A process for recovering copper, uranium and one or more precious metals from an ore material, including: a. forming a heap of the ore material; b. subjecting the heap of the ore material to an acidic heap leach using an iron containing acidic leach solution in the presence of an oxygen containing gas, and producing a pregnant leach solution and a ripios; c. subjecting the ripios to flotation to produce a copper containing ripios concentrate and tailings; and d. subjecting the ripios concentrate to a smelting process to produce a smelted copper product. e. recovering copper and uranium from the pregnant leach solution.

A process for recovering copper, uranium and one or more precious metals from an ore material, including: a. forming a heap of the ore material; b. subjecting the heap of the ore material to an acidic heap leach using an iron containing acidic leach solution in the presence of an oxygen containing gas, and producing a pregnant leach solution and a ripios; c. subjecting the ripios to flotation to produce a copper containing ripios concentrate and tailings; and d. subjecting the ripios concentrate to a smelting process to produce a smelted copper product. e. recovering copper and uranium from the pregnant leach solution.

Siderocalin-metal chelator combinations that bind metallic radioisotopes used in nuclear medicine with high affinity are described. The high affinity siderocalin-metal chelator combinations include a number of chelator backbone arrangements with functional groups that coordinate with metals. The siderocalin-metal chelator combinations can be used to deliver radionuclides for imaging and therapeutic purposes.

Siderocalin-metal chelator combinations that bind metallic radioisotopes used in nuclear medicine with high affinity are described. The high affinity siderocalin-metal chelator combinations include a number of chelator backbone arrangements with functional groups that coordinate with metals. The siderocalin-metal chelator combinations can be used to deliver radionuclides for imaging and therapeutic purposes.

According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

The invention provides methods, compositions, and apparatuses for preventing the formation of scale in heap leach process solution distribution systems comprised of piping, spray nozzles, or emitter tubes. Solution distribution system components often become fouled by scale because of local hot spots more prone to form scale than other locations along the systems length. Positioning sensors that detect periods of high temperature stress and adjusting scale control reagent dosage to send the right amount to inhibit hot spot deposition allows for the control of scale without using wasteful excessive amounts of scale control reagents. This can vastly improve scale control performance under high temperature stress conditions while minimizing scale control reagent waste under less severe stress conditions to reduce the total operating cost of running heap leach mining operations which depend upon well-functioning solution distribution systems.

The present invention relates to a method for removing radioactive element thorium in a rare earth mineral, comprising: mixing the rare earth mineral with selenium dioxide in water, reacting radioactive element thorium with selenium dioxide by hydrothermal method, cooling to form a crystal, and separating the crystal to remove the radioactive element thorium. In the invention, tetravalent element thorium is selectively bound to inorganic ligand selenium dioxide in a hydrothermal environment to form a crystal, thereby achieving removal of radioactive element thorium. The method has high crystallization rate and high decontamination efficiency, and removes thorium from trivalent lanthanide element by crystallization solidification under a uniform reaction condition. Compared to a conventional industrial method for thorium separation, the method has low energy consumption and high separation ratio, enables one-step solidification separation, and effectively avoids the disadvantages of redundant separation operations and a large amount of organic and radioactive liquid wastes.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Novel dissymmetric N,N-dialkylamides which meet the following formula (I): ##STR00001##
where R represents a linear or branched alkyl group at C.sub.8 to C.sub.15. A method for synthesizing these N,N-dialkylamides, and to the uses of same as extractants, alone or in admixture, in order to extract uranium and/or plutonium from an aqueous acid solution, or to totally or separate uranium from plutonium from an aqueous acid solution and, in particular, an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid. Further, a method for processing an aqueous solution resulting from the dissolution of a spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any plutonium reduction operation, and in which one of the aforementioned N,N-dialkylamides or a mixture of same is used as extractant. Applications for the method include the processing of spent nuclear fuels, in particular comprising uranium (e.g. UOX) or uranium and plutonium (e.g. MOX).