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| Number | Title | Issue Date |
| 7521007 | Methods and apparatuses for the development of microstructured nuclear fuels Microstructured nuclear fuel adapted for nuclear power system use includes fissile material structures of micrometer-scale dimension dispersed in a matrix material. In one method of production, fissile material particles are processed in a chemical vapor deposition ... | 04/21/2009 |
| 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 |
| 7139360 | Use of boron or enriched boron 10 in UO The present invention provides a nuclear fuel assembly, where a boron-containing compound is used as a burnable poison and is distributed in a majority of the rods in the assembly. The assembly comprises a plurality of fuel rods, each fuel rod containing a plurality... | 11/21/2006 |
| 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 |
| 6669874 | Method for production of and material adapted to be sintered to a nuclear fuel element with oxide base A method for production of a nuclear fuel element with oxide base, in which the nuclear fuel with oxide base is mixed with Cr and sintered to a solid body. The amount of chrome oxide added is =>50 and | 12/30/2003 |
| 6625248 | Process for the treatment of radioactive graphite A process for the treatment of radioactive graphite which includes the following steps: (i) reacting the radioactive graphite at a temperature in the range of from 250° C. to 900° C. with superheated steam or gases containing water vapor to form hydroge... | 09/23/2003 |
| 6235223 | Method for producing a sintered nuclear fuel body A sintered nuclear fuel body includes (U, Pu)O2 mixed crystals having a mean particle size in a range from 7.5 μm to 50 μm. This sintered nuclear fuel body has a high retention capacity for fission gas in a power reactor. In order to produce ... | 05/22/2001 |
| 5935528 | Multicomponent fluid feed apparatus with preheater and mixer for a high temperature chemical reactor A multicomponent fluid feed apparatus is disclosed that independently preheats and then mixes two or more fluid streams being introduced into a high temperature chemical reactor to promote more rigorous and complete reactions using assemblies of inert tub... | 08/10/1999 |
| 5894501 | Sintered nuclear fuel body and method for producing a sintered nuclear fuel body A sintered nuclear fuel body includes (U, Pu)O2 mixed crystals having a mean particle size in a range from 7.5 μm to 50 μm. This sintered nuclear fuel body has a high retention capacity for fission gas in a power reactor. In order to produce ... | 04/13/1999 |
| 5753925 | Radioactive waste storage facility Horizontal partition wall 10 is disposed between ceiling slab 9 and floor slab 8. A plurality of storage tubes 6 each accomodating canister 2 are hanging from ceiling slab 9, and penetrate horizontal wall 10 to extend towards floor slab 8. Cooling passage... | 05/19/1998 |
| 5585043 | Method of coextracting neptunium and plutonium In a method of coextracting neptunium and plutonium, a nitric acid solution containing a mixture of neptunium and plutonium is oxidized by irradiation of ultraviolet light. As a result, different valences of neptunium are adjusted all into the valence 6, ... | 12/17/1996 |
| 5443702 | Laser isotope separation of erbium and other isotopes Laser isotope separation is accomplished using at least two photoionization pathways of an isotope simultaneously, where each pathway comprises two or more transition steps. This separation method has been applied to the selective photoionization of erbiu... | 08/22/1995 |
| 5350542 | Nuclear fuel with isotopically depleted burnable absorber By using AVLIS or other methods capable of providing a depleted isotopic mixture, troublesome isotopes such as Gd154, Gd156 and Er166 are selectively removed from naturally occurring isotopic mixtures, while avoiding the a... | 09/27/1994 |
| 5349618 | BWR fuel assembly having oxide and hydride fuel A boiling water nuclear reactor used for the production of electricity includes fuel rods and an assembly of these fuel rods that improve the reactor economics and safety. The fuel assemblies include hydride fuel pellets at selected axial and radial posit... | 09/20/1994 |
| 5250231 | Nuclear fuel with isotopically depleted burnable absorber By using AVLIS or other methods capable of providing a depleted isotopic mixture, troublesome isotopes such as Gd154, Gd156 and Er166 are selectively removed from naturally occurring isotopic mixtures, while avoiding the a... | 10/05/1993 |
| 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 |
| 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 |
| 4963294 | Method of preparing uranium dioxide powder from uranium hexafluoride A method of fabricating uranium dioxide (UO2) powder from uranium hexafluoride (UF6) is disclosed, which comprises (1) reacting UF6 gas with steam with controlling the temperature of reaction between said UF6 gas and... | 10/16/1990 |
| 4885147 | Process for preparing a large-grained UO2 fuel A process for producing large-grain, low-density UO2 micro-fuel spheres, the micro-fuel spheres having an average grain diameter of at least 5 μm, which comprises: (a) isothermally heating one or more UO2 micro-fuel spheres in a str... | 12/05/1989 |
| 4882100 | Uo2 pellet fabrication process A process of fabricating UO2 pellets comprising the steps of filtering and drying a slurry of ammonium diuranate (ADU) including ammonium fluoride (NH4 F), in order to form ADU powder, and then subjecting the ADU powder to calcining,... | 11/21/1989 |
| 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 |
| 4871479 | Process for producing sintered mixed oxides which are soluble in nitric acid from solutions of nitrates A process is disclosed for producing sintered mixed metal oxide nuclear f pellets containing UO2 and the oxide of at least one other fissionable or rare earth element M, the pellets being directly soluble in nitric acid without nitric acid add... | 10/03/1989 |
| 4869868 | Nuclear fuel A particulate mixture of uranium dioxide and additive of magnesium silicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein ... | 09/26/1989 |
| 4869866 | Nuclear fuel A mixture of uranium dioxide and additive of aluminosilicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and wherein substantially a... | 09/26/1989 |
| 4869867 | Nuclear fuel A particulate mixture of uranium dioxide and additive of magnesium aluminosilicate composition is formed into a compact and sintered to produce a nuclear fuel wherein the uranium dioxide grains have an average grain size of at least about 20 microns and w... | 09/26/1989 |
| 4816193 | Method for the manufacture of oxide sintered nuclear fuel bodies Method for manufacturing sintered oxidic nuclear fuel bodies by molding uranium oxide starting powder, a mixture of uranium oxide and plutonium oxide starting powder or of uranium-plutonium oxide mixed-crystal starting powder to form blanks and by a heat ... | 03/28/1989 |
| 4687605 | Manufacturing automation system for nuclear fuel rod production An automated fuel rod production system includes a radioactive powder fabrication and processing stage, a pellet fabrication stage, a pellet processing stage, a tube preparation stage and a fuel rod fabrication and inspection stage, all of which provide a... | 08/18/1987 |
| 4671927 | Nuclear fuel rod containing a hybrid gadolinium oxide, boron carbide burnable absorber A nuclear fuel rod contains nuclear fuel pellets that have incorporated therein a hybrid burnable absorber that affects a moderation of the burn-out rate of the system containing the rod. The nuclear fuel pellets contain 1 to 20 percent by weight gadolini... | 06/09/1987 |
| 4637900 | Fabrication of high exposure nuclear fuel pellets A method is disclosed for making a fuel pellet for a nuclear reactor. A mixture is prepared of PuO2 and UO2 powders, where the mixture contains at least about 30% PuO2, and where at least about 12% of the Pu is the Pu... | 01/20/1987 |
| 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 |
| 4557861 | Nuclear fuel cartridge, and a method of preparing the cartridge for the extraction of nuclear material therefrom A nuclear fuel cartridge comprises a sheath, and nuclear material inside the sheath. A continuous liquid permeable passageway extends from one end of the nuclear material to the other, and an annular end member is disposed at each end of the nuclear mater... | 12/10/1985 |
| 4493792 | Method and apparatus for minimizing diversion of radioactive samples from a nuclear fuel sampling system Method and apparatus for minimizing diversion of radioactive samples from a nuclear fuel sampling system. The apparatus includes a sampler for drawing a radioactive sample from a remote vessel containing nuclear fuel. The sampler is located within a shiel... | 01/15/1985 |
| 4493809 | Uranium thorium hydride nuclear fuel A nuclear fuel includes uranium dispersed within a thorium hydride matrix. The uranium may be in the form of particles including fissile and non-fissile isotopes. Various hydrogen to thorium ratios may be included in the matrix. The matrix with the fissil... | 01/15/1985 |
| 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 |
| 4367184 | Mixed uranium dicarbide and uranium dioxide microspheres and process of making same Nuclear fuel microspheres are made by sintering microspheres containing uranium dioxide and uncombined carbon in a 1 mole percent carbon monoxide/99 mole percent argon atmosphere at 1550° C. and then sintering the microspheres in a 3 mole percent carbon ... | 01/04/1983 |
| 4366112 | Solid evacuated microspheres of hydrogen A method is provided for producing solid, evacuated microspheres comprised of hydrogen. The spheres are produced by forming a jet of liquid hydrogen and exciting mechanical waves on the jet of appropriate frequency so that the jet breaks up into drops wit... | 12/28/1982 |
| 4349453 | Method for processing alkaline solutions containing radioactive iodine during reprocessing of nuclear fuels The method of processing alkaline solutions containing radioactive iodine consists in dissolving irradiated fuels in a nitric acid solution. The vapors constituted essentially by nitrogen oxides, iodine and water formed during dissolution are passed into ... | 09/14/1982 |
| 4304645 | Process for removing helium and other impurities from a mixture containing deuterium and tritium, and a deuterium/tritium mixture when purified in accordance with such a process A process for removing helium and other impurities from a mixture containing deuterium and tritium, which process comprises the steps of: separating from the mixture isotopes of hydrogen in any of their diatomic combined forms; oxidizing the separated iso... | 12/08/1981 |
| 4290847 | Multishell microcapsules Smooth-surfaced, free-flowing, rigid, spherical, hollow microcapsules having non-porous shell walls consisting of essentially homogeneous, non-vitreous metal oxide in predominantly polycrystalline state, which have at least one shell having over the entir... | 09/22/1981 |
| 4279866 | Method of producing weakly acidic cation exchange resin particles charged with uranyl ions Weakly acidic cationic ion exchange resin particles are charged with uranyl ions by contacting the particles step wise with aqueous uranyl nitrate solution at higher uranium concentrations from stage to stage. An alkaline medium is added to the uranyl nit... | 07/21/1981 |
