Class / Patent application number | Description | Number of patent applications / Date published |
205043000 | ELECTROLYTIC PROCESS INVOLVING ACTINIDE SERIES ELEMENTS OR COMPOUND (AT. NO. 89+) (PRODUCT, PROCESS, COMPOSITION, AND METHOD OF PREPARING COMPOSITION) | 12 |
20100025251 | System for automatically producing radioisotopes - A system for automatically producing radioisotopes, and including a target carrier; an electrodeposition unit for electrodepositing a target in the target carrier; an irradiation unit for irradiating the target in the target carrier; first transfer means for transferring the target carrier from the electrodeposition unit to the irradiation unit; an electrodissolution unit for electrodissolving the irradiated target; second transfer means for transferring the target carrier from the irradiation unit to the electrodissolution unit; a purifying unit for purifying the radioisotope of the non-reacting target and impurities; third transfer means for transferring the electrodissolved irradiated target from the electrodissolution unit to the purifying unit; and a central control unit for controlling the operating units and transfer means to automate the entire process. The electrodissolution of the irradiated target is carried out without corroding said target carrier. | 02-04-2010 |
20110017601 | Method for Recovery of Residual Actinide Elements from Chloride Molten Salt - A method for recovery of residual actinide element from chloride molten salts that are formed after electro-refining and/or electro-winning of a spent nuclear fuel and include actinide elements and rare-earth elements is provided. The method comprises conducting electrolysis using a liquid cadmium cathode (LCC) in the chloride molten salt that is formed after electro-refining and/or electro-winning of a spent nuclear fuel and contains rare-earth elements and actinide elements; electro-depositing the actinide elements contained in the chloride molten salt on the LCC in order to reduce a concentration of the actinide elements; and adding a CdCl | 01-27-2011 |
205044000 | Plutonium | 4 |
20100038249 | METHOD FOR REPROCESSING SPENT NUCLEAR FUEL AND CENTRIFUGAL EXTRACTOR THEREFOR - A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent. | 02-18-2010 |
20130186762 | DETECTION METHOD USING AN ELECTROCHEMICALLY-ASSISTED ALPHA DETECTOR FOR NUCLEAR MEASUREMENT IN A LIQUID MEDIUM - An in situ method for detecting alpha particles contained in a liquid medium, which uses a system which includes a counter-electrode and an alpha particle detector including a substrate made of an intrinsic semiconductor material sandwiched between two electrical contacts, wherein the contact intended to be in contact with the liquid medium is made of boron-doped diamond. By forming a particular electrolyte 8 and by causing a current to flow between counter-electrode and the boron-doped diamond contact in contact with the liquid medium, actinides or polonium present in the liquid medium may be concentrated on the boron-doped diamond contact, and by this means the detection limit of the alpha emitters may be lowered. | 07-25-2013 |
20130233716 | Room Temperature Electrodeposition of Actinides from Ionic Solutions - Uranic and transuranic metals and metal oxides are first dissolved in ozone compositions. The resulting solution in ozone can be further dissolved in ionic liquids to form a second solution. The metals in the second solution are then electrochemically deposited from the second solutions as room temperature ionic liquid (RTIL), tri-methyl-n-butyl ammonium n-bis(trifluoromethansulfonylimide) [Me | 09-12-2013 |
20160053391 | METHODS OF FABRICATING METALLIC FUEL FROM SURPLUS PLUTONIUM - A method of fabricating metallic fuel from surplus plutonium may include combining plutonium oxide powder and uranium oxide powder to obtain a mixed powder with reduced proliferation potential. The mixed powder may be electroreduced in a bath of molten salt so as to convert the mixed powder to a first alloy. The first alloy may be pressed to remove a majority of the molten salt adhered to the first alloy to form a pressed alloy-salt mixture. The first alloy may be isolated from the salt by melting the pressed alloy-salt mixture. The first alloy may be further processed to fabricate a fuel rod. Accordingly, the metallic fuel produced may be used in a fast reactor system, such as a Power Reactor Innovative Small Module (PRISM). | 02-25-2016 |
205046000 | Uranium | 6 |
20090032403 | URANIUM RECOVERY USING ELECTROLYSIS - 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. | 02-05-2009 |
20090050483 | HIGH CURRENT DENSITY CATHODE FOR ELECTROREFINING IN MOLTEN ELECTROLYTE - 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/cm | 02-26-2009 |
20130206599 | METHOD FOR MEASURING THE URANIUM CONCENTRATION OF AN AQUEOUS SOLUTION BY SPECTROPHOTOMETRY - 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). | 08-15-2013 |
205047000 | Utilizing fused bath | 3 |
20110180409 | HIGH -THROUGHPUT ELECTROREFINER FOR RECOVERY OF U AND U/TRU PRODUCT FROM SPENT FUEL - The present invention provides a method of simultaneously removing uranium and transuranics from metallic nuclear fuel in an electrorefiner. In the method, a potential difference is established between the anode basket and solid cathode of the electrorefiner, thereby creating a diffusion layer of uranium and transuranic ions at the solid cathode, a first current density at the anode basket, and a second current density at the solid cathode. The ratio of anode basket area to solid cathode area that is selected based on the total concentration of uranium and transuranic metals in a molten halide electrolyte in the refiner and the effective thickness of the diffusion layer at the solid cathode, such that the established first and second current densities result in both codeposition of uranium and transuranic metals on the solid cathode and oxidation of the metallic nuclear fuel in the anode basket. Deposited material on the solid cathode is removed, and the first current density at the anode basket is maintained to prevent substantial oxidation of the anode basket during operation of the electrorefiner. | 07-28-2011 |
20160010232 | TREATMENT OF TITANIUM ORES | 01-14-2016 |
20160032473 | ELECTROCHEMICAL CELL FOR RECOVERY OF METALS FROM SOLID METAL OXIDES - An electrochemical cell and methods of using the electrochemical cell are described that can be utilized for the recovery of metals from metal oxides. The cell includes a first electrode that includes a solid metal oxide, an electrolyte including an oxygen ion conductor, and a second electrode space apart from the electrolyte by an oxygen ion conducting membrane. Upon reduction of the metal oxide, solid metal is formed that replaces the metal oxide of the electrode and provides for simplified recovery of the metal from the metal oxide. The membrane protects the second electrode from corrosion and degradation from the electrolyte, increasing the life of the cell. | 02-04-2016 |