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7622090 |
Method for separating uranium (VI) from actinides(IV) and/or actinides (VI) and its uses
The invention relates to a method for separating uranium(VI) from one or more actinides selected from actinides(IV) and actinides(VI) other than uranium(VI), characterized in that it comprises the...
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7169370 |
Method for co-precipitating actinides and method for preparing mixed actinide oxides
The present invention generally relates to the preparation of mixed actinide oxides, such as mixed oxides of uranium and plutonium (U, Pu) O 2 , by simultaneously coprecipitation and then...
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7070717 |
MOX fuel fabrication process from weapon plutonium feed
Process for fabrication MOX fuel from weapon originating plutonium oxide (W—PuO 2 ), including a process for fabricating MOX fuel pellets, a dry processing of W—PuO 2 powder, and a dry...
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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 UO 2 and of PuO 2 dispersed in a UO 2 matrix comprising the steps of dry co-grinding of...
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6656391 |
Preparation by spray-drying of a flowable uranium dioxide powder obtained by dry process conversion of UF6
The invention relates to a process for preparing a castable powder of uranium dioxide UO 2 , for use in the manufacture of MOX fuel. This process comprises the following stages: 1) to prepare an...
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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 U 3 O 8 single crystals. The method consists of two main steps; producing U 3 O 8 single crystals...
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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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5723100 |
Uranium oxide production
A process for the production of a uranium oxide in which UF 6 is converted by reaction with steam into UO 2 F 2 in a first step and by further reaction of UO 2 F 2 with steam and/or hydrogen...
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5702676 |
Production method for obtaining pressable powder yielding high sinter density pellets without defects
This invention provides an improved process of preparing UO 2 powder from poor quality, partially oxidized powder containing organic and inorganic impurities. The process is illustrated in the...
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5698173 |
Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors
A method for purifying metallic alloys of uranium for use as nuclear reactor fuels in which the metal alloy is first converted to an oxide and then dissolved in nitric acid. Initial removal of...
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5641435 |
Control of residual gas content of nuclear fuel
The present invention relates, in general, to a method of producing mixed oxide nuclear fuel and, in particular, to a method of reducing the amount of residual gas absorbed on fuel pellets after...
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5581589 |
Method and apparatus for producing gel particles
A method and an apparatus for producing microspherical ceramic particles such as particulate ceramic fuels for use in nuclear reactors. To produce gel particles by performing microwave heating on...
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5514306 |
Process to reclaim UO.sub.2 scrap powder
A process for reclaiming scrap UO 2 materials yields a high-sinter-density pellet. The scrap is oxidized in a high-temperature furnace to produce U 3 O 8 . The U 3 O 8 particles from the...
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5500158 |
UO2 pellet and method for production thereof
A process for producing a UO 2 pellet comprising the steps of producing UO 2 powder in accordance with the ADU (ammonium diuranate) method or the AUC (ammonium uranyl carbonate) method, forming a...
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5499276 |
Method for minor actinide nuclides incineration
Neptunium of minor actinide nuclides separated from spent fuel is added to fuel of reactor cores (inner reactor cores and/or outer reactor cores) of a fast reactor and americium of the separated...
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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...
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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...
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5278379 |
Continuous denitration apparatus which uses microwave heating
A continuous denitration apparatus by microwave heating comprises an oven into which microwaves are applied and a cylindrical rotary drum disposed horizontally and rotatably disposed inside the...
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5139709 |
Process for converting uranyl compounds to UO.sub.2 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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5015422 |
UO.sub.2 pellet fabrication process
Making uranium dioxide pellets of controlled grain size by treating 50-500 g/l UO 2 F 2 with NH 3 in a first and a second stages to form (NH 4 ) 2 U 2 O 7 precipitate, wherein the NH 3 /U...
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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...
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4963294 |
Method of preparing uranium dioxide powder from uranium hexafluoride
A method of fabricating uranium dioxide (UO 2 ) powder from uranium hexafluoride (UF 6 ) is disclosed, which comprises (1) reacting UF 6 gas with steam with controlling the temperature of...
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RE33243 |
Process for treating a metal oxide powder
The invention relates to a process for the treatment of a metal oxide powder, particularly a UO 2 or PuO 2 powder, with a view to its fritting. This process consists of oxidizing the powder, so...
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4889663 |
Method of manufacturing uranium oxide base nuclear fuel pellets
For manufacturing uranium oxide based nuclear fuel pellets, a fine and reactive U 3 O 8 powder is mixed with a fine UO 2 powder obtained by dry conversion. The U 3 O 8 is obtained by oxidation...
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4885147 |
Process for preparing a large-grained UO.sub.2 fuel
A process for producing large-grain, low-density UO 2 micro-fuel spheres, the micro-fuel spheres having an average grain diameter of at least 5 μm, which comprises: (a) isothermally heating...
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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 UO 2 and the oxide of at least one other fissionable or rare earth element M, the pellets being...
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4839103 |
Method for obtaining a solution of nuclear fuel not readily dissovable, especially of PuOhd 2 or (U/Pu)O.sub.2 mixed oxide
Not readily dissolvable nuclear fuel is dissolved in an airtight closed vessel or autoclave. Nitric acid is evaporated and condensed in the vessel and the nitric acid condensate trickles over the...
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4839149 |
Ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O.sub.2
The invention relates to an ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O 2 . The ammonium plutonate uranate of formula [Cu,Pu)O 3 ] 2 [NH...
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4830841 |
Conversion of uranium hexafluoride to uranium dioxide
The present invention contemplates the conversion of uranium hexafluoride with superheated steam to produce a fine, submicron, uranyl fluoride powder which is agglomerated and densified in a...
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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...
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4774051 |
Sintered nuclear fuel compact and method for its production
A sintered nuclear fuel compact of UO 2 or the mixed oxides (U, Pu)O 2 and (U, Th)O 2 , with which reactivity losses in a nuclear reactor having relatively long fuel element cycles are avoided,...
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4749529 |
Method of manufacturing sintered nuclear fuel bodies
Sintered nuclear fuel bodies are manufactured by pressing a powder of UO 2 containing 1-20 percent by weight Gd 2 O 3 and up to 20 percent by weight U 3 O 8 into a pressed body and sintering...
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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...
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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...
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4676935 |
Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid
Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO 2 +x) and plutonium dioxide (PuO 2 ) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free...
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4671904 |
Method for producing oxidic sintered nuclear fuel bodies
UO 2 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...
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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...
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4663093 |
Preparation of nuclear fuel spheres by flotation-internal gelation
A simplified internal gelation process for the preparation of gel spheres of nuclear fuels. The process utilizes perchloroethylene as a gelation medium. Gelation is accomplished by directing...
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4643873 |
Fabrication of nuclear fuel pellets
Uranium dioxide powder produced by a gas phase process in which uranium hexafluoride is reacted with dry steam and then with steam and/or hydrogen at a higher temperature is subjected to mechanical...
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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 PuO 2 and UO 2 powders, where the mixture contains at least about 30% PuO 2 , and where at least...
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4578229 |
Method for the manufacture of oxidic sintered nuclear fuel bodies
Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO 2 starting power or a mixture of UO 2 and PuO 2 starting powder at a treatment temperature...
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4562017 |
Process for the production of ceramic fuel tablets
There is described a process for the production of ceramic fuel pellets which contain fission and/or fertile material in oxidized form, by heating porous green fuel pellets in a reducing atmosphere...
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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 ThO 2 , PuO 2 or (U/Pu)O 2 mixed oxides by heating the oxides in a hermetically sealed vessel...
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4505882 |
Process for manufacturing uranium dioxide powder
A process for manufacturing uranium dioxide powder which comprises forming fine uranium dioxide powder having a high sinterability and coarse uranium dioxide powder having a low sinterability...
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4439402 |
Nuclear fuel conversion systems
A nuclear fuel conversion system comprises a unit for heating and denitrifying a nitric acid solution of uranyl nitrate, plutonium nitrate, or mixture thereof, a unit for grinding denitrified...
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4436677 |
Nuclear fuel fabrication process
Disclosed is a method of making a pellet from a powder by placing the powder in a heat-shrinkable container, sealing the container and isostatically pressing the container at a temperature which...
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4409157 |
Method for improved decomposition of metal nitrate solutions
A method for co-conversion of aqueous solutions of one or more heavy metal nitrates wherein thermal decomposition within a temperature range of about 300° to 800° C. is carried out in the...
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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...
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4397778 |
Coprocessed nuclear fuels containing (U, Pu) values as oxides, carbides or carbonitrides
Method for direct coprocessing of nuclear fuels derived from a product stream of a fuels reprocessing facility containing uranium, plutonium, and fission product values comprising nitrate...
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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...
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