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8137090 |
Device for producing nuclear fuel pellets and production method applying such a device
Production device including a press, a conveyor (4) intended to transport pellets from the press to a sintering area, means (26) for transferring pellets from the press to the conveyor (4), and...
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7875216 |
Powder dispenser, notably for pelletizer and method for making nuclear fuel pellets
The object of the present invention is mainly a powder dispenser including a casing capable of impulsing the powder in a reciprocal movement on a plane along a determined displacement direction...
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7608209 |
Use of sintered mixed carbonates for the confinement of radioactive carbon
The present invention relates to the use of a mixed carbonate of formula AB(CO3)2, in which A and B are different and chosen from alkali metals, alkaline-earth metals and rare earths, for the...
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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,...
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7485246 |
Fabrication method of sintered duplex nuclear fuel pellet
A method for fabricating a sintered duplex nuclear fuel pellet includes the steps of: preparing a first powder composed of a material selected from the group consisting of UO2 and UO2—Er2O3, and a...
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7070717 |
MOX fuel fabrication process from weapon plutonium feed
Process for fabrication MOX fuel from weapon originating plutonium oxide (W—PuO2), including a process for fabricating MOX fuel pellets, a dry processing of W—PuO2 powder, and a dry processing of ...
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6984344 |
Production process of a composite nuclear fuel material composed of (U, Pu)O2 aggregates dispersed in a UO2 matrix
The invention relates to a production process of a composite material composed of aggregates of a blend of UO2 and of PuO2 dispersed in a UO2 matrix comprising the steps of dry co-grinding of a UO2...
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6878313 |
Method of fabricating sintered nuclear fuel compact
To furnish stably a sintered nuclear fuel compact of uranium dioxide with a large grain diameter, a fabrication method therefor requires sintering a starting material at two stages in an oxidizing...
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6808656 |
Method of producing a nuclear fuel sintered body
A nuclear fuel sintered body is produced from a powder which contains at least one fissile heavy metal oxide. During the further treatment of the powder over the course of the process preceding the...
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6783706 |
Method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste
A method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste, including a process for making fuel pellets of mixed (U,Pu)O2 oxide, including a dosage and a first mixture (1) of...
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6764618 |
Method for making mixed oxide (U,Pu)O2 nuclear fuel pellets from non-castable UO2 powder
A process for manufacturing (U,Pu)O2 mixed oxide nuclear fuel pellets. In a first blending operation, PuO2 is mixed with a UO2 powder and/or fuel manufacturing scrap, forming a first blend. The...
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6733699 |
Method for producing nuclear fuel pellets of the MOX type
A method for producing mixed oxide nuclear fuel pellets comprises the steps of preparing an U-Pu oxide blend powder having a Pu content in excess of the finally desired value, preparing uranium...
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6714617 |
Disposal of radiation waste in glacial ice
Encapsulating calcined radioactive waste in strong, corrosion-resistant spheres of dimensions such that heat from the radiation melts the ice at a rate which brings the spheres to the bottom of the...
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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...
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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 s...
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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...
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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...
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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...
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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 f...
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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...
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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...
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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.
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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...
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6074748 |
Molded product having photocatalytic function
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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...
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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,...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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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,...
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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 ...
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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),...
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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...
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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...
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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...
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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...
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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...
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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...
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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...
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