Class 252/640 - Free metal or metal compound component

Subclass of Class 252 - Compositions
Definition: Compositions wherein the nonactinide element containing
No. of patents: 28
Last issue date: 08/21/2007

Number	Title	Issue Date
7258722	Process for manufacturing ultra fine TiC-transition metal-based complex powder Any one of a Ti-containing water-soluble salt, metatitanic acid (TiO(OH)2) slurry and ultra fine titanium oxide powder, and a transition metal containing metal salt are dissolved in water to prepare a raw material mixture. The raw material is spray-dried ...	08/21/2007
7153340	Process for manufacturing nano-phase TaC-transition metal based complex powder Ultra fine TaC-transition metal based complex powder is prepared by: dispersing a mixture of a Ta-containing material and a transition metal-containing water soluble salt into a solvent; stirring the mixture and spray-drying the stirred material to obtain precursor ...	12/26/2006
7101822	Method for decontaminating solid iodine filters The invention relates to a process for decontaminating solid iodine filters containing silver iodide, silver iodate and/or physisorbed molecular iodine. This process consists in placing the filter in contact with an aqueous solution of a reducing agent chosen...	09/05/2006
7078581	Encapsulation of waste A ceramic waste immobilizing material for the encapsulation of high level radioactive waste (HLW), e.g. resulting from the reprocessing of irradiated nuclear fuel. The ceramic waste immobilising material enables waste ions from at least fission products in irradiate...	07/18/2006
6973154	Method of chemical decontamination and system therefor In a chemical decontamination method of chemically decontaminating radioactive nuclides from a metallic material, oxalic acid and hydrazine are injected as a reductive decontaminating agent into water that is in contact with the metallic material. Injection of the h...	12/06/2005
6413923	Non-corrosive cleaning composition for removing plasma etching residues A non-corrosive cleaning composition for removing residues from a substrate. The composition comprises: (a) water; (b) at least one hydroxylammonium compound; (c) at least one basic compound, preferably selected from the group consisting of amines and qua...	07/02/2002
5999585	Nuclear fuel having improved fission product retention properties A nuclear fuel based on UO2, ThO2 and/or PuO2 having improved retention properties for fission products. The fuel comprises a metal such as Cr or Mo able to trap oxygen in order to form an oxide having a free formation ent...	12/07/1999
5841200	Process for the production of nuclear fuel pellets based on mixed (U, Pu)O₂ oxide with the addition of an organic, sulphur product Process for the production of nuclear fuel pellets based on mixed uranium and plutonium oxide having a specific plutonium content from a charge of UO2 and PuO2 powders by lubrification, pelletizing and sintering, in which a solid, su...	11/24/1998
5642390	Uranium-containing nuclear-fuel sintered pellet A uranium-containing nuclear-fuel sintered pellet containing UO2, (U, Pu)O2, (U, Th)O2, (U, RE)O2, (U, Pu, Th)O2, (U, Pu, RE)O2, (U, Th, RE)O2 or (U, Pu, Th, RE)O2, wherein...	06/24/1997
5473648	Decontamination process The present invention relates to a process of decontaminating zirconium-based alloy claddings tubes used in nuclear reactor fuel rods. The process involved the use of a permanganate in a dilute acid solution. The process renders the alloy suitable for unc...	12/05/1995
5419886	Method for generation of finely divided reactive plutonium oxide powder A method of preparing active, sinterable, finely-divided plutonium oxide (PuO2) powder from plutonium metal is disclosed. The process yields plutonium fissile material which can be easily blended to form a uniformly homogeneous powder for the f...	05/30/1995
5188130	Chemical heat source comprising metal nitride, metal oxide and carbon A chemical heat source comprising metal nitride, metal oxide and carbon, particularly useful in smoking articles, and methods of making the heat source are provided. The metal nitride of the heat source has an ignition temperature substantially lower than...	02/23/1993
5112534	Yttrium and rare earth stabilized fast reactor metal fuel To increase the operating temperature of a reactor, the melting point and mechanical properties of the fuel must be increased. For an actinide-rich fuel, yttrium, lanthanum and/or rare earth elements can be added, as stabilizers, to uranium and plutonium ...	05/12/1992
4997596	Fissionable nuclear fuel composition The disclosed invention consists of a ceramic form of fuel for a nuclear reactor comprising an oxide of a fissionable element and containing therein a consumable neutron absorbing agent. The ceramic fissionable fuel product provides longer fuel performanc...	03/05/1991
4891192	Process for the purification of traces of radioactive elements generated during the storage of uranium resulting from the reprocessing of irradiated nuclear fuels Process for the purification of reprocessing uranium from which have previously been separated the fission products generated in a nuclear reactor and consisting of eliminating the U232 daughter products appearing during storage, by passing said uranium i...	01/02/1990
4634571	Process for the production of plate-shaped fuel elements for research reactors For the production of plate-shaped fuel elements for research reactors having charges of more than 26 volume % of uranium compound in the aluminum matrix according to the known picture frame technique, 0.01 to 0.3 mm thick aluminum layers are applied by r...	01/06/1987
4624828	Metal-actinide nitride nuclear fuel The invention discloses a metal-actinide mononitride composition with dimensional stability in extended nuclear reactor operations, with a method of operation at surface temperatures in excess of 1700° C. The preferred embodiment and operating method use...	11/25/1986
4430276	Method of making stable UO₂ fuel pellets A method is disclosed for producing a dimensionally stable UO2 fuel pellet of large grain mole %, and relatively large pore size. A dopant containing an element selected from the group consisting of aluminum, calcium, magnesium, titanium, zirco...	02/07/1984
4383855	Cermets and method for making same The present invention is directed to a method for making a wide variety of general-purpose cermets and for radioactive waste disposal from ceramic powders prepared from urea-dispersed solutions containing various metal values. The powders are formed into ...	05/17/1983
4278560	Method for manufacturing gadolinium-containing nuclear fuels Mixed crystals containing uranium and gadolinium for conversion into nuclear fuels by introducing NH3, CO2 and a uranyl salt solution containing dissolved gadolinium into a body of an aqueous solution of ammonium carbonate. As a resu...	07/14/1981
4216110	Method of making crack-free zirconium hydride Crack-free hydrides of zirconium and zirconium-uranium alloys are produced by alloying the zirconium or zirconium-uranium alloy with beryllium, or nickel, or beryllium and scandium, or nickel and scandium, or beryllium and nickel, or beryllium, nickel and...	08/05/1980
4189398	Nuclear fuel composition 1. A high temperature graphite-uranium base nuclear fuel composition containing from about 1 to about 5 five weight percent rhenium metal....	02/19/1980
4162230	Method for the recovery of actinide elements from nuclear reactor waste A process for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to the waste solution to adjust the valence of the neptunium and...	07/24/1979
4097402	Nuclear fuel assembly and process Rupture of boiling water reactor nuclear fuel cladding resulting from embrittlement caused by fission product cadmium is prevented by adding the stoichiometrically equivalent amount of gold, silver or palladium to the fuel....	06/27/1978
4071587	Method of making ZrH fuel element A method of making a nuclear fuel element for a fission reactor. A solid body of an alloy of zirconium and nuclear fuel metal is exposed to hydrogen at an elevated temperature to hydride the zirconium. The hydrided alloy is exposed to oxygen at a lower te...	01/31/1978
4059539	(U,Zr)N alloy having enhanced thermal stability A nitrided alloy of uranium and zirconium is provided which consists of a single-phase UN structure containing a dissolved amount of Zr as ZrN, effective to inhibit dissociation of the UN phase....	11/22/1977
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
3940312	Nuclear fuel and process of preparation thereof Vanadium carbide is present in the particles as supersaturated solid solution and the particles are coated with a thin porous layer of vanadium carbide....	02/24/1976

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Class 252/640 - Free metal or metal compound component