11results about "Uranium fluorides" patented technology

Provided is a process which allows uranium and molybdenum fluorides to be efficiently separated, said process comprising a step of providing a mixture containing MoF6 and UF6; a step of reducing the UF6 to UF5 in the gas phase or in a liquid phase; and a step of separating the UF5 and the MoF6 or a conversion product thereof which may be obtained by further converting the molybdenum fluoride to another molybdenum compound. In a further aspect, a process for the fluorination of metals or semimetals is provided.

Described herein are methods for recovering uranium tetrafluoride (UF4) from uranium hexafluoride (UF6) by directly dissolving UF6 in ionic liquids and recovering UF4, which can be processed to obtain UO2 (s) or uranium metal.

A uranium tetrafluoride preparation system based on a reducing hydrofluorination reaction includes a gas supply mechanism, a three-stage fluidized bed mechanism, and a tail gas treatment mechanism. The gas supply mechanism includes an ammonium fluoride heating tank and a gas separation tank. The gas separation tank has a mixed gas inlet, an ammonia outlet A, and a hydrogen fluoride outlet at its top. The mixed gas inlet of the gas separation tank is connected to the mixed gas outlet of the ammonium fluoride heating tank. The three-stage fluidized bed mechanism includes a fluidized bed A, an intermediate container X, a fluidized bed B, an intermediate container Y, and a fluidized bed C. The tail gas treatment mechanism includes a condenser, a crystallization tank, a plate filter, a microwave dryer, and a scrubbing tower. This invention uses a three-stage fluidized bed system to reduce and hydrofluorinate uranium oxide to prepare uranium tetrafluoride. Compared with the existing "uranium purification-uranium conversion" process, it enables continuous production control and significantly shortens the process flow.

Method and system for detecting a uranium hexafluoride leak. The detection method allows for the detection of the presence of uranium hexafluoride (UF6) in a gas stream (G). The detection method comprises humidifying the gas stream by circulating the gas stream (G) through contact with a copolymer fluoropolymer based on sulfonate tetrafluoroethylene, in particular Nafion, and then detecting the presence of hydrogen fluoride (HF) in the gas stream (G) using a sensor. Figure for the abstract: Figure 1

The invention provides a method for preparing nuclear pure grade uranium hexafluoride, which comprises the following steps: (1) adding fluoride containing molybdenum, tungsten, vanadium, titanium, chromium and antimony and crude uranium hexafluoride of hydrogen fluoride impurities into a distillation kettle, and carrying out pressurized distillation to obtain a gaseous mixture; (2) introducing the gaseous mixture obtained in the step (1) into a calcium fluoride adsorption column, and removing hydrogen fluoride in the mixture through selective adsorption of calcium fluoride; and (3) carrying out single-tower pressurized distillation on the gaseous mixture treated in the step (2) to obtain nuclear pure grade uranium hexafluoride. The method solves the problems of low uranium hexafluoride purity, high energy consumption and high cost of the existing uranium purification conversion technology in the conversion technology of the high-impurity-content natural uranium concentrate, realizes cost reduction and efficiency improvement of uranium hexafluoride purification on the premise of ensuring that uranium hexafluoride reaches the nuclear purity grade standard, and has a wide application prospect. Rapid popularization of a dry uranium purification and conversion process is boosted, and the technical level of uranium purification and conversion in China is further improved.

The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.

The present invention relates to the use of natural uranium hexafluoride UF6 as a propellant in an electric propulsion system.

The invention provides a device and method for preparing uranium hexafluoride based on uranium-containing molten salt, the uranium-containing molten salt contains uranium dioxide and / or triuranium octaoxide, and the device comprises a reaction cavity used for containing the uranium-containing molten salt; the gas inlet is communicated with the reaction cavity and is used for introducing fluorinated gas containing chlorine trifluoride into the reaction cavity, the chlorine trifluoride is subjected to fluorination reaction with each of uranium dioxide and / or triuranium octaoxide, and the fluorination reaction generates reaction gas containing uranium hexafluoride; the gas outlet is communicated with the reaction cavity and is used for discharging reaction gas; and the separation unit is used for separating uranium hexafluoride from the reaction gas.

The present disclosure provides systems and methods for fast molten salt reactor fuel-salt preparation. In one implementation, the method may comprise providing fuel assemblies having fuel pellets, removing the fuel pellets and spent fuel constituents from the fuel assemblies, granulating the removed fuel pellets or process feed to a chlorination process, processing the granular spent fuel salt into chloride salt by ultimate reduction and chlorination of the uranium and associated fuel constituents chloride salt solution, enriching the granular spent fuel salt, chlorinating the enriched granular spent fuel salt to yield molten chloride salt fuel, analyzing, adjusting, and certifying the molten chloride salt fuel for end use in a molten salt reactor, pumping the molten chloride salt fuel and cooling the molten chloride salt fuel, and milling the solidified molten chloride salt fuel to predetermined specifications.

The application provides a device and a method for preparing uranium hexafluoride based on a uranium-containing molten salt, the uranium-containing molten salt containing uranium dioxide and / or triuranium octaoxide, the device comprising: a reaction cavity for containing the uranium-containing molten salt; a gas inlet in communication with the reaction cavity, for introducing a fluorination gas containing chlorotrifluoride into the reaction cavity, the chlorotrifluoride being fluorinated with each of the uranium dioxide and / or the triuranium octaoxide, the fluorination reaction generating a reaction gas comprising uranium hexafluoride; a gas outlet in communication with the reaction cavity, for discharging the reaction gas; and a separation unit for separating the uranium hexafluoride from the reaction gas.

The invention belongs to the technical field of uranium concentration, and particularly relates to a device for purifying light impurities. The device comprises a membrane component mounted before a material enters a material receiving container; the membrane component comprises a shell and separation membrane filaments arranged in the shell; the separation membrane wire is used for separating UF6 and light impurities; an inlet of the membrane component is connected with the material, a product outlet is connected with a material receiving container, and an impurity outlet is connected with an impurity collecting device; the impurity collecting device is used for purifying tail gas. The process flow for purifying the light impurities in the product is simplified, the workload is reduced, the working efficiency is improved, continuous, stable and efficient separation of the materials and the light impurities in the uranium concentration production product is achieved, and a foundation is laid for follow-up optimization of the layout of a material supply and taking plant, reduction of the engineering construction cost and the operation cost and improvement of the system automation level.