Matches 201 - 250 out of 362 < 1 2 3 4 5 6 7 8 >


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4212849 Simultaneous extraction and recovery of uranium and vanadium from wet process acids  
A process for the simultaneous coextraction of uranium and vanadium from an aqueous acidic solution containing the same comprising contacting said aqueous acidic solution with an organic phase...
4208377 Process for recovering actinide values  
A process for rendering actinide values recoverable from sodium carbonate scrub waste solutions containing these and other values along with organic compounds resulting from the radiolytic and...
4207294 Process for recovering uranium from wet-process phosphoric acid  
A process for recovering uranium from a wet-process phosphoric acid crude solution is provided in which the phosphoric acid crude solution is contacted with an organic extractant consisting of...
4197195 Method for minimizing the organic waste in aqueous product streams produced in liquid-liquid extraction processes  
A method is provided for minimizing the organic waste found in an aqueous process stream of products and refined products from a liquid-liquid extraction process. The aqueous process stream...
4190633 Crud handling circuit  
A method for handling the problem of crud formation in the solvent extraction of wet-process phosphoric acid is described. Crud is the name ordinarily given to the thick interfacial layer of...
4186175 Crown ether uranyl halide complexes  
Uranium oxide is recovered from an aqueous solution of uranyl halides by extracting uranyl halide from the aqueous solution with an organic liquid, forming a crown ether uranyl halide complex in...
4162230 Method for the recovery of actinide elements from nuclear reactor waste  
A process for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to...
4141854 Emulsion breaking  
A method of resolving water-in-oil emulsions resulting from the organic solvent extraction of uranium from aqueous leach liquors which comprises treating said emulsions with at least 20 parts per...
4131527 Method for selectively reducing plutonium values by a photochemical process  
The rate of reduction of Pu(IV) to Pu(III) in nitric acid solution containing a reducing agent is enhanced by exposing the solution to 200-500 nm electromagnetic radiation. Pu values are recovered...
4105741 Process for recovery of uranium from wet process phosphoric acid  
Process for the recovery of uranium from wet process phosphoric acid solution in which an organic extractant, containing uranium values and dissolved iron impurities and comprising a...
4087512 Process for removing solid organic material from wet-process phosphoric acid  
Wet-process phosphoric acid which is obtained by the acidulation of uncalcined phosphate rock with sulphuric acid and which typically contains 28-31% P2 O5 and measurable amounts of solid organic...
T970007 Uranium recovery from wet-process phosphoric acid  
a method of recovering uranium from wet-process phosphoric acid wherein the acid is treated with a mixture of an ammonium salt or ammonia, a metallic reducing agent such as iron, aluminum or zinc,...
4080273 Method for photochemical reduction of uranyl nitrate by tri-N-butyl phosphate and application of this method to nuclear fuel reprocessing  
Uranyl ion in solution in tri-n-butyl phosphate is readily photochemically reduced to U(IV). The product U(IV) may effectively be used in the Purex process for treating spent nuclear fuels to...
4059671 Method for increasing the lifetime of an extraction medium used for reprocessing spent nuclear fuel and/or breeder materials  
A method is provided for increasing the lifetime of an extraction medium containing an organophosphorus acid ester and a hydrocarbon and being used for reprocessing spent nuclear fuel and/or...
4022708 Method of preparation for storage of liquids used in the reprocessing of spent nuclear fissile and/or fertile materials  
A method of preparation for non-polluting storage of liquids containing phosphoric acid ester and hydrocarbons used in the reprocessing of spent nuclear fissile and/or fertile materials. The...
4011296 Irradiated fuel reprocessing  
A process for separately recovering uranium, plutonium and neptunium substantially free of fission products from irradiated nuclear fuel is presented in which the fuel is dissolved in a strong...
4002716 Sulfide precipitation method of separating uranium from group II and group III metal ions  
Uranium is separated from analytical Group II and Group III metal ions in an aqueous liquor containing uranyl ions. The liquor is extracted with a non-interfering, water-immiscible, organic...
3993728 Bidentate organophosphorus solvent extraction process for actinide recovery and partition  
A liquid-liquid extraction process for the recovery and partitioning of actinide values from acidic nuclear waste aqueous solutions, the actinide values including trivalent, tetravalent and...
3991154 Method of reprocessing fuel and/or breeder material containing thorium dissolved in an acid solution  
A method of regenerating fuel and/or breeder elements with thorium as brer material for nuclear reactors. The fuel and/or breeder material is dissolved in an acid such as nitric acid, sulfuric...
3987145 Ferric ion as a scavenging agent in a solvent extraction process  
Ferric ions are added into the aqueous feed of a plutonium scrap recovery process that employs a tributyl phosphate extractant. Radiolytic degradation products of tributyl phosphate such as...
3981961 Method of selective stripping of plutonium from organic solvents loaded with plutonium  
The method of selective stripping from plutonium-loaded organic solvents which may also contain uranium consists in passing the organic solvent in countercurrent contact with an aqueous solution...
3980750 Method of selective stripping of plutonium from an organic solvent containing plutonium and in some cases uranium by reduction of said plutonium  
The method of selective stripping from plutonium-loaded organic solvents which may also contain uranium consists in bringing the initial organic solvent into countercurrent contact with a solution...
3966872 Coupled cationic and anionic method of separating uranium  
Uranium is separated from contaminating metal ions in an aqueous feed liquor containing the uranyl ion. The liquor is extracted with a first, non-interfering, waterimmiscible, organic solvent...
3966873 Uranium complex recycling method of purifying uranium liquors  
Uranium is separated from contaminating cations in an aqueous liquor containing uranyl ions. The liquor is mixed with sufficient recycled uranium complex to raise the weight ratio of uranium to...
3962401 Method of recovering neptunium from spent nuclear fuel  
An improved Purex wet recovery process including the step of extracting and separating uranium and plutonium simultaneously from the fission products in the presence of nitric acid and nitrous...
3959435 Improvements in the processing of irradiated nuclear reactor fuel  
A process for the treatment of irradiated fissile material in solution in nitric acid in which tributylphosphate diluted to less than 7% by volume with an inert diluent is contacted with the...
3949048 Separation by solvent extraction  
17. A process for separating fission product values from uranium and plutonium values contained in an aqueous solution, comprising adding an oxidizing agent to said solution to secure uranium and...
3949049 Method of stripping plutonium from tributyl phosphate solution which contains dibutyl phosphate-plutonium stable complexes  
Fast breeder fuel elements which have been highly burnt-up are reprocessed by extracting uranium and plutonium into an organic solution containing tributyl phosphate. The tributyl phosphate...
3943204 Method for improving the extraction properties of a tributyl phosphate solution  
A method for improving the extraction properties of a tributyl phosphate extractant used for reprocessing irradiated nuclear reactor fuel (Purex Process) containing degradation products of...
3857919 SEPARATING METAL VALUES BY SELECTIVE EXTRACTION  
Double solvent extraction process wherein an aqueous solution of difficult to separate metals is alternately contacted with two different solvents and at least one metal is preferentially...
3835213 CO-EXTRACTION AND SEPARATE RECOVERY OF URANIUM AND THORIUM FROM ACID SOLUTIONS  
A process is described for separating uranium and thorium from an aqueous acid solution containing them together with rare earth elements. The process comprises contacting the solution with a...
3835214 OXIDATIVE STRIPPING PROCESS FOR THE RECOVERY OF URANIUM FROM WET-PROCESS PHOSPHORIC ACID  
A process for the recovery of uranium from a wet-process type phosphoric acid solution is effected by adjusting said solution with sufficient ferrous ion to insure that the uranium is in the...
3812232 SOLVENT EXTRACTION PROCEDURE FOR SEPARATING SAMARIUM FROM NEODYMIUM  
Separation of mixtures of metals, particularly complex lanthanide mixtures, in aqueous solution is accomplished by means of a process comprising total extraction of metal values into an organic...
3714324 IRRADIATED FUEL RECOVERY SYSTEM  
An improved process for recovering irradiated nuclear reactor fuel material is disclosed. This process includes the steps of extracting uranium, plutonium and neptunium from a solution of...
3711591 REDUCTIVE STRIPPING PROCESS FOR THE RECOVERY OF URANIUM FROM WET-PROCESS PHOSPHORIC ACID  
A reductive stripping flow sheet for recovery of uranium from wet-process phosphoric acid is described. Uranium is stripped from a uranium-loaded organic phase by a redox reaction converting the...
3708508 METHOD FOR THE PURIFICATION AND RECOVERY OF TRIBUTYL PHOSPHATE USED IN REPROCESSING NUCLEAR FUEL  
Tributyl phosphate solutions used in reprocessing nuclear fuel are purified and removed by passing them through a bed of particles of a macroreticular anion or cation exchange resin whereby the...
3652233 METHOD OF IMPROVING RECOVERY OF NEPTUNIUM IN THE PUREX PROCESS  
The recovery of neptunium values from the Purex Process for reprocessing irradiated nuclear reactor fuel is improved by adding a rate-accelerating material to increase the rate of oxidation of the...
3616276 PROCESS FOR CHANGING THE VALENCE OF A METAL OF VARIABLE VALENCE IN AN ORGANIC SOLUTION  
A process for changing the valence of a metal of variable valence in an organic solution whereby a dispersion is formed by agitating the organic solution with an immiscible aqueous solution and an...
3616275 PROCESS FOR CONCENTRATING A METAL OF VARIABLE VALENCE IN AQUEOUS SOLUTION  
Method for concentrating a metal of variable valence in aqueous solution by extracting the metal with an immiscible organic solvent, separating the resulting immiscible solutions, forming a...
3533757 PROCESSES FOR SIMULTANEOUSLY PURIFYING AND CONCENTRATING PLUTONIUM SOLUTIONS  
3523765 MULTISTAGE PROCESS FOR EXTRACTING U AND PU WITH SOLVENT COMPRISING TRIBUTYLPHOSPHATE  
3511621 PROCESS FOR RECOVERING URANIUM AS URANIUM DIOXIDE  
3748104 EXTRACTION OF TRANSPLUTONIUM ELEMENTS FROM AN AQUEOUS SOLUTION CONTAINING RARE EARTHS AND FISSION PRODUCTS  
3836476 SIMULTANEOUS RECOVERY OF VANADIUM AND URANIUM FROM OXIDIZED WET PROCESS ACID  
3808320 METHOD FOR REPROCESSING RADIOACTIVE MATERIALS  
3745205 EXTRACTION OF URANIUM FROM AN AQUEOUS SOLUTION  
3808306 PROCESSES FOR RECOVERING URANIUM VALUES FROM ORES  
3740199 ORE SEPARATION PROCESS  
3560169 MANNER OF PROCESSING PLUTONIUM-CONTAINING URANIUM FUEL FROM NUCLEAR REACTORS  
3580705 SELECTIVE STRIPPING OF PLUTONIUM FROM ORGANIC EXTRACTS  

Matches 201 - 250 out of 362 < 1 2 3 4 5 6 7 8 >