Mouthguard made at least partially from an edible candy
A mouthguard includes a U-shaped upper bite plate which removably fits over upper teeth of a person, with the entire upper bite plate being made from a soft, deformable and edible gummi candy.
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| Number | Title | Issue Date |
| 7195745 | Method of preparing a product based on phosphate of thorium and/or actinide(s) The invention relates to a process for the preparation of a product based on a phosphate of at least one element M(IV), for example of thorium and/or of actinide(IV)(s). This process comprises the following stages: a) mixing... | 03/27/2007 |
| 7187744 | Method of providing a nuclear fuel and a fuel element provided by such a method A method for providing a nuclear fuel includes forming a uranium-molybdenum alloy that provides an enhanced reactivity in research, test and radioisotope production nuclear reactors. In this uranium-molybdenum alloy, the uranium is enriched in the isotope 235-U, whi... | 03/06/2007 |
| 7182926 | Process for separating and recovering valuable metals A process for economically separating and recovering valuable metal components, with few kinds of chemicals being used, with no waste water that causes environmental pollution being discharged, and also perfectly no by-products being formed by means of simple steps.... | 02/27/2007 |
| 7169370 | Method for co-precipitating actinides and method for preparing mixed actinide oxides The present invention generally relates to the preparation of mixed actinide oxides, such as mixed oxides of uranium and plutonium (U, Pu) O2, by simultaneously coprecipitation and then calcinations. ... | 01/30/2007 |
| 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 |
| 5213777 | Process for the recovery of metals Metal values (especially uranium values) are extracted from aqueous solutions of metal oxyions in the absence of halogen ion using an imidazole of defined formula. Especially preferred extractants are 1-alkyl imidazoles and benzimidazoles having from 7 to... | 05/25/1993 |
| 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 |
| 5035840 | Process for cleaning trace metals from EDTA A process for removing metal salts from an H4 EDTA precipitate by esterification with an esterification reagent to produce an esterification mixture comprising a solid metal salt an EDTA ester and thereafter separating the solid metal salt from... | 07/30/1991 |
| 5015422 | UO2 pellet fabrication process Making uranium dioxide pellets of controlled grain size by treating 50-500 g/l UO2 F2 with NH3 in a first and a second stages to form (NH4)2 U2 O7 precipitate, wherein the NH3 | 05/14/1991 |
| 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 |
| 4873031 | Method of controlling the crystal grain size of uranium dioxide pellet A method of controlling the crystal grain size of UO2 pellets is disclosed, which comprises (1) providing an aqueous uranyl solution which is free of hydrofluoric acid and nitric acid and which contains uranyl fluoride (UO2 F2)... | 10/10/1989 |
| 4839149 | Ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O2 The invention relates to an ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O2. The ammonium plutonate uranate of formula [Cu,Pu)O3 ]2 [NH3 ]x [H2 | 06/13/1989 |
| 4832924 | Process for producing uranium oxides The present invention provides a process for producing a uranium oxide by dissolving a yellow cake in sulfuric acid or hydrochloric acid, bringing the obtained solution into contact with a chelating resin of diaminocarboxylic acid type and subjecting the ... | 05/23/1989 |
| 4749453 | Method and apparatus for making hydrochloric acid and sodium hydroxide By combining the manufacture of sodium hydroxide and hydrochloric acid, and by using a fuel cell to optimize the energy consumption, the energy efficiency of the manufacture of NaOH and HCl can be improved by at least about 33%. Electrical energy produced... | 06/07/1988 |
| 4744960 | Process for the separation of rare earths and uranium of a UF4 concentrate and for putting them into useful form The present invention relates to a proces for separating rare earths and uranium from a UF4 concentrate and for placing them into useful form, comprising attacking the UF4 concentrate with potassium hydroxide, followed by nitric acid... | 05/17/1988 |
| 4681705 | Decontamination of radioactively contaminated liquids A method of decontaminating mixtures of radioactively contaminated water and radioactively contaminated water-immiscible organic liquids to produce a decontaminated organic liquid which can be disposed of in a conventional manner. The method comprises sep... | 07/21/1987 |
| 4675166 | Process for the selective separation of uranium, zirconium and/or hafnium and/or molybdenum from a carbonated aqueous solution containing same Process for the selective separation of uranium in carbonated aqueous solution from soluble impurities including in particular at least one of the elements zirconium and/or hafnium and/or molybdenum, thereby making it possible to produce a uraniferous liq... | 06/23/1987 |
| 4671904 | Method for producing oxidic sintered nuclear fuel bodies UO2 base powder exhibiting any specific surface and crystallite diameter properties is mixed with rare earth (SE) oxide-containing powder, the particles of which exhibit at least in one surface layer, a crystal lattice of the fluorite type, wit... | 06/09/1987 |
| 4668482 | Recovery of uranium from solutions For the recovery of uranium from a solution in which the uranium is in valence (VI), a solution is formed containing ammonium (NH4+), fluoride (F-) and sodium hydrosulfite (Na2 S2 O4). This... | 05/26/1987 |
| 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 |
| 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 |
| 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 |
| 4565672 | Method for the manufacture of PuO2 -containing crystals A method for manufacturing Pu2 -containing crystals by oxidizing plutonium in a heavily contaminated nitric acid starting solution to Pu6+, precipitating ammonium plutonyl carbonate containing crystals by reaction with ammonium- and ... | 01/21/1986 |
| 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 |
| 4536034 | Method for immobilizing contaminants in previously leached ores This invention relates to a process for reducing to environmentally acceptable levels the amount of soluble or mobile contaminants in formations that have been subjected to in situ leaching to recover mineral values therefrom. The present process is also ... | 08/20/1985 |
| 4514365 | Process for recovering a uranium-containing concentrate and purified phosphoric acid from a wet process phosphoric acid containing uranium A process for recovering from a wet process phosphoric acid which contains uranium, a uranium containing concentrate and a purified phosphoric acid. The wet process phosphoric acid is treated with a precipitant in the presence of a reducing agent and an a... | 04/30/1985 |
| 4512939 | Method for manufacturing oxidic sintered nuclear fuel bodies Method for the manufacture of oxidic sintered nuclear fuel bodies by compacting UO2 -starting powder or a mixture of UO2 -and PuO2 starting powder which contains up to 10% by weight rare-earth oxide, especially Gd2 | 04/23/1985 |
| 4485075 | Process for the extraction of arsenic from aqueous solutions containing alkali metal carbonate, sulfate and hydroxide or hydrogen carbonate and at least on metal including vanadium, uranium and molybdenum A process for extracting arsenic from aqueous solutions containing alkali metal carbonate, sulfate and hydroxide or hydrogen carbonate, at least one metal selected from the group consisting of vanadium, uranium and molybdenum in the form of an alkali meta... | 11/27/1984 |
| 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 |
| 4476101 | Producing ammonium uranate in spherical particulate form A novel easily handled substantially particulate ammonium uranate with a mean diameter between 30 and 150 micrometers, an apparent untamped bulk density of 2 to 2.8 g/cm3, and a flowability measured on the Carr scale equal to or greater than 95... | 10/09/1984 |
| 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 |
| 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 |
| 4432947 | Process for obtaining molybdenum as a useful product from molybdeniferous solutions containing alkali metal carbonate, sulphate, hydroxide or hydrogen carbonate and possibly uranium A process for obtaining molybdenum as a useful product from aqueous solutions to be purified, according to claim 1 of French patent No. 2 404 601, which contain, besides said molybdenum, alkali metal carbonate, sulphate, hydroxide or hydrogen carbonate an... | 02/21/1984 |
| 4430309 | Acid wash of second cycle solvent in the recovery of uranium from phosphate rock Entrainment of contaminated water in the organic phase and poor phase disengagement is prevented in the second cycle scrubber, in a two cycle uranium recovery process, by washing the organic solvent stream containing entrained H3 PO4... | 02/07/1984 |
| 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 |
| 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 |
| 4409157 | Method for improved decomposition of metal nitrate solutions A method for co-conversion of aqueous solutions of one or more heavy metal nitrates wherein thermal decomposition within a temperature range of about 300° to 800° C. is carried out in the presence of about 50 to 500% molar concentration of ammonium nitr... | 10/11/1983 |
| 4407781 | Method of separating molybdenum from uranium A method is disclosed for separating uranium from molybdenum in an aqueous solution. The pH of the solution is lowered to about 1 to about 4 using an inorganic acid such as hydrochloric acid. The carbon dioxide is then removed from the solution which can ... | 10/04/1983 |