Abstract: A method for recycling molten salt from electrorefining processes, the method having the steps of collecting actinide metal using a first plurality of cathodes from an electrolyte bath, collecting rare earths metal using a second plurality of cathodes from the electrolyte bath, inserting the collected actinide metal and uranium into the bath, and chlorinating the inserted actinide metal and uranium. Also provided is a system for recycling molten salt, the system having a vessel adapted to receive and heat electrolyte salt, a first plurality of cathodes adapted to be removably inserted into the vessel, a second plurality of cathodes adapted to be removably inserted into the vessel, an anode positioned within the vessel so as to be coaxially aligned with the vessel, and a vehicle for inserting uranium into the salt.

Abstract: A method for processing a coolant includes filtering a coolant using a first filtration system to generate a first filtered material, and filtering the filtered coolant using a second filtration system to generate a second filtered material. The second filtration system is different from the first filtration system. The first filtered material is transferred to a first waste treatment container and converted to a first waste product for permanent disposal, and the second waste product is transferred to a second waste treatment container and converted to a second waste product for permanent disposal.

Abstract: A system providing selective spin modification and reaction in an electrolytic cell. An electrolytic cell is coupled to a magnet that provides a level-splitting magnetic field in a region of electrolyte adjacent to a working electrode, thus establishing a spin resonance for an unpaired electron associated with a chemical species in the region of electrolyte adjacent to the working electrode. The working electrode carries an excitation current produced by a switching source or amplifier. The excitation current produces an alternating magnetic field adjacent to the working electrode that alters the spin state population density for the unpaired electron associated with a chemical species within the electrolyte, thereby enhancing or inhibiting the reaction of the chemical species during subsequent electrolysis.

Abstract: A method for measuring the uranium concentration of an aqueous solution including the following successive steps: a) electrochemical reduction towards valence IV, of the uranium present in the aqueous solution with a valence greater than IV, this reduction being implemented at pH<2 and by passing an electrical current in the solution; b) measurement of the absorbance of the solution obtained on completion of step a) at a chosen wavelength between 640 and 660 nm, and preferably 652 nm; and c) determination of the uranium concentration of the aqueous solution by deduction of the uranium concentration of valence (IV) present in the aqueous solution obtained on completion of step a) from measurement of the absorbance obtained in step b).

Abstract: A process for the extraction of uranium compounds from wet-process phosphoric acid includes lowering the iron concentration of the wet-process phosphoric acid and reducing the valency of any remaining ferric iron in the wet-process phosphoric acid to ferrous iron, and then extracting uranium compounds from the wet-process phosphoric acid. The process can include separating a side stream from a feed stream of wet-process phosphoric acid, wherein the side stream has a greater concentration of the uranium compounds than the feed stream by filtration. Extracting uranium compounds from the wet-process phosphoric acid can be by ion exchange process or by solvent extraction.

Abstract: Disclosed herein is a method of preparing uranium metal by electrorefining uranium metal, comprising: applying a predetermined current to an anode electrode included in an anode basket receiving fuel segments made of uranium metal and a cathode electrode of carbon material; electrodepositing uranium on the cathode electrode in accordance with the reaction initiated by the applied current; and collecting the electrodeposited uranium by self-weight. An apparatus for electrorefining uranium metal used in the method according to the present invention, comprises: an anode basket (6) receiving fuel segments made of uranium metal and comprising an anode electrode; and a reactor including a cathode electrode (5) made of carbon material and a uranium collector (10) therein.

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: A system providing selective spin modification and reaction in an electrolytic cell. An electrolytic cell is coupled to a magnet that provides a level-splitting magnetic field in a region of electrolyte adjacent to a working electrode, thus establishing a spin resonance for an unpaired electron associated with a chemical species in the region of electrolyte adjacent to the working electrode. The working electrode carries an excitation current produced by a switching source or amplifier. The excitation current produces an alternating magnetic field adjacent to the working electrode that alters the spin state population density for the unpaired electron associated with a chemical species within the electrolyte, thereby enhancing or inhibiting the reaction of the chemical species during subsequent electrolysis.

Abstract: An anode and cathode for an electrolytic cell configured as a low inductance transmission line to enable control of an interphase at an electrode surface. The anode and cathode are coupled to a switched current source by a low inductance path that includes a parallel plate transmission line, a coaxial transmission line, or both. The switched current source provides fast switching between current sources to provide fast charging and discharging of the double-layer capacitance associated with the electrode surface so that an isotope may be selectively transported to the electrode surface for oxidation or reduction. A photon source may be used to create a population of isotope containing species within the electrolyte. An additional static magnetic field and/or an alternating current magnetic excitation source may be used to modify the composition of the population of species containing the isotope to be separated.

Abstract: A high current density cathode for electrorefining in a molten electrolyte for the continuous production and collection of loose dendritic or powdery deposits. The high current density cathode eliminates the requirement for mechanical scraping and electrochemical stripping of the deposits from the cathode in an anode/cathode module. The high current density cathode comprises a perforated electrical insulated material coating such that the current density is up to 3 A/cm2.

Abstract: A high current density cathode for electrorefining in a molten electrolyte for the continuous production and collection of loose dendritic or powdery deposits. The high current density cathode eliminates the requirement for mechanical scraping and electrochemical stripping of the deposits from the cathode in an anode/cathode module. The high current density cathode comprises a perforated electrical insulated material coating such that the current density is up to 3 A/cm2.

Abstract: An electrolytic process for recovering uranium produces high quality uranium while reducing the processing necessary as well as the chemicals consumed. The process is environmentally friendly as it significantly reduces the emission of carbon dioxide from the processing system.

Abstract: Disclosed is a method of in-situ monitoring a reduction process of uranium oxides by lithium metal, wherein a conversion yield of uranium metal from uranium oxides upon production of uranium metal through a reaction of uranium oxides (UOx, x?3) with lithium metal in the presence of a high-temperature molten salt is measured according to an electrochemical analysis based on an oxidation of an oxygen ion and a reduction of a lithium ion dissociated from lithium oxide obtained as a by-product of the reaction, by use of a measuring device composed of a potentiostat/galvanostat and a reactor provided with an anode and a cathode. The in-situ monitoring method of the current invention is advantageous in terms of fast and simplified measuring techniques, by directly measuring the reduction process of uranium oxides at the anode and cathode connected to the potentiostat/galvanostat in the presence of the high-temperature molten salt.

Abstract: An anode and cathode for an electrolytic cell configured as a low inductance transmission line to enable control of an interphase at an electrode surface. The anode and cathode are coupled to a switched current source by a low inductance path that includes a parallel plate transmission line, a coaxial transmission line, or both. The switched current source provides fast switching between current sources to provide fast charging and discharging of the double-layer capacitance associated with the electrode surface so that an isotope may be selectively transported to the electrode surface for oxidation or reduction. A photon source may be used to create a population of isotope containing species within the electrolyte. An additional static magnetic field and/or an alternating current magnetic excitation source may be used to modify the composition of the population of species containing the isotope to be separated.

Abstract: An improved process and device for the recovery of the minor actinides and the transuranic elements (TRU's) from a molten salt electrolyte. The process involves placing the device, an electrically non-conducting barrier between an anode salt and a cathode salt. The porous barrier allows uranium to diffuse between the anode and cathode, yet slows the diffusion of uranium ions so as to cause depletion of uranium ions in the catholyte. This allows for the eventual preferential deposition of transuranics present in spent nuclear fuel such as Np, Pu, Am, Cm. The device also comprises an uranium oxidation anode. The oxidation anode is solid uranium metal in the form of spent nuclear fuel. The spent fuel is placed in a ferric metal anode basket which serves as the electrical lead or contact between the molten electrolyte and the anodic uranium metal.

Abstract: The invention provides a process for dissolving actinic oxides, the process comprising performing the steps of (a) introducing the actinic oxides into a solution of nitric acid; (b) treating the acidic solution in order to substantially remove palladium; and (c) treating with divalent silver. Preferably, the actinic oxides are comprised in spent nuclear fuel. Optionally, the process comprises a second treatment of the acidic solution in order to substantially remove palladium and a second treatment with divalent silver. The steps may be performed on a batchwise or continuous basis. The treatment to remove palladium is preferably carried out by solvent extraction or ion exchange, and provides greatly improved rates of dissolution of oxides of plutonium. The treatment with divalent silver preferably involves the addition of a source of monovalent silver, followed by an electrolysis treatment to generate divalent silver.

Abstract: The invention relates to an efficient process and device for the decontamination of waters polluted with heavy metals, semimetals and/or radionuclides by cation exchange and electrochemical deposition of the anions.

Abstract: A negative ion generating medium for generating negative ions from the surface of a mother material made of aluminum or aluminum alloy. The negative ion generating medium has the mother material of aluminum or aluminum alloy covered at the surface with an anodized layer on which a rare metal separated from a rare metal solution such as zirconium salt is deposited. As the rare metal is deposited in the pores provided in the anodized layer, its negative ion generating area can be increased thus releasing a large number of negative ions. The negative ion generating medium is manufactured by electrolytically processing the mother material in an electrolyte solution of sulfuric acid doped with a rare metal salt such as lithium salt to develop the anodized layer on the surface of the mother material and deposit the rare metal on the anodized layer.

Abstract: A method for separating a metal from a composition including the metal involves forming an electrolytic cell in which the anode comprises a composition including the metal. The electrolyte is an ionic liquid. A sufficient potential difference is applied between the anode and the cathode to cause the metal to transfer from the anode to the cathode deposited thereon.

Abstract: A new process for recycling spent nuclear fuels, in particular, mixed nitrides of transuranic elements and zirconium. The process consists of two electrorefiner cells in series configuration. A transuranic element such as plutonium is reduced at the cathode in the first cell, zirconium at the cathode in the second cell, and nitrogen-15 is released and captured for reuse to make transuranic and zirconium nitrides.

Abstract: A nuclear fuel electrorefiner for recovering uranium from nuclear material containing uranium. A cylindrical vessel with having a longitudinal axis has a product collector movable axially of the vessel. Circular cathodes extend axially of and radially spaced inwardly of the vessel with a plurality of generally polyhedron-shaped anode baskets having at least one face aligned with a radius of said vessel and circumferentially spaced from adjacent anode baskets and concentric with respect to the cathodes in the vessel. A plurality of axially extending metal rods are insulated from and placed between the anode baskets. Mechanism outside of the vessel rotate the anode baskets and the metal rods with respect to the cathodes, and an electrical power supply in selective electrical communication with said cathode and said anode baskets and said metal rods to cause uranium values to move between the and when current flow is in a first direction uranium values in said anode baskets and the metal rods to the cathodes.

Abstract: The present invention includes uranium-bearing ceramic phase electrodes and electrolysis apparatus and electrolysis methods featuring same, including methods of metal production and the like by the electrolytic reduction of oxides or salts of the respective metals. More particularly, the invention relates to an inert type electrode composition, and methods for fabricating electrode compositions, useful in the electrolytic production of such metals. The present invention also includes an inert-type electrode composition, and methods for fabricating electrode compositions, used in processes for generating energy from fossil fuels.

Abstract: A spent reactor fuel processing method is provided for recovering at least any one of metallic nuclear fuel materials, in which the reactor fuel is composed by covering the metallic nuclear fuel material with a cladding tube made of alloy and having a melting point lower than that of the metallic nuclear fuel material and end plugs made of alloy are mounted to both ends thereof. The processing method comprises a cladding tube smelting separation process, a molten salt electrorefining process and a salt evaporation separation process for recovering metallic uranium, uranium and plutonium, or uranium, plutonium and transuranium elements.

Abstract: Magnesium fluoride slag contaminated with metallic uranium or uranium compounds is treated by digestion with potassium hydroxide to soluble potassium fluoride and insoluble magnesium hydroxide. The solid and liquid phases are then separated and the solids phase is dissolved in acid to form a solution of metal salts. The liquid phase is treated with lime to precipitate calcium fluoride and convert the potassium back to potassium hydroxide for recycle to the digestion reaction. The metal salts are separated to remove the uranium salt from the magnesium salt. The result is an efficient removal of uranium contamination from the magnesium, the recovery of magnesium in a manner that permits efficient reuse or safe disposal, and the production of calcium fluoride useful for a variety of purposes.

Abstract: Apparatus and methods for decontaminating surfaces are disclosed. A housing is configured with first and second channels and first and second fluid pathways in fluid communication therewith, respectively. First and second applicators are positioned within respective first and second channels and electrodes are electrically connected with the applicators. Electric current of a first polarity is supplied to a first applicator via the first electrode, and electric current of a second polarity is supplied to a second applicator via the second electrode. Decontaminating a surface comprises supplying a first fluid to a first applicator, supplying a second fluid to a second applicator, generating an electrical potential between the first and second applicators, and contacting the contaminated surface with the first and second applicators.

Abstract: Processes for in-situ decontamination and recovery of metal from radioactive-contaminated metal which is contained in process equipment, including ancillary systems of process equipment, comprise two basic steps. In the first step, an acid decontamination solution is circulated through the equipment and in contact with the radioactive-contaminated metal for removing the radioactive contaminants and a first surface portion of the metal from the metal-containing equipment. In the second step, an acid digestion solution is circulated through the equipment for removing at least a second portion of the metal which is substantially free of radioactive contaminants. The present methods are particularly suitable for in-situ decontamination and recovery of nickel from radioactive-contaminated nickel diffusion barriers in the cascade converters of uranium gas diffusion plants.

Abstract: A process and apparatus for dissolving a mixed oxide or mixture of oxides of uranium and plutonium. The powder is added with nitric acid to a chamber to dissolve uranium oxide, and the solution is circulated through a circuit of the apparatus with a portion of the solution passing through a filter. At least a portion of the filtered solution containing dissolved uranium oxide is removed from the apparatus, while returning non-filtered circulating solution containing non-dissolved plutonium oxide to the chamber. The removal of solution is then terminated, a monovalent silver salt is added and divalent silver is generated in-situ by electrolysis, the divalent silver causing dissolution of the plutonium oxide.

Abstract: A process of remediation of cationic heavy metal contamination from soil utilizes gas phase manipulation to inhibit biodegradation of a chelating agent that is used in an electrokinesis process to remove the contamination, and further gas phase manipulation to stimulate biodegradation of the chelating agent after the contamination has been removed. The process ensures that the chelating agent is not attacked by bioorganisms in the soil prior to removal of the contamination, and that the chelating agent does not remain as a new contaminant after the process is completed.

Abstract: A cathode-anode arrangement for use in an electrolytic cell is adapted for electrochemically refining spent nuclear fuel from a nuclear reactor and recovering purified uranium for further treatment and possible recycling as a fresh blanket or core fuel in a nuclear reactor. The arrangement includes a plurality of inner anodic dissolution baskets that are each attached to a respective support rod, are submerged in a molten lithium halide salt, and are rotationally displaced. An inner hollow cylindrical-shaped cathode is concentrically disposed about the inner anodic dissolution baskets. Concentrically disposed about the inner cathode in a spaced manner are a plurality of outer anodic dissolution baskets, while an outer hollow cylindrical-shaped is disposed about the outer anodic dissolution baskets. Uranium is transported from the anode baskets and deposited in a uniform cylindrical shape on the inner and outer cathode cylinders by rotating the anode baskets within the molten lithium halide salt.

Abstract: According to the invention, a consumable anode constituted by a metal alloy incorporates between 20 and 70 wt. % iron, between 20 and 40 wt. % cobalt and between 5 and 30 wt. % aluminium. To these basic constituents can optionally be added elements such as nickel and/or titanium and/or copper and/or niobium. The decontamination process involves an electrodissolution of said anode.