200335 ⎘
Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel; Reprocessing of irradiated fuel of irradiated solid fuel Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
INSTALLATION AND METHOD FOR CONVERTING URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE
#2SEPARATION OF METAL IONS BY LIQUID-LIQUID EXTRACTION
#3Separation apparatus for high-level nuclear waste
#4MODULAR, INTEGRATED, AUTOMATED, COMPACT, AND PROLIFERATION-HARDENED METHOD TO CHEMICALLY RECYCLE USED NUCLEAR FUEL (UNF) ORIGINATING FROM NUCLEAR REACTORS TO RECOVER A MIXTURE OF TRANSURANIC (TRU) ELEMENTS FOR ADVANCED REACTOR FUEL, AND TO RECYCLE URANIUM AND ZIRCONIUM
#5Modular, integrated, automated, compact, and proliferation-hardened method to chemically recycle used nuclear fuel (UNF) originating from nuclear reactors to recover a mixture of transuranic (TRU) elements for advanced reactor fuel to recycle uranium and zirconium
#6Modular, integrated, automated, compact, and proliferation-hardened method to chemically recycle used nuclear fuel (UNF) originating from nuclear reactors to recover a mixture of transuranic (TRU) elements for advanced reactor fuel to recycle uranium and zirconium
#7Equipment for producing nuclear fuel powder
#8INSTALLATION AND METHOD FOR CONVERTING URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE
#9Carbamides for separating uranium(VI) and plutonium(IV) without reducing the plutonium(IV)
#10Dissymmetric N,N-dialkylamides used particularly for separating uranium(VI) from plutonium(IV), synthesis thereof and uses of same
#11Method for preparing a powder comprising particles of triuranium octoxide and particles of plutonium dioxide
#12SYSTEMS AND METHODS FOR THERMAL MOLTEN SALT REACTOR FUEL-SALT PREPARATION
#13Method for recycling plutonium from spent radioactive fuel
#14Method to produce salts containing actinide halides
#15Separation of metal ions by liquid-liquid extraction
#16Method for dissolving nuclear fuel
#17Use of hydroxyiminoalkanoic acids as anti-nitrous agents in operations of reductive stripping of plutonium
#18Method for the treatment of an aqueous nitric solution resulting from dissolving spent nuclear fuel, said method being performed in a single cycle and without requiring any operation involving reductive stripping of plutonium
#19Electrolytic tank and electrolytic method for high-efficiency dry reprocessing
#20Method of recovering nuclear fuel material
#21Removal of radionuclides from mixtures
#22Method for controlling aluminum dissolution
#23Method for processing spent nuclear fuel comprising a step for decontaminating uranium (VI) from at least one actinide (IV) by complexing this actinide (IV)
#24Process for preparing a powder comprising a solid solution of uranium dioxide and of a dioxide of at least one other actinide and/or lanthanide element
#25Method of recovering nuclear fuel material
#26POLYMERIC CHELATORS FOR METAL ION EXTRACTION AND SEPARATION
#27FUNCTIONAL CONDUCTING POLYMERS FOR REDOX MEDIATED SEPARATIONS OF F-ELEMENTS
#28Recovery of uranium from an irradiated solid target after removal of molybdenum-99 produced from the irradiated target
#29Recovering and recycling uranium used for production of molybdenum-99
#30Process and apparatus for treating a gas stream
#31Purification of metals
#32Method for precipitating one or more solutes
#332,9-dipyridyl-1,10-phenanthroline derivatives useful as actinide ligands, method for synthesizing same, and uses thereof
#34Compositions and methods for treating nuclear fuel
#35Process for separating at least one platinoid element from an acidic aqueous solution comprising, besides this platinoid element, one or more other chemical elements
#36Method for corium and used nuclear fuel stabilization processing
#37Tributyl phosphate-nitrate solvent extraction process for producing high purity nuclear grade rare earth metal oxides
#38Process for separating americium from other metallic elements present in an acidic aqueous or organic phase
#39Process for reprocessing spent nuclear fuel not requiring a plutonium-reducing stripping operation
#40Use of certain chemical elements for inhibiting the formation of precipitates containing zirconium molybdate in an aqueous solution containing the element molybdenum and the element zirconium
#41Methods of separating medical isotopes from uranium solutions
#42Method for purifying the uranium from a natural uranium concentrate
#43Method for preparing a porous nuclear fuel based on at least one minor actinide
#44METHOD FOR OXIDATION TREATMENT OF A SUBSTRATE FOR THE ADSORPTION OF RADIONUCLIDES
#45Compounds useful as ligands of actinides, their synthesis and their uses
#46Dialkyldiaza-tetraalkyloctane diamide derivatives useful for the separation of trivalent actinides from lanthanides and process for the preparation thereof
#47Increase in the separation factor between americium and curium and/or between lanthanides in a liquid-liquid extraction operation
#48Method for selectively recovering americium from a nitric aqueous phase
#49Method for treating spent nuclear fuel
#50Method of recovering enriched radioactive technetium and system therefor
#51Method for preparing an actinide(s) oxalate and for preparing an actinide(s) compound
#52Method and apparatus for the extraction and processing of molybdenum-99
#53Encapsulation of nano-materials for fluid purification/separation
#54Decontamination of radioactive liquid effluent by solid-liquid extraction using a recycle loop
#55Compositions and methods for treating nuclear fuel
#56Method for separating and recycling uranium and fluorine form solution
#57Use of butyraldehyde oxime as an anti-nitrous agent in an operation for the reductive stripping of plutonium
#58Process for Treating Spent Nuclear Fuel
#59Electrochemically Modulated Separations for In-line and At-line Monitoring of Actinides in High-Volume Process Streams
#60Purification of metals
#61Solute precipitation method and device
#62Process for the extraction of technetium from uranium
#63Method for extraction of metals by methyliminobisalkylacetamide
#64Method for reprocessing spent nuclear fuel and centrifugal extractor therefor
#65Process for separating a chemical element from uranium (VI) starting from a nitric aqueous phase, in an extraction cycle for the uranium
#66Method for selective separation of trivalent and tetravalent actinoids from trivalent lanthanoids using hybrid donor type extractant having functional group carrying active oxygen and nitrogen atoms
#67Demineralizer of primary coolant system in pressurized-water reactor power plant and method for purifying primary cooling water in pressurized-water reactor power plant
#68SPENT FUEL REPROCESSING METHOD
#69RADIONUCLIDE RESINS
#70PROCESS FOR REPROCESSING A SPENT NUCLEAR FUEL AND OF PREPARING A MIXED URANIUM-PLUTONIUM OXIDE
#71Grouped separation of actinides from a strongly acidic aqueous phase
#72Process for preparing magnetic particles for selectively removing contaminants from solution
#73Sodium salt recycling process for use in wet reprocessing process of spent nuclear fuel
#74Electrochemical Process to Recycle Aqueous Alkali Chemicals Using Ceramic Ion Conducting Solid Membranes
#75PROCESS FOR TREATING COMPOSITIONS CONTAINING URANIUM AND PLUTONIUM
#76Method and system for recovering metal from metal-containing materials
#77Purex method and its uses
#78Extraction of radionuclides by crown ether-containing extractants
#79Process for reprocessing a spent nuclear fuel and of preparing a mixed uranium-plutonium oxide
#80Electrolytic apparatus for use in oxide electrowinning method
#81Method for separating uranium (VI) from actinides(IV) and/or actinides (VI) and its uses
#82Process for the dissolution of actinic oxides
#83Mediated electrochemical oxidation for decontamination
#84Treatment process for removing radioactive thorium from solvent extraction liquid effluent
#85Separation apparatus for high-level nuclear waste
#86Reduction-oxidation of actinides extraction process (ROANEX) for used nuclear fuel recycling