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| Number | Title | Issue Date |
| 7311655 | Method for manufacturing radioactive brachytherapy source material, brachytherapy source material and encapsulated radioactive brachytherapy source The invention relates to a method for producing a radioactive brachytherapy source material comprising indium-114m in radioactive equilibrium with indium-114 as main radioactive isotopes. A new radioactive brachytherapy source material comprises indium-114m in radio... | 12/25/2007 |
| 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 |
| 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 |
| 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 |
| 6190582 | Controlled atmosphere sintering process for urania containing silica additive Improved method of sintering for the manufacture of nuclear fuel comprising a fissionable ceramic material including a silica containing additive. The method includes controlling the sintering atmosphere to impede loss through vaporization of the silica.... | 02/20/2001 |
| 5978431 | Nuclear fuel pellets A method of producing mixed oxide fuel pellets. The method uses oxides of at least two fissile elements and includes a mixing, milling, spheroidising and sintering step to produce a fuel pellet incorporating a neutron poison.... | 11/02/1999 |
| 5762831 | Composite nuclear fuel material and method of manufacture of the material This invention relates to a composite nuclear fuel material and method of manufacture of said material. The purpose of the invention is a composite nuclear fuel material comprising a matrix inert under irradiation and particles of nuclear fuel offering go... | 06/09/1998 |
| 5464571 | Once-through nuclear reactor fuel compounds The improved oxide, once-through plutonium fuel compound that can be used for nuclear fission in currently operating light-water reactors and fast reactors has a composition in the range defined by the lines that connect the three compositional points of ... | 11/07/1995 |
| 5429775 | Nuclear fuel pellets and method of manufacturing the same The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets.... | 07/04/1995 |
| 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 |
| 5417943 | Method for producing UO2 or (U/PU)02 powder A method for producing UO2 or (U/Pu)O2 powder includes obtaining ammonium uranyl carbonate or ammonium uranyl plutonyl carbonate by treating a starting oxide selected from the group consisting of uranium oxide, plutonium oxide and ur... | 05/23/1995 |
| 5362426 | Nuclear fuel pellets and method of manufacturing the same The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets.... | 11/08/1994 |
| 5268947 | Nuclear fuel elements comprising a trap for fission products based on oxide A nuclear fuel element comprising sintered pellets based on uraniferous oxide which are surrounded by a metallic sheath and permitting trapping of the fission products which appear in the course of irradiation characterized in that the pellets contain or ... | 12/07/1993 |
| 5257298 | Nuclear fuel pellets having an aluminosilicate deposition phase This invention provides nuclear fuel pellets including fission substance of UO2 or UO2 having Gd2 O3 added thereto, the pellets comprising a satisfactory solid-solution state (homogeneous state), large grain dia... | 10/26/1993 |
| 5255299 | Method of manufacturing nuclear fuel pellets The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets.... | 10/19/1993 |
| 5180527 | Nuclear fuel pellets The present invention provides improved nuclear fuel pellets having high thermal conductivity for use in an LWR. This can be achieved by creating a continuous deposition phase of high-thermal conductivity substances in the grain boundaries in the pellets.... | 01/19/1993 |
| 5139709 | Process for converting uranyl compounds to UO2 via ADU ADU (ammonium diuranate) is prepared in particle form directly by reacting ammonium gas with liquid droplets of atomized uranyl compound solutions. Generation of liquid filtrate is prevented by using concentrated solutions of uranyl compounds as feed solu... | 08/18/1992 |
| 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 |
| 4985183 | UO2 pellet fabrication process There is disclosed a process for fabricating UO2 pellets from highly active uranium dioxide powders, comprising the steps of (1) uniformly adding at least one pore-former agent in the range of 0.3 to 1.4% by weight to uranium dioxide powders as... | 01/15/1991 |
| 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 |
| 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 |
| 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 |
| 4774051 | Sintered nuclear fuel compact and method for its production A sintered nuclear fuel compact of UO2 or the mixed oxides (U, Pu)O2 and (U, Th)O2, with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided, has in its sintered matrix neutr... | 09/27/1988 |
| 4749529 | Method of manufacturing sintered nuclear fuel bodies Sintered nuclear fuel bodies are manufactured by pressing a powder of UO2 containing 1-20 percent by weight Gd2 O3 and up to 20 percent by weight U3 O8 into a pressed body and sintering the pressed bo... | 06/07/1988 |
| 4696769 | Method and binder for the manufacture of nuclear fuel pellets, and the product A method and binder composition for prolonging the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compression molding in the manufacture of... | 09/29/1987 |
| 4687601 | Process for the preparation of pulverulent metallic oxides from metallic nitrates Process for the preparation of pulverulent metallic oxides with predetermined reactivity which is adjusted by the specific surface area, which are intended to be subjected to subsequent conversions, by thermal treatment of corresponding nitrates in the fo... | 08/18/1987 |
| 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 |
| 4670198 | Binder system for the manufacture of nuclear fuel pellets, and the method and product thereof A reproducible method and stable binder composition for preserving the induced plasticity of a particulate ceramic material admixture comprising uranium dioxide and a fugitive binder, and product thereof, for subsequent compaction by compressing molding i... | 06/02/1987 |
| 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 |
| 4636352 | Nuclear fuel rod with burnable plate and pellet-clad interaction fix An improved nuclear fuel rod comprising a tubular metallic cladding containing a plurality of nuclear fuel pellets has a plurality of ceramic wafers therein, each of which wafers being disposed between a major portion of adjacent fuel pellets. The ceramic... | 01/13/1987 |
| 4528130 | Method for dissolving hard-to-dissolve thorium and/or plutonium oxides Method for dissolving hard-to-dissolve thorium and/or plutonium oxides, especially dioxides such as ThO2, PuO2 or (U/Pu)O2 mixed oxides by heating the oxides in a hermetically sealed vessel in fluoride-free nitric acid. Th... | 07/09/1985 |
| 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 |
| 4460522 | Method of producing low density oxide fuel pellet A method of producing an oxide fuel pellet having a low density is provided which comprises adding a manganese compound to an oxide fuel powder selected from a group consisting of uranium dioxide powder and a mixed powder of uranium dioxide and plutonium ... | 07/17/1984 |
| 4438050 | Method for the manufacture of very dense oxidic nuclear fuel bodies Manufacture of very dense oxidic fuel bodies of UO2 with rare earth oxides in which pressed blanks are subjected to sintering in an oxidizing atmosphere at relatively low temperature and are sintered in a reducing atmosphere at a higher tempera... | 03/20/1984 |
| 4432915 | Method for producing nuclear fuel pellets, and product thereof A method for improving the physical properties of pressed bodies or pellets formed of particulate nuclear fuel material containing uranium dioxide. The green or unfired pressed bodies comprise a fugitive binder dispersed through the particulate fuel mater... | 02/21/1984 |
| 4427579 | Method of producing fugitive binder-containing nuclear fuel material A nuclear fuel material green body of density from about 30 to 70% of theoretical density having tensile strenght and plasticity adequate to maintain the integrity of the body during processing leading to ultimate sintered condition is produced by adding ... | 01/24/1984 |
| 4401608 | Method for enlarging grain size of uranium oxide The grain size of particulate uranium oxides is increased and adjusted by the application thereto of hydrogen peroxide. The procedure is useful in the manufacture of nuclear reactor fuel from powdered fissionable materials.... | 08/30/1983 |
| 4389341 | Fugitive binder-containing nuclear fuel material and method of production A nuclear fuel material green body of density from about 30 to 70% of theoretical density having tensile strength and plasticity adequate to maintain the integrity of the body during processing leading to ultimate sintered condition is produced by adding ... | 06/21/1983 |
| 4383953 | Method of improving the green strength of nuclear fuel pellets A process for imparting increased strength and physical durability in green bodies or pellets formed of particulate oxides of uranium, plutonium and the like in the production of pelletized fissionable nuclear fuel. The green or unfired pellets comprise a... | 05/17/1983 |
