Did You Know...
...that several people are credited with the invention of the flush toilet? Most people have heard of Thomas Crapper (1837-1910), the sanitary engineer who invented the valve-and-siphon arrangement that made the modern toilet possible. Another claimant to "the throne" was British inventor Alexander Cumming who patented a toilet in 1775. Then there's a nameless Minoan (a native of ancient Crete) who lived 4,000 years ago who supposedly was ahead of his time and created the first flush toilet!
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| Number | Title | Issue Date |
| 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 element (TRU) nuclides such as Pu, Np, Am, Cm, etc. from the spent nuclear... | 07/06/2010 |
| 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) phosphoric acid (D2EHPA) and tri-n-butyl phosphate (TBP) with refine... | 03/20/2007 |
| 6960311 | Radiation shielding materials and containers incorporating same An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (“PYRUC”) shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising m... | 11/01/2005 |
| 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 recovers valuable metals and semi-metal elements including rar... | 07/28/1998 |
| 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 |
| 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 hydrogen peroxide in an acid medium. During this precipitation,... | 02/21/1995 |
| 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.... | 01/28/1992 |
| 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 3, then adjusting the pH of the said solution to, and main... | 01/16/1990 |
| 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 a combustion shaft, which communicates with and verticall... | 10/03/1989 |
| 4793978 | Method and apparatus for producing uranyl peroxide (U04.2H.sub.2 O) from uranium and uranium alloy pieces A method and apparatus are provided for producing uranyl peroxide (UO4.2H.sub.2 O) from uranium-bearing metal pieces. The uranium-bearing metal pieces are dissolved in a first aqueous solution containing nitric acid and between 0.5% and 5.0% fl... | 12/27/1988 |
| 4701310 | Method and apparatus for producing uranyl peroxide (UO4.2H.sub.2 O) from uranium and uranium alloy pieces A method and apparatus are provided for producing uranyl peroxide (UO4.2H.sub.2 O) from uranium-bearing metal pieces. The uranium-bearing metal pieces are dissolved in a first aqueous solution containing nitric and fluoboric acids to provide a ... | 10/20/1987 |
| 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 composition against decomposition of said peroxide and th... | 01/13/1987 |
| 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 concentration of uranium between about 0.5 and 300 g/L and a hydr... | 07/23/1985 |
| 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 pH at an acid level which is suitable for the precipitation... | 01/31/1984 |
| 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 acidic eluant through the column without preconditioning a... | 12/27/1983 |
| 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 |
| 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 anion-exchange resin to capture the uranium and molybdenum va... | 03/01/1983 |
| 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 adding water glass to the liquid containing uranium and/or tho... | 07/06/1982 |
| 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 extraction with DEPA-TOPO followed by reductive stripping of the e... | 11/24/1981 |
| 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 reducing agent to produce uranium trioxide. The reaction be... | 11/24/1981 |
| 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 peroxide. A guard chamber is positioned in the elution circuit s... | 11/03/1981 |
| 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 solution and is supersaturated with calcium carbonate, is t... | 05/05/1981 |
| 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 fluoride complexing agent to produce an aqueous uranium solutio... | 03/24/1981 |
| 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 fluoride precipitating agent to produce an aqueous uranium solu... | 01/27/1981 |
| 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 pH of 1 - 2.5 with hydrogen peroxide, calcining of the pero... | 05/01/1979 |
| 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 in an amount sufficient to have an excess of at least 0.5... | 05/17/1977 |
| 3980757 | Process for uranium separation and preparation of UO4.2NH.sub.3.2HF 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) | 09/14/1976 |
