A reactor (1) for hydrolysis of uranium hexafluoride comprises a tubular injector (9) comprising first (11), second (13) and third (15) concentric fluid circulation ducts intended to be connected respectively with a source of UF.sub.6, a source of inert gas and a source of water vapor. The tubular injector (9) is obtained by additive manufacturing.

A reactor (1) for hydrolysis of uranium hexafluoride comprises a tubular injector (9) comprising first (11), second (13) and third (15) concentric fluid circulation ducts intended to be connected respectively with a source of UF.sub.6, a source of inert gas and a source of water vapor. The tubular injector (9) is obtained by additive manufacturing.

A nuclear fuel powder production plant comprises a conversion installation (2) for the conversion of uranium hexafluoride (UF.sub.6) into uranium dioxide (UO.sub.2) having a hydrolysis reactor (4) for the conversion of UF.sub.6 into uranium oxyfluoride powder (UO.sub.2F2) and a pyrohydrolysis furnace (6) for converting the UO.sub.2F2 powder into UO.sub.2 powder. The nuclear fuel powder production plant also includes a packaging unit (20) for the UO.sub.2 powder comprising a filling station (22) having a chamber (26) for receiving a container (24) to be filled, a filling duct (28) supplied from the furnace (6) and a suction system (32) comprising a suction ring (34) disposed at the outlet (30) of the filling duct (28) for sucking an annular air flow (A) around a stream (P) of UO.sub.2 powder falling from the outlet (30) from the filling duct (28) into the container (24).

A nuclear fuel powder production plant comprises a conversion installation (2) for the conversion of uranium hexafluoride (UF.sub.6) into uranium dioxide (UO.sub.2) having a hydrolysis reactor (4) for the conversion of UF.sub.6 into uranium oxyfluoride powder (UO.sub.2F2) and a pyrohydrolysis furnace (6) for converting the UO.sub.2F2 powder into UO.sub.2 powder. The nuclear fuel powder production plant also includes a packaging unit (20) for the UO.sub.2 powder comprising a filling station (22) having a chamber (26) for receiving a container (24) to be filled, a filling duct (28) supplied from the furnace (6) and a suction system (32) comprising a suction ring (34) disposed at the outlet (30) of the filling duct (28) for sucking an annular air flow (A) around a stream (P) of UO.sub.2 powder falling from the outlet (30) from the filling duct (28) into the container (24).

A novel semi-batch process for deconverting high assay low enriched uranium (HALEU) from its uranium hexafluoride state to uranium dioxide and other chemical states useful as feeds for nuclear fuel in a nuclear reactor is provided. The semi-batch process enables the use of equipment that is small enough, and production rates that are low enough, to meet nuclear criticality safety restraints for HALEU, while enabling the safe, dependable, and economical production of HALEU feed for nuclear fuel at a nominal capacity of up to about 20 MTU (metric tons of uranium metal) per year per deconversion reactor.

Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.

A method for electrochemical extraction of uranium from seawater using an oxygen vacancy (OV)-containing metal oxide includes the following steps: adding glycerin to a solution of indium nitrate in isopropanol, transferring a resulting mixture to a reactor, and conducting reaction to obtain a spherical indium hydroxide solid; dissolving the solid in deionized water, transferring a resulting solution to the reactor, and conducting reaction to obtain a flaky indium hydroxide solid; calcining the solid to obtain calcined OV-containing In.sub.2O.sub.3-x; adding the In.sub.2O.sub.3-x to ethanol, and adding a membrane solution; coating a resulting solution uniformly on carbon paper, and naturally drying the carbon paper; clamping dried carbon paper with a gold electrode for being used as a working electrode for a three-electrode system; and adding simulated seawater to an electrolytic cell, placing the three-electrode system in the simulated seawater, and stirring the simulated seawater for electrolysis to extract uranium from the seawater.

A method for electrochemical extraction of uranium from seawater using an oxygen vacancy (OV)-containing metal oxide includes the following steps: adding glycerin to a solution of indium nitrate in isopropanol, transferring a resulting mixture to a reactor, and conducting reaction to obtain a spherical indium hydroxide solid; dissolving the solid in deionized water, transferring a resulting solution to the reactor, and conducting reaction to obtain a flaky indium hydroxide solid; calcining the solid to obtain calcined OV-containing In.sub.2O.sub.3-x; adding the In.sub.2O.sub.3-x; to ethanol, and adding a membrane solution; coating a resulting solution uniformly on carbon paper, and naturally drying the carbon paper; clamping dried carbon paper with a gold electrode for being used as a working electrode for a three-electrode system; and adding simulated seawater to an electrolytic cell, placing the three-electrode system in the simulated seawater, and stirring the simulated seawater for electrolysis to extract uranium from the seawater.

Described are methods for the recovery of uranium from uranium hexafluoride dissolved directly into ionic liquids.