A process for selectively separating a metallic constituent from other metals and other materials accompanying the metallic constituent in a mixture is described. The process comprises the step of providing the mixture in an aqueous solution such that the metallic constituent forms a complex anion in the solution. One or more of the other metals forms a cation or a complex cation in the solution. Another step includes contacting the solution with one or more additives to form layered double hydroxide (LDH) material in situ such that the complex anion is intercalated within interlayers of the LDH material and wherein one or more of the other metals are incorporated into the LDH material's crystal structure or matrix. Another step involves the addition of an LDH to an aqueous solution. The process involves selectively recovering the metallic constituent from the interlayer of the LDH by subjecting the LDH to a recovery treatment step(s) and as required, methods to modify the LDH to facilitate metal separation and recovery or contaminant stabilisation.

The-use of carbamides as extractants for fully or partially separating uranium(VI) from plutonium(IV) in an aqueous solution obtained by dissolving a spent nuclear fuel in nitric acid, by method of liquid-liquid extraction, without carrying out any reduction of the plutonium(IV) to plutonium(III). The invention also relates to new carbamides. Uses are the processing of spent nuclear fuels based on uranium (especially uranium oxides—UOX) or uranium and plutonium (especially mixed uranium and plutonium oxides—MOX).

Methods and systems for separation of thorium from uranium and their decay products are provided. The method comprises combining a nuclear fuel feedstock comprising thorium and uranium with a first acid to form a first solution. The first solution is contacted an ion exchange resin that is selective for thorium or uranium. The thorium or uranium is at least partially removed from the first solution by binding the thorium or uranium to the ion exchange resin thereby forming a second solution. The second solution is combined with oxalic acid to precipitate uranium or thorium from the second solution to form a precipitate. The precipitate is separated from the second solution.

Disclosed is an apparatus that is an attrition mill for grinding or comminuting ores, mine wastes, and radioactive wastes some of which may comprise metals, which may include uranium and/or cesium and/or mercury and/or thorium and/or rare earth elements. Also disclosed are processes that employ the apparatus for combined grinding and optionally leaching metals from ores and wastes. Some such methods comprise an optional step of grinding and mixing the ore or waste with a solid inorganic base with water addition or with an aqueous inorganic base, follow by a step of grinding and mixing the ore or waste with an aqueous inorganic acid with or without leaching salt addition, to solubilize the metals present in the ore or the waste. The disclosed apparatus and methods, in some embodiments, enable efficient grinding and attrition of ores substrates and mine wastes even without need for grinding media.

Disclosed is an apparatus that is an attrition mill for grinding or comminuting ores, mine wastes, and radioactive wastes some of which may comprise metals, which may include uranium and/or cesium and/or mercury and/or thorium and/or rare earth elements. Also disclosed are processes that employ the apparatus for combined grinding and optionally leaching metals from ores and wastes. Some such methods comprise an optional step of grinding and mixing the ore or waste with a solid inorganic base with water addition or with an aqueous inorganic base, follow by a step of grinding and mixing the ore or waste with an aqueous inorganic acid with or without leaching salt addition, to solubilize the metals present in the ore or the waste. The disclosed apparatus and methods, in some embodiments, enable efficient grinding and attrition of ores substrates and mine wastes even without need for grinding media.

Provided are a method and a system for processing a rare earth concentrate ore. The method comprises (1) mixing the rare earth concentrate ore and concentrated sulfuric acid, thereby obtaining a mixed slurry and a first fluorine-containing gas; (2) mixing the mixed slurry and an initiator liquid for acidolysis, thereby obtaining a clinker and a second fluorine-containing gas; (3) subjecting the clinker to leaching with water, thereby obtaining a leached slurry; (4) subjecting the leached slurry to a solid-liquid separation, thereby obtaining a filtrate and a leached slag, and recycling the leached slag to step (2) for acidolysis again.

A method for obtaining .sup.225AC from .sup.225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize .sup.226Ra .sup.225Ra and natural decay products therefrom; immobilizing the .sup.226Ra, .sup.225Ra, .sup.224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the .sup.225Ra with an aqueous sulfate solution to obtain a milking effluent that contains .sup.225AC. Also provided is a method for obtaining pure .sup.225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize .sup.225Ac, and natural decay products of .sup.225AC; immobilizing the .sup.225Ac, and natural decay products therefrom onto the stationary phase within the column .sup.226Ra, .sup.225Ra, .sup.224Ra; and eluting the column containing the .sup.225AC to obtain an effluent that contains the isotope parents.

A method for obtaining .sup.225AC from .sup.225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize .sup.226Ra .sup.225Ra and natural decay products therefrom; immobilizing the .sup.226Ra, .sup.225Ra, .sup.224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the .sup.225Ra with an aqueous sulfate solution to obtain a milking effluent that contains .sup.225AC. Also provided is a method for obtaining pure .sup.225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize .sup.225Ac, and natural decay products of .sup.225AC; immobilizing the .sup.225Ac, and natural decay products therefrom onto the stationary phase within the column .sup.226Ra, .sup.225Ra, .sup.224Ra; and eluting the column containing the .sup.225AC to obtain an effluent that contains the isotope parents.

Disclosed are a method of manufacturing a uranium target, the method including (a) a step of preparing a conjugate including a matrix and a uranium target green compact formed in the matrix; and (b) a step of performing thermo-mechanical treatment through additional heat treatment at 530° C. to 600° C. during a hot rolling pass in a process of hot-rolling the conjugate, and a method of extracting radioactive Mo-99 using the uranium target.

The invention relates to a beneficiation process for uranium ores comprising clay and carbonate minerals, the process comprising: performing a hydrocyclone step to obtain a hydrocyclone underflow fraction substantially comprising the uranium component; treating the hydrocyclone underflow fraction to effect a separation of carbonate and uranium minerals; and recovering the uranium-bearing minerals to produce a uranium concentrate.