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| Number | Title | Issue Date |
| 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 |
| 6613303 | Highly radioactive miniaturized ceremic strontium 90 radiation sources and method for the production thereof The present invention relates to highly radioactive, miniaturized, cylindrical strontium 90 titanate, strontium 90 zirconate, and strontium 90 silicate radiation sources having an activity exceeding 25 mCi/mm3, preferably ࣙ30 mCi/mm3 | 09/02/2003 |
| 6251310 | Method of manufacturing a nuclear fuel pellet by recycling an irradiated oxide fuel pellet A method of manufacturing new UO2 -based fuel pellets by recycling irradiated UO2 -based fuel pellets. Irradiated UO2 -based fuel pellets are oxidized so as to make U3 O8 -based powder, and then the U... | 06/26/2001 |
| 6251309 | Method of manufacturing large-grained uranium dioxide fuel pellets containing U3O8 Disclosed is a method of manufacturing large-grained uranium dioxide pellets through the use of U3 O8 single crystals. The method consists of two main steps; producing U3 O8 single crystals and manufacturing lar... | 06/26/2001 |
| 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 |
| 6221286 | 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... | 04/24/2001 |
| 6143944 | Consolidation process for producing ceramic waste forms A process for the consolidation and containment of solid or semisolid hazardous waste, which process comprises closing an end of a circular hollow cylinder, filling the cylinder with the hazardous waste, and then cold working the cylinder to reduce its di... | 11/07/2000 |
| 6137025 | Ceramic composition for immobilization of actinides Disclosed is a ceramic composition for the immobilization of actinides, particularly uranium and plutonium. The ceramic is a titanate material comprising pyrochlore, brannerite and rutile.... | 10/24/2000 |
| 6133498 | Method for producing chemically bonded phosphate ceramics and for stabilizing contaminants encapsulated therein utilizing reducing agents Known phosphate ceramic formulations are improved and the ability to produce iron-based phosphate ceramic systems is enabled by the addition of an oxidizing or reducing step during the acid-base reactions that form the phosphate ceramic products. The addi... | 10/17/2000 |
| 6074748 | Molded product having photocatalytic function A molded article having a photocatalytic function, a desired shape, a large contact area, and being sufficiently irradiated with ultraviolet rays, even at an inner surface thereof. Unit particles such as glass beads, or filaments such as fibers, are bonde... | 06/13/2000 |
| 5994609 | Methods of treating nuclear hydroxyapatite materials Methods are provided for treating liquid hazardous waste containing anionic radioactive or heavy metal materials by binding the hazardous waste to hydroxyapatite powder, drying and then cold or hot pressing the hydroxyapatite powder into a solid mass for ... | 11/30/1999 |
| 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 |
| 5978432 | Dispersion fuel with spherical uranium alloy, and the fuel fabrication process The invention is directed to a high-density dispersion nuclear fuel having spherical particles of an uranium alloy dispersed in a nonfissionable matrix. The alloy includes uranium and 4-9 wt % Q, wherein Q is selected from the group consisting of Mo, Nb, ... | 11/02/1999 |
| 5932930 | Method for fabricating mixed oxide fuel A process for fabricating weapons-grade plutonium into mixed-oxide fuel for use in a nuclear reactor. The plutonium is converted into plutonia powder at a site remote from the fuel fabrication facility and then the plutonia powder is pressed and fired int... | 08/03/1999 |
| 5926772 | Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining su... | 07/20/1999 |
| 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 |
| 5762838 | Method of producing nuclear fuel pellet A nuclear fuel green compact is produced by sintering in an atmosphere of reducing gas. A mixed gas of hydrogen and nitrogen to which water vapor is added is used as the reducing gas. By establishing the amount of water vapor added to the mixed gas of hyd... | 06/09/1998 |
| 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 |
| 5732364 | Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining su... | 03/24/1998 |
| 5723100 | Uranium oxide production A process for the production of a uranium oxide in which UF6 is converted by reaction with steam into UO2 F2 in a first step and by further reaction of UO2 F2 with steam and/or hydrogen in a second st... | 03/03/1998 |
| 5597538 | Process to remove rare earths from spent nuclear fuel The present invention relates to a process for removing rare earth elements (RE) from spent nuclear fuel. The spent nuclear fuel is subjected to an oxidation step at a temperature of between about 200° to about 800° C. and a heating step at a temperatur... | 01/28/1997 |
| 5545427 | Process for the preparation of lithium aluminosilicate or gamma lithium aluminate ceramics having a controlled stoichiometry and microstructure This invention relates to a process for the preparation of lithium aluminosilicate or gamma lithium aluminate ceramics having a controlled microstructure and stoichiometry. According to this process, mixing takes place accompanied by stirring in a short c... | 08/13/1996 |
| 5514306 | Process to reclaim UO2 scrap powder A process for reclaiming scrap UO2 materials yields a high-sinter-density pellet. The scrap is oxidized in a high-temperature furnace to produce U3 O8. The U3 O8 particles from the oxidation furnace a... | 05/07/1996 |
| 5500158 | UO2 pellet and method for production thereof A process for producing a UO2 pellet comprising the steps of producing UO2 powder in accordance with the ADU (ammonium diuranate) method or the AUC (ammonium uranyl carbonate) method, forming a compact of said UO2 powder, ... | 03/19/1996 |
| 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 |
| 5414197 | Method of containing and isolating toxic or hazardous wastes A method of containing hazardous and toxic wastes includes the steps of irporating the dried waste, in a salt form, in melted polymer, such as asphalt, and forming the waste salt and asphalt blend into aggregate pellets. The pellets are coated with a pow... | 05/09/1995 |
| 5401444 | Apparatus and method for verifiably sterilizing, destroying and encapsulating regulated medical wastes Apparatus and method for processing regulated medical waste using a processing oven having multiple temperature ranges and compacting means and an oven with means for sensing and generating heat near the base of the medical waste container. Temperature-ca... | 03/28/1995 |
| 5390218 | Process for preparing a fuel pellet for nuclear reactor A process of preparing a fuel pellet for a nuclear reactor, comprising washing the gel particle using an organic solvent miscible with water to substitute the organic solvent for the water, removing the organic solvent, moistening again the dry gel partic... | 02/14/1995 |
| 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 |
| 5320786 | Zone sintering of ceramic fuels Cold pressed UC2 fuel compacts are sintered at temperatures greater than about 1850° C. while in contact with a sintering facilitator material, e.g., tantalum, niobium, tungsten or a metal carbide such as uranium carbide, thereby allowing for ... | 06/14/1994 |
| 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 |
| 5252258 | Method of recovering and storing radioactive iodine by freeze vacuum drying process The invention provides a method of recovering and storing radioactive iodine by a freeze vacuum drying process, in which off-gas generated when spent fuel is subjected to shearing and dissolving treatments is scrubbed and, when necessary, is subjected to ... | 10/12/1993 |
| 5238667 | Method for treating hydrated green salt A method of producing a high density, low hygroscopic green salt from hydrated green salt includes heating a charge of hydrated green salt in a nonreactive atmosphere to a first temperature above the boiling point of water to drive off free water; heating... | 08/24/1993 |
| 5238611 | Process for producing granulated particles from a powder A process for producing granulated particles from a powder which is insoluble in water, employs dimensions of the formed granulated particles which are substantially larger than those of the powder grains. The powder is mixed with an aqueous solution of a... | 08/24/1993 |
| 5164123 | Encapsulation of toxic waste A method of encapsulating a toxic material with a resinous plastic wherein the toxic material is admixed and coated with the resinous plastic to result in an encapsulated product having a protective skin thereover. The method involves an extrusion step fo... | 11/17/1992 |
| 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 |
| 5091120 | Process for obtaining UO2 fuel pellets from metallic U without producing any effluent Process for obtaining nuclear fuel pellets, which produces no liquid effluent, for which the starting product is metallic uranium, which is oxidized to U3 O 8, then crushed and either reduced to UO2 and activated (or vice ... | 02/25/1992 |
| 5066324 | Method of evaluation and identification for the design of effective inoculation agents The Droplet Emulsion Technique is used to produce droplets of bulk metal or metal alloys containing inoculant particles. Heterogeneous nucleation responses are then separated and identified with variances in inoculant chemistry, size, morphology, and surf... | 11/19/1991 |
