po separation yields a product containing... 210 The purified solution of Po was diluted to obtain a diluent. Tetravalent tellurium, a reducing agent, and isopropanol were added to the diluent to obtain a mixture. The mixture was filtered to obtain an α-measurement source, and the α-spectrum was obtained by measurement. The purification method of this embodiment utilizes a thorium oxide target obtained after irradiation. 210 The differences in physicochemical properties between Po and impurities enable... 210 Purification of Po.

The application discloses a preparation method of thorium carbide, which comprises the following steps: mixing thorium dioxide and carbon according to a fixed molar ratio to obtain a solid mixture; mixing the solid mixture and anhydrous ethanol according to a solid-liquid ratio of 1:1.5 to obtain a precursor raw material; stirring the precursor raw material until the anhydrous ethanol is completely volatilized, so as to further mix the precursor raw material uniformly; placing the stirred precursor raw material in a vacuum or an argon environment to perform a carbothermic reduction reaction, so as to obtain a thorium carbide product; and crushing and grinding the thorium carbide product to obtain a thorium carbide powder. The application solves the problems of low purity, environmental pollution and high cost of the thorium carbide in the prior art.

The present disclosure relates to a method 200 for producing polytetrafluoroethylene (PTFE) thorium oxide membrane. The method 200 comprising combining metal oxide and polytetrafluoroethylene (PTFE) powder to form a first mixture and screening the first mixture to remove aggregates. The method 200 also comprising mixing a lubricant, wetting agent, and optional pigments to form a second mixture and spraying the second mixture over the first mixture. The method 200 also comprising compacting the homogeneous product into a preform and extruding and calendaring the preform to obtain a tape of desired thickness. The method 200 also comprising heating the tape formed to evaporate the lubricant and sintering the tape to fuse polytetrafluoroethylene (PTFE) and encapsulate the thorium oxide particles. The method 200 also comprising cooling the sintered tape at a controlled rate to prevent crack formation and maintain the integrity of the membrane structure.

The invention discloses a method for preparing an ion source filament protective thermal adaptation thorium oxide coating, and particularly relates to the technical field of inorganic membrane materials. The method comprises the following steps of S1, base material pretreatment, S2, pre-sputtering treatment, S3, chromium transition layer deposition, S4, Cr-ThO2 gradient co-sputtering layer deposition, S5, pure thorium oxide functional layer deposition and S6, vacuum annealing treatment. According to the method for preparing the ion source filament protective thermal adaptation thorium oxide coating, through the double buffering design of the chromium transition layer and the Cr-ThO2 gradient layer, continuous transition of the thermal expansion coefficient between the alloy matrix and the thorium oxide coating is achieved, and the interface stress in the cold and hot circulation process is effectively relieved. Tests show that after the coating is subjected to hot and cold impact for 20 times at the room temperature to 650 DEG C, the phenomena of cracking and peeling are avoided, the thermal stability is obviously superior to that of the prior art, each coating is prepared by adopting a magnetron sputtering process, the film layer is compact and uniform, the porosity is lower than 2%, and the coating is far superior to that prepared by adopting a traditional sol-gel method and a spray sintering method.

To provide a fusion-driven subcritical reactor that is more efficient and safer. [Solution] A fusion-driven subcritical reactor is a nuclear reactor that starts and operates by amplifying neutrons obtained from nuclear fusion and supplying the amplified neutrons to a reactor that holds subcritical nuclear fuel by external neutrons. It consists of a main neutron source that generates DD neutrons through a nuclear fusion reaction, a cascade member that surrounds the main neutron source, separates fusion / fission neutrons, multiplies the fast fission neutrons generated by nuclear fission, and slows down the fast fission neutrons, and a cascade member that surrounds the cascade member and is mainly made of thorium oxide ( 232 It is equipped with a subcritical main fission blanket made of uranium dioxide (ThO2), and a neutron flattening blanket that has a neutron source located around the outer periphery of the main fission blanket to improve the containment of fission neutrons.

The application belongs to the technical field of conductive ceramic materials, and particularly relates to a conductive ceramic material and a preparation method and application thereof. According to mass parts, the conductive ceramic material comprises the following components: 79-97 parts of beta-aluminum oxide, 0.5-2 parts of yttrium oxide, 0.7-3 parts of thorium oxide, 1-8 parts of zirconium oxide, 0.5-2 parts of molybdenum dioxide, 0.2-3 parts of copper oxide and 0.1-3 parts of zinc oxide. Due to the introduction of high-activity aluminum oxide nano powder and yttrium oxide, the sintering temperature can be greatly reduced, the energy consumption is reduced, the preparation cost is reduced, the competitiveness is improved, and the application is conducive to popularization.

The invention discloses a method for separating uranium-233 in a thorium oxide target after reactor irradiation, and relates to the technical field of radiochemistry, nuclide separation and nuclear measurement. The separation method comprises the following steps: dissolving a thorium oxide target material; the preparation method comprises the following steps: pretreating methyl trioctyl ammonium chloride (A336) levextrel resin and diamyl amyl phosphate (DAAP) levextrel resin; loading the thorium oxide target material dissolving solution on a column; purification of uranium-233 and separation and recovery of thorium. According to the method, a double-column combination mode of A336 extraction resin and DAAP extraction resin is adopted, efficient separation and purification of trace uranium 233 in a thorium oxide target after reactor irradiation are achieved, and a large number of thorium matrixes and various fission products can be effectively removed; wherein the removal rate of thorium is not lower than 99.99%, the total recovery rate of uranium-233 is not lower than 90%, the thorium matrix is recovered, the total recovery rate is not lower than 90%, and the total removal rate of gamma nuclide is not lower than 99.99%.

The invention relates to a carbon-containing uranium and thorium mixed fuel microsphere and a preparation method thereof. The preparation method comprises the following steps: carrying out ball milling on ThO2, UO2 and carbon powder to refine until D50 is less than or equal to 2 microns; thorium dioxide, uranium dioxide and carbon powder are put into a sound wave mixing device according to the mass ratio of 3: 7: 1, deionized water is added till the solid content is 30%-40%, and mixed powder is obtained through dispersion in the argon atmosphere of the sound wave mixing device; adding a binder into the mixed powder, and mixing with deionized water to form a plastic wet material; the plastic wet material forms a continuous strip-shaped material through an extruder, the continuous strip-shaped material is cut into 1.2 mm * 1.2 mm columnar particles through a rotary blade of cutting and rounding equipment, and the columnar particles are rounded into wet-state ball blanks with the diameter of 1.0 + / -0.1 mm through a rounding disc; and in an inert atmosphere, carrying out gradient heating on the wet ball blank to remove the binder and complete a carbon thermal reduction reaction to finally obtain the UC2-ThC2 composite fuel microspheres. The technical problems that uranium and thorium fuel microspheres are non-uniform in mixing, poor in forming quality and low in sintering performance are solved by integrating the technologies of acoustic dispersion, plastic wet material rolling and gradient sintering.

This invention relates to the field of radionuclide pollution control technology, and in particular to a method for extracting thorium using a chromotropic acid-aqueous two-phase system. The method involves adding a ligand, a salting-out agent, and an extractant to thorium-containing wastewater, mixing them thoroughly, adjusting the pH of the mixture to induce phase separation, resulting in a thorium-rich upper organic phase and a lower aqueous phase containing inorganic salts. The thorium-rich upper organic phase is then taken, and the pH is adjusted to induce phase separation again. The upper layer contains recyclable chromotropic acid and the extractant, while the lower layer is a thorium hydroxide precipitate obtained through back-extraction. The thorium hydroxide precipitate is then taken and calcined under nitrogen protection to obtain thorium oxide. The ligand is chromotropic acid; the salting-out agent includes any one or more of sulfates, halide salts, and silicates; and the extractant includes any one or more of ethanol, propanol, chloroform, acetone, and benzene. This invention has broad application prospects in the field of separation, enrichment, recovery, and determination of the long-lived, highly soluble, and biotoxic radionuclide thorium.

This invention discloses a method for producing Ac-225 mother liquor by irradiating a thorium target, belonging to the field of medical radioisotope production technology. Through steps such as designing a composite target of nano-scale thorium dioxide powder and high-purity niobium powder, medium-energy proton beam irradiation, high-temperature fluorination pretreatment, HDEHP extraction for impurity removal, TODGA extraction enrichment, and terminal aseptic filtration, efficient large-scale production of Ac-225 is achieved. This invention solves industry pain points such as dependence on reactors, poor target irradiation stability, low separation and purification efficiency, insufficient radiochemical purity of the product, and long production cycle of traditional processes. It achieves an Ac-225 recovery rate of 85.85%, a radiochemical purity of 99.99%, an endotoxin content of <0.25 EU / mL, and a production cycle shortened to 28 days. This invention offers controllable process parameters, high yield, high purity, and strong aseptic assurance, making it suitable for the large-scale and stable production of medical-grade Ac-225 mother liquor.

This invention discloses a thorium polymer spinning precursor, thorium oxide nanofibers, their preparation methods, and applications, belonging to the field of nuclear materials technology. The invention uses thorium chloride as the thorium source, acetylacetone as the ligand, and triethylamine as the dechlorination agent to prepare a thorium polymer spinning precursor. A spinning solution is prepared using the thorium polymer as the spinning precursor, methanol as the solvent, and polyethylene oxide (PEO) as the spinning aid. The thorium polymer spinning precursor fibers are obtained by electrospinning, and the precursor fibers are then heat-treated to obtain thorium oxide nanofibers. The thorium polymer spinning precursor prepared by this invention has a high thorium content and stable properties. Its spinning solution exhibits good filamentation properties, and the prepared thorium oxide fibers have uniform diameter, dense structure, and excellent flexibility. This thorium oxide nanofiber material can be used as a neutron shielding material, a breeder fuel for nuclear technology, and also as a high-temperature resistant material for preparing special ceramics.

The present disclosure relates to a method 200 for producing polytetrafluoroethylene (PTFE) thorium oxide membrane. The method 200 comprising combining metal oxide and polytetrafluoroethylene (PTFE) powder to form a first mixture and screening the first mixture to remove aggregates. The method 200 also comprising mixing a lubricant, wetting agent, and optional pigments to form a second mixture and spraying the second mixture over the first mixture. The method 200 also comprising compacting the homogeneous product into a preform and extruding and calendaring the preform to obtain a tape of desired thickness. The method 200 also comprising heating the tape formed to evaporate the lubricant and sintering the tape to fuse polytetrafluoroethylene (PTFE) and encapsulate the thorium oxide particles. The method 200 also comprising cooling the sintered tape at a controlled rate to prevent crack formation and maintain the integrity of the membrane structure.