Abstract: A method for the recovery of uranium from pregnant liquor solutions that comprise levels of chloride of 5 to 80 g/L by using an amino phosphonic functionalized resin. The method includes providing an amino phosphonic functionalized resin; providing a pregnant liquor solution comprising and uranium; passining the pregnant liquor solution over the amino phosphonic functionalized resin to separate the uranium from the pregnant liquor solution; and eluting the uranium.

Abstract: The present invention relates to a treatment method of spent uranium catalyst, and more specifically, to a method which can considerably reduce the volume of the spent uranium catalyst to be disposed of and simultaneously minimize secondary wastes that can be generated during the process of treating the spent uranium catalyst.

Abstract: The main subject-matter of the present invention is a process for the dissolution of at least one element chosen from niobium and tantalum and at least one other element chosen from uranium and the rare earth elements, advantageously for the dissolution of niobium, tantalum, uranium and rare earth elements, present in an ore or an ore concentrate. Said process comprises: the roasting of a material, comprising said elements, which material is mixed, dry or/in the presence of water, with an acid roasting agent in order to obtain a calcine; said material consisting of said ore or concentrate or having been obtained from said ore or said concentrate and said acid roasting agent providing for roasting in a sulphate medium; and the dissolution in an aqueous solution of the calcine obtained in order to obtain a slurry, the liquid fraction of which includes iron, in the ferric state, at a concentration of at least 50 g/l, advantageously of at least 70 g/l and very advantageously of at least 120 g/l.

Abstract: A highly efficient uranium leaching method using ultrasound is disclosed. The uranium leaching method includes preparing black slate powder containing uranium by pulverizing black slate containing uranium, placing the black slate powder and water in a reaction bath, and performing uranium leaching by adding and mixing sulfuric acid and an oxidant with the black slate powder and water to prepare a mixture in the reaction bath while applying ultrasound to the reaction bath. In this method, uranium leaching efficiency can be maximized by adding sulfuric acid to the uranium ore while applying ultrasound thereto.

Abstract: A method for the selective recovery of uranium from a sulphate-based acidic aqueous solution of uranium containing iron and other metals by means of solvent extraction, in which the extractant used in the organic extraction solution is bis(2-ethylhexyl) phosphate and a liquid branched trialkyl phosphine oxide is the modifying agent. It is typical of the method that the uranium concentration in the feed solution is less than 50 mg/l and a reducing agent is introduced into the aqueous and/or extraction solution to prevent the permanent oxidation of iron to trivalent. In the method the majority of the extraction solution is circulated in a circuit consisting of the extraction stage and the storage tank and only a small part of the uranium-loaded extraction solution is routed to scrubbing and stripping.

Abstract: A method with which uranium from a natural uranium concentrate may be purified, including a) extracting the uranium present as uranyl nitrate in an aqueous phase A1 resulting from the dissolution of the natural uranium concentrate in nitric acid, by means of an organic phase which contains an extractant in an organic diluent; b) washing the organic phase obtained at the end of step a), with an aqueous phase A2; and c) stripping the uranyl nitrate of the organic phase obtained at the end of step b), by circulating this organic phase in an apparatus, as a counter current against an aqueous phase A3. The extractant is an N,N-dialkylamide and the ratio between the flow rate at which the organic phase obtained at the end of step b) and the aqueous phase A3 circulate in the apparatus where step c) occurs, is greater than 1.

Abstract: Compositions comprising a tripeptide having the sequence XC1C2; wherein X is any amino acid such that XC1C2 is capable of binding a metal in a square planar orientation or square pyramidal orientation or both; and wherein C1 and C2 are the same or different; and wherein C1 and C2 individually are chosen from a cysteine and a cysteine-like nonnatural amino acid, as well as metal-XC1C2 complexes and methods for forming such complexes.

Abstract: The present invention is directed to a new more environmentally friendly method for the recovery of uranium from pregnant liquor solutions that comprise high levels of chloride by using an amino phosphonic functionalized resin.

Abstract: A process for recovering copper from heap leach residues, the process comprising treating heap leach residues to provide treated heap leach residues providing improved permeability of a heap of the treated heap leach residues, and leaching the heap of the treated heap leach residues with a leaching solution. Treating the heap leach residues includes: a) blending the heap leach residues with additional material to provide a blend; or b) agglomerating the heap leach residues; or c) both blending the heap leach residues with additional material and agglomerating.

Abstract: Embodiments of a method and a system for recovering a metal, such as uranium, from a metal-containing material are disclosed. The metal-containing material is exposed to an extractant containing a liquid or supercritical-fluid solvent and an acid-base complex including an oxidizing agent and a complexing agent. Batches of the metal-containing material are moved through a series of stations while the extractant is moved through the stations in the opposite direction. After the extraction step, the metal is separated from the solvent, the complexing agent and/or other metals by exposing the extract to a stripping agent in a countercurrent stripping column. The complexing agent and the solvent exit the column and are separated from each other by reducing the pressure. The recovered complexing agent is recharged with fresh oxidizing agent and recombined with fresh or recovered solvent to form a recovered extractant, which is distributed through the extraction stations.

Abstract: The invention provides a series of techniques for processing uranium containing feed materials such as uranium ores, reprocessed uranium, uranium containing residues and uranium containing spent fuel. The processes described involve fluorination of uranium containing material, separation of the uranium containing material from other materials based on ionization thereof with the non-ionized fluorine containing material being recycled. Metallic uranium and/or plutonium and/or fission products may result. The technique offers advantages in terms of the range of materials which can be reprocessed and a reduction in the number of complexity of stages which are involved in the process.

Abstract: Embodiments of a method and a system for recovering a metal, such as uranium, from a metal-containing material are disclosed. The metal-containing material is exposed to an extractant containing a liquid or supercritical-fluid solvent and an acid-base complex including an oxidizing agent and a complexing agent. Batches of the metal-containing material are moved through a series of stations while the extractant is moved through the stations in the opposite direction. After the extraction step, the metal is separated from the solvent, the complexing agent and/or other metals by exposing the extract to a stripping agent in a countercurrent stripping column. The complexing agent and the solvent exit the column and are separated from each other by reducing the pressure. The recovered complexing agent is recharged with fresh oxidizing agent and recombined with fresh or recovered solvent to form a recovered extractant, which is distributed through the extraction stations.

Abstract: A treatment apparatus (10) includes a liquid reactant metal containment vessel (11) for containing a first liquid reactant metal and isolating the reactant metal from the atmosphere. A release chamber (14) is adapted to receive the first liquid reactant metal from the containment vessel (11) and a submerging arrangement (21) is adapted to dunk or submerge a container (46) of feed material into the liquid reactant metal and move the container to a release location within the release chamber (14). Relatively light materials rising from the submerged container (46), including unreacted feed material, intermediate reaction products, and perhaps final reaction products collect in a collection area (60) having an upper surface defined by an upper surface of the release chamber (14).

Abstract: Improved methods for the extraction or dissolution of metals, metalloids or their oxides, especially lanthanides, actinides, uranium or their oxides, into supercritical solvents containing an extractant are disclosed. The disclosed embodiments specifically include enhancing the extraction or dissolution efficiency with ultrasound. The present methods allow the direct, efficient dissolution of UO2 or other uranium oxides without generating any waste stream or by-products.

Abstract: A metallothermy method includes continuously withdrawing an ingot of a metal product such as uranium or a uranium alloy as it is formed from an oxide or salt of the metal. The method employs upper and lower communicating crucibles. The upper crucible contains a layer of reducing medium floating on a solvent medium. The metal oxide or metal salt is reduced as it is introduced into the layer reducing medium to form metal particles and slag. The settling metal is melted by further induction heating, collected in the lower crucible and withdrawn. The slag is absorbed by the solvent medium which is regenerated with the use of electrolysis.

Abstract: A method of recovering contaminating or valuable components from a solid feed material (10), includes feeding the material (10) into an optional grinder as a pretreatment (12), then into a heated melter (14) along with a material (16) that provides fluorine, to provide a molten or semi-molten material, where the molten material is then reacted with water or an acid solution (22) in vessel (20), to form a dissolved molten or semi-molten salt in solution, which can be passed to extractor (26) or the like and provide a concentrated stream of the valuable or contaminating components (30).

Abstract: A method and apparatus producing halogenated products from metal halide feeds. In one embodiment, uranium hexafluoride is treated by separating fluorine from the metal of the uranium hexafluoride. Uranium hexafluoride is introduced into a molten metal bath under conditions whereby the uranium hexafluoride in the presence of hydrogen and oxygen can react to form a uranium dioxide and anhydrous hydrogen fluoride. The anhydrous hydrogen fluoride is removed from the molten metal bath as a gas stream and the uranium dioxide is discharged as a ceramic phase.

Abstract: Finely powdered urania scrap materials are subjected to sintering conditions (greater than 1600.degree. C.) in a hydrogen atmosphere for about 4 to 8 hours in order to remove impurities (such as Si, Fe, Ni, Sn, Cu, Na and Pb). The process upgrades the quality of the urania powder to where it can be used directly as clean scrap makeup, thereby avoiding expensive decontamination and recovery steps like solvent extraction. The novelty of the process is in the use of sintering conditions (greater than 1600.degree. C.) in a hydrogen atmosphere on finely divided powder to decontaminate urania materials.

Abstract: Uranium chloride is reacted with either magnesium, sodium or calcium in the presence of a molten salt comprising light metal chlorides including lithium chloride. The temperature is maintained below the melting point of uranium. The magnesium may be in the form of magnesium-cadmium alloy, the temperature being maintained below the temperature at which magnesium and cadmium vaporize. The components of the molten salt may be first fused together so as to form the molten salt eutectic. Subsequently after separation of the uranium, products of the reaction may be recovered and recycled.

Abstract: A method of converting uranium dioxide into a metallic uranium lump is provided The method comprises mixing a reducing agent comprised of metallic calcium, a slag solvent comprised of calcium chloride and a eutectic comprised of at least one member selected from the group consisting of barium chloride, lithium chloride, sodium chloride and potassium chloride into uranium dioxide to obtain a mixture, heating the mixture at a temperature not below the melting point of metallic uranium, separating resulting molten metallic uranium from a resulting molten slag based on a difference in specific gravity, and cooling the molten metallic uranium to produce metallic uranium as a solid lump.

Abstract: Apparatus for separating molten salt by-product phase from molten uranium or molten uranium alloy product phase using a barrier which passes molten salt but retains molten uranium or molten uranium alloy. The operation of the barrier relies on the differences in the physical behavior of said molten salt from the behavior of said molten uranium or molten uranium alloy as they interact with each other and with said barrier.

Abstract: A process for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride.

Abstract: An electrolytic process for making uranium from uranium oxide using Cl.sub.2 anode product from an electrolytic cell to react with UO.sub.2 to form uranium chlorides. The chlorides are used in low concentrations in a melt comprising fluorides and chlorides of potassium, sodium and barium in the electrolytic cell. The electrolysis produces Cl.sub.2 at the anode that reacts with UO.sub.2 in the feed reactor to form soluble UCl.sub.4, available for a continuous process in the electrolytic cell, rather than having insoluble UO.sub.2 fouling the cell.