Celebrity Inventors
Comic actor Danny Kaye received patent D166,807 for the co-design of "Blowout Toy or the Like". It's similar to one of those toys that unravels when you blow into at a birthday party except Kaye's has three blowouts going in different directions, not just one.
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| Number | Title | Issue Date |
| 7255798 | Recycling of used perfluorosulfonic acid membranes A method for recovering and recycling catalyst coated fuel cell membranes includes dissolving the used membranes in water and solvent, heating the dissolved membranes under pressure and separating the components. Active membranes are produced from the recycled mater... | 08/14/2007 |
| 5640701 | Method for remediating soil containing radioactive contaminants Soil comprising small soil particles, clay and silt particles, humus, fine vegetation, and contaminated with soluble or insoluble radioactive species is treated by first introducing an aqueous extracting solution comprising a mixture of sodium and potassi... | 06/17/1997 |
| 5494648 | Process for removing thorium and recovering vanadium from titanium chlorinator waste A process for removal of thorium from titanium chlorinator waste comprising: (a) leaching an anhydrous titanium chlorinator waste in water or dilute hydrochloric acid solution and filtering to separate insoluble minerals and coke fractions from soluble me... | 02/27/1996 |
| 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 containing solid phase and a metal containing first liquid... | 08/01/1995 |
| 5384104 | Uranium carbonate extraction process A process for extracting uranium from uranium-containing waste residues. The process dissolves the residue in hot nitric acid, and precipitates the resulting solution with sodium carbonate/sodium bicarbonate.... | 01/24/1995 |
| 5322644 | Process for decontamination of radioactive materials A process for decontaminating radioactive material comprises the step of contacting the material with a dissolving composition to dissolve the contaminants in the material, said composition comprising a dilute solution of about 0.05 molar ethylene diamine... | 06/21/1994 |
| 5223181 | Process for selectively concentrating the radioactivity of thorium containing magnesium slag Magnesium is separated from magnesium slag containing radioactive thorium and its daughters by solubilizing magnesium from magnesium slurry using carbon dioxide and separating magnesium from magnesium slurry containing thorium and its daughters by filteri... | 06/29/1993 |
| 5202062 | Disposal method of radioactive wastes The present invention adds carbonates or chlorides of alkaline earth metals to the radioactive wastes containing sodium sulfate and subjects sulfate group in the radioactive wastes to reduction treatment, thereby converts the sulfate group into sulfides o... | 04/13/1993 |
| 4740359 | Process for the recovery of uranium values in an extractive reprocessing process for irradiated nuclear fuels An organic extraction phase, containing fission materials uranium and plutonium, as well as a minor amount of fission- and corrosion-products, from an extraction step or from a purification step of a nuclear fuel reprocessing process is treated with an aq... | 04/26/1988 |
| 4696768 | Process for the separation of large amounts of uranium from small amounts of radioactive fission products, which are present in basic, aqueous carbonate containing solutions A process for separating large amounts of uranium from small amounts of radioactive fission products, which are present in basic, aqueous carbonate containing solutions, by means of a basic, organic anion exchanger. Uranium values present as uranykl-carbo... | 09/29/1987 |
| 4655936 | Microbiological control in uranium processing A method of improving the recovery of U3 O8 from circulating aqueous leach fluids used to extract uranium from its ores in underground uranium fields, which fields are made up of a series of injection and producing wells, which aqueo... | 04/07/1987 |
| 4652431 | Process for recovering uranium using an alkyl pyrophosphoric acid and alkaline stripping solution A process is described for the recovery of uranium from wet-process phosphoric acid utilizing an alkyl pyrophosphoric extractant. The extractant also contains a modifier for retaining the alkyl pyrophosphoric acid in solution in an essentially water-immis... | 03/24/1987 |
| 4652432 | Process for recovering uranium using an alkyl pyrophosphoric acid and alkaline stripping solution A process is described for the recovery or uranium from wet-process phosphoric acid utilizing an alkyl pyrophosphoric extractant. The extractant also contains a modifier for retaining the alkyl pyrophosphoric acid ester in solution in an essentially water... | 03/24/1987 |
| 4649031 | Process for recovering rare metals from the combustion residue of coal by digestion The invention relates to a method for recovering rare metals from the combustion residues of various coals, in particular brown coals. The recovery is performed by digestion, more particularly by aqueous and/or dilute alkaline and/or dilute acidic digesti... | 03/10/1987 |
| 4636367 | Removal of radium from aqueous liquids A process for separating radium-226 from an aqueous liquid by adding a precipitant to the liquid. The liquid, including the precipitant, is passed upwardly through a particulate bed to assist co-precipitation and removal of the radium-226. The effect is t... | 01/13/1987 |
| 4634579 | Selective removal of arsenical material in the course of an alkaline process for treating a uraniferous and/or molybdeniferous ore by means of a magnesium compound A process for the selective removal of arsenical material in the course of a process for the hot oxidizing attack on a uraniferous and/or molybdeniferous ore containing arsenical materials, comprising attacking said ore with an aqueous liquor of sodium or... | 01/06/1987 |
| 4606894 | Uranium recovery from carbonate leach liquors using carboxylic acid cation exchange resin A process and apparatus for recovering uranium from a carbonate solution containing uranium ions whereby the carbonate solution containing uranium ions is brought in contact with a cation exchanger so that a uranium cation is removed from solution and ads... | 08/19/1986 |
| 4587109 | Process for the separate recovery of molybdenum and vanadium The invention relates to a process for recovering and purifying the molybdenum from a solution containing more molybdenum than vanadium. The process of the invention comprises the step of contacting the solution which contains molybdenum and vanadium, original... | 05/06/1986 |
| 4584184 | Separation and recovery of molybdenum values from uranium process waste A method for treating process waste consisting of uranium hexafluoride, UF6, molybdenum hexafluoride, MoF6 and molybdenum oxytetrafluoride, MoOF4 is provided wherein the foregoing mixture is hydrolyzed in an aqueous soluti... | 04/22/1986 |
| 4582688 | Process for recovery of mineral values The present invention relates to a process for the recovery of mineral values from ores containing such wherein at least part of the mineral values is present as a refractory mineral complex. A fluid bed reactor is utilized to simultaneously solubilize th... | 04/15/1986 |
| 4572581 | In-situ recovery of mineral values Mineral values, particularly uranium, are recovered from subsurface earth formations containing the same, as well as cations which form precipitates with sulfuric acid leach solutions, by injecting into at least one injection well a preliminary acidic sol... | 02/25/1986 |
| 4549985 | Waste disposal process Method for precipitating and removing soluble metal compounds from solutions of phosphoric acid. The method is useful in the disposal of metal-containing phosphoric acid waste from electrolytic operations, including such acid solutions contaminated with u... | 10/29/1985 |
| 4489042 | Process for recovery of mineral values from subterranean formations The present invention relates to the in situ recovery of mineral values, particularly uranium, from subterranean formations that contain sulfur in organic or inorganic forms where the sulfur causes premature deletion of an oxidant and reduction in permeab... | 12/18/1984 |
| 4476099 | Method of recovering uranium Uranium is recovered from a carbonate leach solution containing a dissolved uranium salt and a monovalent ion. The pH of the leach solution is adjusted to about 5 to about 7.5, and preferably to about 6 to about 7. Phosphate ion is then added to typical i... | 10/09/1984 |
| 4475772 | Process for recovering uranium and other base metals Uranium and other base metals are leached from their ores with aqueous solutions containing bicarbonate ions that have been generated or reconstituted by converting other non-bicarbonate anions into bicarbonate ions. The conversion is most conveniently ef... | 10/09/1984 |
| 4473255 | Magnesium bicarbonate as an in situ uranium lixiviant In the subsurface solution mining of mineral values, especially uranium, in situ, magnesium bicarbonate leaching solution is used instead of sodium, potassium and ammonium carbonate and bicarbonates. The magnesium bicarbonate solution is formed by combini... | 09/25/1984 |
| 4464345 | Method of precipitating contaminants in a uranium leachate using ferri ions, complexing agent, and pH control The present invention relates to a process for recovery of uranium from a carbonate lixiviant additionally containing other contaminants such as molybdenum and silica, by adjusting the pH of the lixiviant to a value of at least 4 and treating the lixivian... | 08/07/1984 |
| 4460547 | Separating actinide ions from aqueous, basic, carbonate containing solutions using mixed tertiary and quaternary amino anion exchange resins A process for the separation of actinide ions from aqueous, basic, carbonate containing solutions with the use of basic ion exchangers. The actinide ions are sorbed at a weakly basic anion exchanger comprised of a polyalkene matrix provided in the majorit... | 07/17/1984 |
| 4452490 | Treatment of subterranean uranium-bearing formations A process is described for improving yields and leaching rates of mineral values in highly reducing uranium-bearing formations, while minimizing deleterious environmental impact, by injecting an oxidant such as gaseous air or O2 into the format... | 06/05/1984 |
| 4451438 | Process for recovering niobium and/or tantalum metal compounds from such ores further containing complexes of uranium, thorium, titanium and/or rare earth metals A process for recovering one or more non-radioactive transition metal compounds from an ore containing one or more compounds of said transition metal or metals and further containing at least one complex of a member selected from the group consisting of u... | 05/29/1984 |
| 4451439 | Process for the purification of solutions containing a sodium or potassium carbonate, sulphate, and possibly hydroxide, and at least one of the metals vanadium, uranium and molybdenum A process for the purification of solutions containing sodium or potassium carbonate, sulphate, hydroxide or hydrogen carbonate, and mainly at least one of the metals belonging to the group formed by vanadium, uranium or molybdenum, in the form of sodium ... | 05/29/1984 |
| 4441993 | Flotation process A process for recovering metallic values by putting the values into solution and separating undesired mineral matter from the solution using countercurrent flotation is provided. The process involves leaching metallic values from host rock, conditioning t... | 04/10/1984 |
| 4438077 | Two stage selective oxidative leach method to separately recover uranium and refractory uranium-mineral complexes The present invention relates to a process for the recovery of uranium and other minerals from uranium ore where at least part of the uranium is present as refractory uranium-mineral complexes, comprising subjecting the uranium ore to mild oxidative carbo... | 03/20/1984 |
| 4436704 | Method of recovering uranium oxide from alkaline sodium uranyl carbonate solutions A method of recovering uranium dioxide from a sodium uranyl carbonate solution obtained by the alkaline carbonate leaching of uranium ore in which a solution is reacted at a temperature above 130° C. and at superatmospheric pressure with particular metal... | 03/13/1984 |
| 4427236 | In-situ uranium leaching The present invention relates to a method for improving the recovery of mineral values from ore bodies subjected to in-situ leaching by controlling the flow behavior of the leaching solution. Foam is introduced into the higher permeability zones of the or... | 01/24/1984 |
| 4423009 | Carbonate, sulphate and hydroxide or hydrogen carbonate Process for the purification of an aqueous solution containing alkali metal carbonate, sulphate, and hydroxide or hydrogen carbonate and primarily one at least of the metals belonging to the group formed by vanadium, uranium and molybdenum, in the form of... | 12/27/1983 |
| 4423010 | Process for the selective removal of arsenic in the course of the oxidizing attack by means of a carbonated liquor on a uraniferous ore containing same A process for the selective removal of arsenical materials, in the course of a continuous hot oxidizing attack process, comprising attacking a uraniferous ore containing arsenical materials as impurities in the presence of an oxidizing agent in the reacti... | 12/27/1983 |
| 4418042 | Ion exchange process using resins of high loading capacity, high chloride tolerance and rapid elution for uranium recovery The present invention relates to a process for effectively recovering uranium from dilute solutions, particularly alkaline carbonate leachates from an in-situ leaching process. The uranium complexes are made unstable by adjusting the pH of the leachate to... | 11/29/1983 |
| 4411873 | In-line regeneration of polythionate poisoned ion exchange resins A process is described for minimizing accumulation of undesirable polythionates on an ion exchange resin used to recover uranium values from a leachate from an in situ mining operation by adding sulfite, either as a sulfite salt or as SO2, dire... | 10/25/1983 |
| 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 ion exchange columns for removing uranium values from ura... | 10/18/1983 |
