Abstract: A method of producing uranium halides is disclosed in which chlorine gas is introduced into a liquid uranium-nickel alloy. NaCl salt is surrounding the crucible containing the liquid uranium-nickel alloy, producing a eutectic mixture of NaCl—UCl3. Upon chlorination, the metal halide dissolves in the matrix salt forming a solution. Adding the reactant metal, uranium to the nickel, the alloy is able to remain molten throughout processing. The liquid metal alloy may be removed from the salt bath, while the halogen gas continues to enter the system through the sparge until the desired composition of NaCl—UCl3—UCl4 is achieved. The method and system can be used to produce other metal halide salts such as actinide, lanthanide or transition metal halides contained in a matrix salt consisting of alkali and/or alkaline earth halides.

Abstract: A device for mixing powders by a cryogenic fluid, characterised in that it comprises: a chamber for mixing the powders, comprising a cryogenic fluid, provided with means for forming a fluidised powder bed; a chamber for supplying powders in order to allow the powders to be introduced into the mixing chamber; a chamber for supplying cryogenic fluid in order to allow the cryogenic fluid to be introduced into the mixing chamber; a system for generating vibrations in the fluidised powder bed; and a system for controlling the system for generating vibrations.

Abstract: A molten salt reactor includes a containment vessel, a reactor core, a neutron reflector spaced from the containment vessel, and liquid fuel enclosed within the core. The liquid fuel is comprised of a nuclear fission material dissolved in a molten salt. A heat exchanger is positioned external to the containment vessel. A plurality of heat transfer pipes are provided for transferring heat from the core to the heat exchanger. Each pipe has a first and a second end. The first end of each pipe is positioned within the reactor core for absorbing heat from the fuel. The heat exchanger receives the second end of each heat transfer pipe. At least two or more reactor shut down systems are provided. At least one shut down system may be a passive system and at least one or both shut down systems may be an active or a manually operated system.

Abstract: Disclosed is an exemplary method of purifying lead which includes the steps of placing lead and a fluoride salt blend in a container; forming a first fluid of molten lead at a first temperature; forming a second fluid of the molten fluoride salt blend at a second temperature higher than the first temperature; mixing the first fluid and the second fluid together; separating the two fluids; solidifying the molten fluoride salt blend at a temperature above a melting point of the lead; and removing the molten lead from the container. In certain exemplary methods the molten lead is removed from the container by decanting. In still other exemplary methods the molten salt blend is a Lewis base fluoride eutectic salt blend, and in yet other exemplary methods the molten salt blend contains sodium fluoride, lithium fluoride, and potassium fluoride.

Abstract: A process for producing a ferric containing solution by the controlled oxidation of a ferrous containing solution, said process including providing a solution containing at least ferrous ions; treating the solution with one or more inlet gases containing sulfur dioxide and oxygen in order to oxidize said ferrous ions to ferric ions, wherein the delivery rate of the sulfur dioxide gas is oxidation rate limiting; and controlling the concentration of dissolved oxygen in said solution at an optimum value.

Abstract: The proposed methods are exemplarily utilized in uranium hydrometallurgy for selective extraction of uranium out of ore by in situ or heap leaching. According to the disclosure, the methods encompass catalytic oxidation of U4+ to U6+ using a proposed oxidizing catalyst “Muhamedzhan-1”, filtration of this solution through ore, transferring hexavalent uranium, trivalent iron, and other metal ions into a production solution, extraction of uranium yielding a barren solution and re-circulation of this solution back for ore leaching. The methods essentially improve known technologies by employing “Muhamedzhan-1”, being a solution of d- and f-mixed valence metal salts (MLn, wherein M=Fe, U, Cu, Mn, and L=NO3?, SO42?Cl?, Br?, I?) and alkali metal halogenides (MX, wherein M=Na+, Na+, K+, and X=Cl?, Br?, I?) used as an oxidizing agent, with the weight ratio of MLn: 0.01-25.0%, MX: 0.01-12.5%, and solvent: balance.

Abstract: A process for producing a ferric containing solution by the controlled oxidation of a ferrous containing solution, said process including providing a solution containing at least ferrous ions; treating the solution with one or more inlet gases containing sulfur dioxide and oxygen in order to oxidize said ferrous ions to ferric ions, wherein the delivery rate of the sulfur dioxide gas is oxidation rate limiting; and controlling the concentration of dissolved oxygen in said solution at an optimum value.

Abstract: A method for producing metal powder is provided the comprising supplying a molten bath containing a reducing agent, contacting a metal oxide with the molten bath for a time and at a temperature sufficient to reduce the metal in the metal oxide to elemental metal and produce free oxygen; and isolating the elemental metal from the molten bath.

Abstract: The invention relates to the confinement of an alloy formed of actinide transuranic radioactive wastes and beryllium metal within a neutron moderating and reflecting apparatus to cause accelerated destruction (burning) of the actinide wastes. Waste actinides, including plutonium, neptunium, americium, and curium, emit alpha particles by radioactive decay. The alpha particles are converted into neutrons by the beryllium through an alpha-neutron (alpha, n) reaction. The neutrons developed by the alpha, n reaction are moderated by a surrounding layer of graphite, which allows the slowed neutrons to cause additional fission or decay events within the waste actinide alloy. This process is passive because the alpha particles that initiate the actinide burning are an intrinsic physical property of the actinides.

Abstract: An improved process and composition for the extraction of metal from a metal-laden ore, soil or rock is provided. A liquid, three-component aqueous lixiviant comprises water, an alkali metal salt and a low pH acidic composition. A four-component aqueous lixiviant comprises water, a low pH acidic composition, an alkali metal salt and an acid having a pH value less than 2. Both lixiviant compositions are efficient for extracting metal into a pregnant liquid solution. The pregnant solution is treated by known conventional means, such as filtration, centrifuging or electrolysis to remove the extracted metals. The three-component and four-component aqueous lixiviants of the present invention are non-toxic, meaning, not an irritant or deleterious to humans or the environment and perform, as well as, or better than known toxic cyanide lixiviants.

Abstract: The present invention relates to the recovery of base metals, in particular but not exclusively copper, via integrated hydrometallurgical and pyrometallurgical processing of base-metal sulphides, in particular but not exclusively iron-containing base-metal sulphides.

Abstract: The invention provides a process for reducing to metallic form oxides of uranium, or metals more noble than uranium, present in spent nuclear fuel comprising a mixture of metal oxides, the process comprising cathodically electrolysing the oxide in the presence of a molten salt electrolyte, the potential of the cathode being controlled so as to favour oxygen ionisation over deposition of the metal from the cations present in the molten salt, and to ensure than reduction of metals other than uranium or metals more noble than uranium does not occur. The invention allows for the reduction of uranium or metals more than uranium present in spent nuclear fuel comprising mixed metal oxides to a metallic form by the use of a single electrochemical process, with oxygen being produced as the only by-product.

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: This invention provides improved production, continuous or batch, especially of metals which have been produced by versions of the Kroll and Ames processses. This list includes titanium, zirconium, hafnium, vanadium, niobium, tantalum, rhenium, molybdenum, tungsten, and uranium. It also offers a process for growing particular shapes of metallic crystals, e.g., needlelike. This invention is intended to be less expensive to operate and to provide a superior product than from Kroll batch processing, as often used: For the continuous metal production, circulating molten salt supports two principal reaction stages, which together allow continuous metal production: Titanium powder production with one possible set of reactants may be used as an example for the group of metals listed: In Stage 1 a pumped solution of titanium ions (Ti++) dissolved in molten salt (e.g., MgCl2—KCl) flows onto, then down beside, molten magnesium that floats on molten salt below.

Abstract: A fast quench reaction includes a reactor chamber having a high temperature heating means such as a plasma torch at its inlet and a means of rapidly expanding a reactant stream, such as a restrictive convergent-divergent nozzle at its outlet end. Metal halide reactants are injected into the reactor chamber. Reducing gas is added at different stages in the process to form a desired end product and prevent back reactions. The resulting heated gaseous stream is then rapidly cooled by expansion of the gaseous stream.

Abstract: A process for facilitating the removal of impurities e.g. radionuclides, such as uranium and thorium, and/or one or more of their radionuclide daughters, from titaniferous material includes contacting the titaniferous material with one or more reagents at an elevated temperature selected to enhance the accessibility of at least one of the radionuclide daughters in the titaniferous material. The reagent(s) may be a glass forming reagent and is selected to form a phase at the elevated temperature which disperses onto the surfaces of the titaniferous material and incorporates the radionuclides and one or more radionuclide daughter. The titaniferous material may be, e.g., ilmenite, reduced ilmenite, altered ilmenite or synthetic rutile.

Abstract: A process for preparing uranium metal or alloy thereof suitable for use in a metal-based uranium enrichment plant or other use requiring a superdense metal comprising providing a molten metal bath containing the alloy metal and feeding uranium oxide and a reactive metal reductant into the molten metal bath so that the oxide is reduced to elemental uranium and alloying the thus formed uranium with the bath metal.

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: A process for facilitating the removal of impurities e.g. radionuclides, such as uranium and thorium, and/or one or more of their radionuclide daughters, from titaniferous material includes contacting the titaniferous material with one or more reagents at an elevated temperature selected to enhance the accessibility of at least one of the radionuclide daughters in the titaniferous material. The reagent(s) may be a glass forming reagent and is selected to form a phase at the elevated temperature which disperses onto the surfaces of the titaniferous material and incorporates the radionuclides and one or more radionuclide daughters. The titaniferous material may be, e.g., ilmenite, reduced ilmenite, altered ilmenite or synthetic rutile.

Abstract: A method is described for forming metallic uranium, or a uranium alloy, from uranium oxide in a manner which substantially eliminates the formation of uranium-containing wastes. A source of uranium dioxide is first provided, for example, by reducing uranium trioxide (UO.sub.3), or any other substantially stable uranium oxide, to form the uranium dioxide (UO.sub.2). This uranium dioxide is then chlorinated to form uranium tetrachloride (UCl.sub.4), and the uranium tetrachloride is then reduced to metallic uranium by reacting the uranium chloride with a metal which will form the chloride of the metal. This last step may be carried out in the presence of another metal capable of forming one or more alloys with metallic uranium to thereby lower the melting point of the reduced uranium product.

Abstract: A process for converting PuO.sub.2 and UO.sub.2 present in an electrorefiner to the chlorides, by contacting the PuO.sub.2 and UO.sub.2 with Li metal in the presence of an alkali metal chloride salt substantially free of rare earth and actinide chlorides for a time and at a temperature sufficient to convert the UO.sub.2 and PuO.sub.2 to metals while converting Li metal to Li.sub.2 O. Li.sub.2 O is removed either by reducing with rare earth metals or by providing an oxygen electrode for transporting O.sub.2 out of the electrorefiner and a cathode, and thereafter applying an emf to the electrorefiner electrodes sufficient to cause the Li.sub.2 O to disassociate to O.sub.2 and Li metal but insufficient to decompose the alkali metal chloride salt. The U and Pu and excess lithium are then converted to chlorides by reaction with CdCl.sub.2.

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: In the pyrochemical reduction of uranium dioxide or other actinide metal oxides by reaction with magnesium, magnesium oxide byproduct is produced. The use of a salt flux comprising magnesium chloride and a rare earth element trichloride such as neodymium chloride is disclosed. The neodymium chloride reacts with magnesium oxide to form magnesium chloride and neodymium oxychloride. The resulting magnesium chloride-neodymium oxychloride salt mixture can readily be subjected to electrolysis to regenerate magnesium and neodymium chloride for reuse in the pyrochemical reduction process. Other uses of the magnesium chloride-neodymium chloride salt flux are also proposed.

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: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a U-Fe alloy containing not less than about 84% by weight uranium at a temperature in the range of from about 800.degree. C. to about 850.degree. C. to produce additional uranium metal which dissolves in the U-Fe alloy raising the uranium concentration and having transuranium actinide metals and rare earth fission product metals and the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel.

Abstract: A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800.degree. C. to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein.

Abstract: Actinides metals are recovered from spent nuclear fuel oxides containing fission products by a pyrochemical process. The process comprises, in part, electrorefining the metal complex from an anode by electrolytically oxidizing actinides into a salt and then electrodepositing actinides onto a cathode to form an actinide metal deposit. The actinide metal deposit is then melted to separate the salts and the actinide metals. The separated salt is recycled into an electrorefiner and the actinide metals are recovered and then transferred to a fuel fabrication system.

Abstract: A process for converting uranium oxide to uranium metal wherein uranium oxide is reduced with a reducing agent, and the uranium metal product is recovered by dissolving the excess reducing agent and by-products in a dissolution aid.

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.