Bizarre Patents
Mountable Printable Placard With Headband
A resilient headband in a shape for being mounted on the head of the user. The headband is equipped with a longitudinal slotted member for holding a placard.
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| Number | Title | Issue Date |
| 7326346 | High capacity regenerable sorbent for removal of arsenic and other toxic ions from drinking water The present invention is directed to a sorbent comprising a disordered polyvalent metal oxide on the surface of an inert substrate. The substrate can be a layered silicate, such as vermiculite, an aluminosilicate such as montmorillonite, or a nonlayered silicate suc... | 02/05/2008 |
| 7183235 | High capacity regenerable sorbent for removing arsenic and other toxic ions from drinking water The present invention is directed to a sorbent comprising a disordered polyvalent metal oxide on the surface of an inert substrate. The substrate can be a layered silicate, such as vermiculite, an aluminosilicate such as montmorillonite, or a nonlayered silicate suc... | 02/27/2007 |
| 7063793 | Apparatus and method for removing mercury and mercuric compounds from dental effluents The present invention is directed to processes for removing a contaminant from dental effluents and includes transporting a three-phase effluent through a suction line into a particle collection vessel, introducing a suction line cleaning solution which includes a r... | 06/20/2006 |
| 7048781 | Chemically-impregnated silicate agents for mercury control The present invention is directed to a contaminant removal agent comprising a polyvalent metal sulfide on the surface of an inert substrate. The substrate can be a layered silicate, such as vermiculite, an aluminosilicate such as montmorillonite, or a nonlayered sil... | 05/23/2006 |
| 6960326 | Method of separating uranium from irradiated nuclear fuel The invention provides a method of separating uranium from at least fission products in irradiated nuclear fuel, said method comprising reacting said irradiated nuclear fuel with a solution of ammonium fluoride in hydrogen fluoride fluorinating said reacted irradiat... | 11/01/2005 |
| 6942840 | Method for removal and stabilization of mercury in mercury-containing gas streams The present invention is directed to a process and apparatus for removing and stabilizing mercury from mercury-containing gas streams. A gas stream containing vapor phase elemental and/or speciated mercury is contacted with reagent, such as an oxygen-containing oxid... | 09/13/2005 |
| 6911570 | Method for fixating sludges and soils contaminated with mercury and other heavy metals The invention relates to a method, composition and apparatus for stabilizing mercury and other heavy metals present in a particulate material such that the metals will not leach from the particulate material. The method generally involves the application of a metal ... | 06/28/2005 |
| 6379634 | Ionic liquids as solvents A method of dissolving in an ionic liquid a metal in an initial oxidation state below its maximum oxidation state, characterized in that the ionic liquid reacts with the metal and oxidizes it to a higher oxidation state. The initial metal may be in the fo... | 04/30/2002 |
| 6231683 | Method for cleaning radioactively contaminated material Radioactively contaminated material is cleaned by contacting the material with a decontaminating liquid comprising an aqueous solution of nitric acid containing an NOx generating agent. The NOx generating agent may be a nitrite, for example, sodium nitrit... | 05/15/2001 |
| 5686052 | Process for the treatment of nuclear targets and/or fuels based on metallic aluminium by tetramethylammonium hydroxide solutions The invention relates to a process for the processing of nuclear targets and/or fuels based on metallic aluminium by dissolving with the aid of aqueous tetramethylammonium hydroxide (TMAOH) solutions. Dissolving can consist of a total dissolving in a single st... | 11/11/1997 |
| 5008044 | Process for decontaminating radioactively contaminated metal or cement-containing materials Contaminated surface layers are decontaminated by treatment with an aqueous fluorine base-containing decontamination solution. The aqueous decontamination solution contains 0.05 to 50 Mol of decontamination agent per liter, and the decontamination agent p... | 04/16/1991 |
| 5000927 | Method of regulating a purex solvent extraction process The "Purex" solvent extraction and separation process for recovering uranium from scrap material or spent fuel containing gadolinia is modified by treating uranium containing scrap or spent fuel with nitric acid to convert uranium oxide to soluble uranyl ... | 03/19/1991 |
| 4933113 | Process for the processing of contaminated boric acid Contaminated surface layers are decontaminated by treatment with an aqueous fluorine base-containing decontamination solution. The aqueous decontamination solution contains 0.05 to 50 Mol of decontamination agent per liter, and the decontamination agent p... | 06/12/1990 |
| 4830738 | Separation of matter by floatation Matter is floated to the surface of a liquid by bonding ions to the surface of the matter to give the matter a charge, and forming a froth with the aid of a frothing agent having groups of opposite charge to the ions so that the frothing agent bonds to th... | 05/16/1989 |
| 4828759 | Process for decontaminating radioactivity contaminated metallic materials Contaminated surface layers are decontaminated by treatment with an aqueous fluorine base-containing decontamination solution. The aqueous decontamination solution contains 0.05 to 50 Mol of decontamination agent per liter, and the decontamination agent p... | 05/09/1989 |
| 4769222 | Method of dissolving nuclear material from a nuclear fuel cartridge A method of dissolving nuclear material from a relatively long length cut from a nuclear fuel cartridge and having a liquid permeable passageway extending from one end to the other end of the cut length. The method comprises holding the cut length upright... | 09/06/1988 |
| 4764228 | Method for preparing hydride configurations and reactive metal surfaces A method for preparing highly hydrogen-reactive surfaces on metals which normally require substantial heating, high pressures, or an extended induction period, which involves pretreatment of said surfaces with either a non-oxidizing acid or hydrogen gas t... | 08/16/1988 |
| 4687600 | Process for the separation of coated nuclear fuel particles from a graphitic matrix and installation for implementing the process A treating process for the separation of coated nuclear fuel particles from a graphitic matrix in which the nuclear fuel particles are embedded, which is employed in an installation for the conditioning of graphitic fuel elements of high-temperature nucle... | 08/18/1987 |
| 4521400 | Agitator apparatus Apparatus for agitating and circulating a liquid 20 comprising a vessel having two upright chambers 10, 12 and two vertically displaced ducts 14, 18 connecting the chambers 10, 12. In use of the apparatus, a steady flow of gas into the top of one chamber ... | 06/04/1985 |
| 4514364 | Method for reprocessing a nuclear reactor fuel rod Reprocessing a nuclear reactor fuel rod which contains nuclear fuel in a cladding tube, by removing the cladding tube from the nuclear fuel. The cladding tube is uniformly heated in hermetically sealed condition together with the nuclear fuel contained th... | 04/30/1985 |
| 4507267 | Heat-aided method for separating the graphite matrix from the nuclear fuel of nuclear reactor fuel elements Removal of the graphite structure from the nuclear fuel material of fuel elements of gas-cooled high-temperature reactors is performed by heat-treatment of the fuel elements in oxygen-containing gas at temperatures below 700° C. until the carbon or graph... | 03/26/1985 |
| 4507227 | Comminuting irradiated ferritic steel Disclosed is a method of comminuting irradiated ferritic steel by placing the steel in a solution of a compound selected from the group consisting of sulfamic acid, bisulfate, and mixtures thereof. The ferritic steel is used as cladding on nuclear fuel ro... | 03/26/1985 |
| 4461650 | Method for removing scale from nuclear fuel rods A neclear fuel rod assembly used in a nuclear reactor and deposited with radioactive scale is taken out of a fuel pool and disposed in a substantially sealed vertical casing, while the scale is still wetted by water. Gas in the casing is heated to a tempe... | 07/24/1984 |
| 4392995 | Molten tin reprocessing of spent nuclear fuel elements A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an... | 07/12/1983 |
| 4296074 | Method of decladding A method of decladding an assembly comprising an element selected from the group consisting of uranium, thorium and mixtures thereof, clad in stainless steel, zirconium, or an alloy consisting essentially of zirconium and containing minor amounts of nicke... | 10/20/1981 |
| 4294805 | Method of leaching the contents of a can A method of leaching a material from a cavity having a closed or a partially closed top. The method consists of subjecting the liquid to a number of pressure cycles, each pressure cycle involving a decrease in pressure to cause boiling of the liquid, foll... | 10/13/1981 |
| 4278559 | Method for processing spent nuclear reactor fuel A method and apparatus for processing spent nuclear reactor fuel wherein plutonium is continuously contaminated with radioactive fission products and diluted with uranium. Plutonium of sufficient purity to fabricate nuclear weapons cannot be produced by t... | 07/14/1981 |
| 4248836 | Recovery of nuclear fuel material Irradiated nuclear fuel is separated from the protective metal sheath in which it is enclosed by treating the sheath with an embrittling agent which effects embrittlement of the sheath, breaking up the sheath and separating the nuclear fuel material from ... | 02/03/1981 |
| 4230672 | Apparatus for recovering nuclear fuel from scrap material Process for recovering compounds of enriched nuclear fuel from scrap materials is disclosed. The process yields an acid solution with the nuclear fuel dissolved therein. Except for spent filter media, the scrap materials are calcined to produce an oxidize... | 10/28/1980 |
| 4228141 | Process for a gasification of graphite A graphite can be easily and completely gasified by soaking the graphite in a catalyst solution of a nitrate of a gasification catalyst selected from the group consisting of cobalt, nickel and iron and nitric acid to impregnate the graphite with the gasif... | 10/14/1980 |
| 4201690 | Processing of irradiated nuclear fuel Irradiated nuclear fuel is dissolved in nitric acid under a carbon dioxide atmosphere which is treated to remove iodine, krypton and xenon and recycled.... | 05/06/1980 |
| 4180476 | Process for the extraction of fission products Process for the extraction of fission products contained in irradiated nuclear fuel elements which have been subject to a temperature of at least 1200° C. during their irradiation prior to dissolving the fuel by the wet process. After mechanically treati... | 12/25/1979 |
| 4177241 | Apparatus and process for recovering nuclear fuel from scrap material A process for recovering compounds of enriched nuclear fuel from scrap materials is disclosed. The process yields an acid solution with the nuclear fuel dissolved therein. Except for spent filter media, the scrap materials are calcined to produce an oxidi... | 12/04/1979 |
| 4174369 | Fluid pressure method for recovering fuel pellets from nuclear fuel elements Method for removing fuel pellets from a nuclear fuel element without damaging the fuel pellets or fuel element sheath so that both may be reused. The method comprises holding the fuel element while a high pressure stream internally pressurizes the fuel el... | 11/13/1979 |
| 4024068 | Process for separating ceramics of uranium and plutonium from zirconium by hydriding and mixtures thereof A process is provided involving the use of hydrogen for the separation of uranium and plutonium and mixtures thereof, from composite substances and assemblies or mixtures containing metallic and ceramic components where the metallic component is zirconium... | 05/17/1977 |
| 4022865 | Process for working up block shaped graphite fuel elements There is provided a process for recovering block shaped graphite fuel elements made of a graphite block with a parallel cooling channel and which block contains the fuel arranged in separate zones. The process is especially useful for such fuel elements i... | 05/10/1977 |
| 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 mineral acid forming an aqueous dissolved nuclear fuel solutio... | 03/08/1977 |
| 4000039 | Fuel elements for high temperature reactors having special suitability for reuse of the structural graphite There are prepared fuel elements for high temperature reactors from which the fuel zone can be removed from the structural graphite after the burnup of the fissile material has taken place so that the fuel element can be filled with new fuel and again pla... | 12/28/1976 |
| 3984519 | Process to transport carbon from a zone to another one, by means of a carrier fluid acting inside a closed system, particularly for the reprocessing of nuclear fuel elements having a graphite structure A method is disclosed for eliminating carbon from nuclear fuel elements in the reprocessing thereof in a closed system wherein such carbon is caused to combine with hydrogen to form methane in an attack zone, and the methane is then caused to flow from th... | 10/05/1976 |
| 3967958 | Method of winning copper, nickel, and other metals The invention is a process for winning nickel by treating an aqueous ammonium salt solution of nickel salts with a carbon monoxide-containing gas under reducing conditions to produce nickel carbonyl and subsequently recovering nickel therefrom. Optionally... | 07/06/1976 |
