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7749469 |
Process for recovering isolated uranium from spent nuclear fuel using a highly alkaline carbonate solution
Disclosed is a process for recovery of uranium from a spent nuclear fuel using a carbonate solution, characterized by excellent proliferation resistance of preventing leaching of transuranium...
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7192563 |
Process for recovery of high purity uranium from fertilizer grade weak phosphoric acid
A two-cycle countercurrent extraction process for recovery of highly pure uranium from fertilizer grade weak phosphoric acid. The proposed process uses selective extraction using di-(2-ethyl hexyl)...
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5787332 |
Process for recovering tantalum and/or niobium compounds from composites containing a variety of metal compounds
A process for treating composite materials comprising metals and having significant radioactivity for separation into concentrated individual products is provided. The process of the invention...
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5437848 |
Recovery of metal values from process residues
A process for recovering metal and acid values from a source material containing metallic fluorides comprises digesting the source material in sulfuric acid to form a slurry, separating a fluoride...
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5391347 |
Process for the production of sintered nuclear fuel pellets from precipitated solutions with the aid of hydrogen peroxide in an acid medium
Process for obtaining fritted oxide pellets of the MxOy type for nuclear fuels from solutions of soluble salts of the element or elements M, involving stage of precipitating the elements M by...
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5084252 |
Method and means for continuous precipitation of easy-dry, granular uranium peroxide
A method and means for continuous precipitation of granular uranium peroxide. The reaction vessel and agitation method practiced in it avoid filter plugging and caking problems.
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4894209 |
Process for obtaining a uranium-bearing concentrate of high purity from liquors contaminated with zirconium
The invention has as its object a process for the purification of a uranium solution which is contaminated by zirconium. This process consists of bringing the pH of the solution to a value of 1 to...
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4871147 |
Apparatus for the pyrometallurgical processing of fine-grained solids
An apparatus is described which serves for a pyrometallurgical processing of fine-grained solids suspended in high-oxygen gases, comprising a generally horizontally extending cylindrical vessel and...
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4793978 |
Method and apparatus for producing uranyl peroxide (U04.2H2 O) from uranium and uranium alloy pieces
A method and apparatus are provided for producing uranyl peroxide (UO4.2H2 O) from uranium-bearing metal pieces. The uranium-bearing metal pieces are dissolved in a first aqueous solution...
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D293123 |
Cloth bunny
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4636368 |
Stabilized acidic aqueous solutions containing hydrogen peroxide and metallic ions and processes
A stabilized acidic aqueous composition comprising hydrogen peroxide, metallic ions, and 3-amino-1,2,4-triazine, said triazine being present in an amount sufficient to improve the stability of said...
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4530823 |
Uranium peroxide in the form of spherical particles having good flowability and processes for preparing same
A process for preparing uranium peroxide in a fluidized bed by precipitation of a uranium peroxide solution obtained from the reaction of uranyl sulfate or uranyl nitrate solutions having a...
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4428911 |
Method of precipitating uranium peroxide
Uranium peroxide is precipitated from an acidified carbonate strip solution by the addition of hydrogen peroxide and a sufficient quantity of the alkaline carbonate strip solution to maintain the...
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4423008 |
Direct acid elution of anionic exchange resins for recovery of uranium
A process as disclosed for recovering uranium values from a carbonate leach solution which comprises directly eluting a column of resin onto which uranium has been sorbed by flowing a concentrated...
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4410497 |
Separation of uranium from carbonate containing solutions thereof by direct precipitation
A direct precipitation method based on the insolubility of uranyl phosphate in carbonate containing solutions at pH 6-6.5 and its insolubility at pH 8 is described. The method eliminates the use of...
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T102906 |
Method of removing phosphorus impurities from yellowcake
Phosphorus impurities are removed from yellowcake by dissolving it in hydrochloric or sulfuric acid to a U3 O8 assay of at least 150 g/l at a pH of 2; precipitating uranium peroxide with hydrogen...
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4375452 |
Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange
A process is described for recovering uranium from a pregnant lixiviant containing uranium values and a certain portion of molybdenum values comprising passing the pregnant lixiviant through an...
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4338286 |
Process for recovering uranium and/or thorium from a liquid containing uranium and/or thorium
A process for recovering uranium and/or thorium from a liquid containing uranium and/or thorium is disclosed, which comprises making a precipitate composed mainly of amorphous silica formed by...
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4302427 |
Recovery of uranium from wet-process phosphoric acid
Uranium values are recovered as uranyl peroxide from wet process phosphoric acid by a solvent extraction-precipitation process. The preferred form of this process comprises a first solvent...
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4302428 |
Yellowcake processing in uranium recovery
A process for the recovery of uranium by precipitation from a rich eluate by contacting the eluate with hydrogen peroxide to produce uranium peroxide yellowcake and reacting the yellowcake with a...
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4298578 |
Leach method including means to protect ion exchange resin
A method for recovering uranium and/or related values which include means for protecting ion-exchange resins in the recovery operation from oxidative degradation due to contact with hydrogen...
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4265861 |
Method of reducing radioactive waste and of recovering uranium from it
A method is described for reducing the volume of radioactive waste produced during the solution mining of uranium and for recovering uranium from it. The recovery leach, which contains uranium in...
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4258012 |
Method of purifying uranium tetrafluoride hydrate and preparing uranium (VI) peroxide hydrate using a fluoride complexing agent
A method of preparing uranium (VI) peroxide hydrate from uranium tetrafluoride hydrate, comprising the steps of digesting uranium tetrafluoride hydrate in an aqueous acid in the presence of a...
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4247522 |
Method of purifying uranium tetrafluoride hydrate and preparing uranium (VI) peroxide hydrate using a fluoride precipitating agent
A method of preparing uranium (VI) peroxide hydrate from uranium tetrafluoride hydrate, comprising the steps of digesting uranium tetrafluoride hydrate in an aqueous acid in the presence of a...
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4152395 |
Process for the production of free-flowing directly compactable uranium dioxide powder with adjustable sintering properties and apparatus for this process
There is provided a process for the production of pourable, directly compactable uranium dioxide powder by continuous precipitation of uranium peroxide from a stirred uranyl nitrate solution at a...
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4024215 |
Production of uranium peroxide
A process of recovering uranium values as uranium peroxide from an aqueous uranyl solution containing dissolved vanadium and sodium impurities by treating the uranyl solution with hydrogen peroxide...
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3980757 |
Process for uranium separation and preparation of UO4.2NH3.2HF
A process for treating the aqueous effluents that are produced in converting gaseous UF6 (uranium hexafluoride) into solid UO2 (uranium dioxide) by way of an intermediate (NH4)4 UO2 (CO3) 3 ("AUC"...
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3697441 |
METHOD FOR PREPARING STABLE ACTINIDE PEROXIDE SOLS
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3842155 |
TREATMENT OF WASTE MATERIALS GENERATED IN THE CONVERSION OF UF6 TO UO2 BY THE AUC ROUTE
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3238014 |
Recovery of uranium and plutonium values from aqueous solutions of ammonium fluoride
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3081148 |
Inhibition of post precipitation of uranium in barren liquor of carbonate leaching process
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3033645 |
Precipitation of plutonous peroxide
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2996352 |
Precipitation of plutonous peroxide
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2978295 |
Recovery of plutonium by carrier precipitation
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2936213 |
Process of reducing plutonium to tetravalent state
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2905525 |
Method of separation of plutonium from carrier precipitates
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2900228 |
Selective separation of uranium from thorium, protactinium and fission products by peroxide dissolution method
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2878100 |
Formation of uranium precipitates
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2873169 |
Basic peroxide precipitation method of separating plutonium from contaminants
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2855270 |
Process of recovering uranium
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2852336 |
Peroxide process for separation of radioactive materials
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2849284 |
Method of separating uranium suspensions
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2847277 |
Precipitation of uranium peroxide of low fluoride content from solutions containing fluorides
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2843453 |
Separation of plutonyl ions
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2839358 |
Process of recovering uranium
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2838371 |
Method of separating plutonium from lanthanum fluoride carrier
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2782091 |
Uranium recovery process
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2780516 |
Chemical purification of uranium compounds
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2780515 |
Method for improved precipitation of uranium peroxide
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2779657 |
Recovery of uranium from wash liquids
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