Did You Know...
...that Robert Adler has the dubious distinction of being the Father of the Couch Potato? Back in 1955 Adler was employed by what was then Zenith Radio Corp., where he was charged to invent something that would allow viewers to turn down the TV volume without leaving their chairs. After a series of flops (such as a wired contraption that people tripped over), Adler hit on the idea of using sound waves. Thus the Remote Control was born...
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| Number | Title | Issue Date |
| 8088312 | Method of removing the polymer encapsulating a nuclear fuel pellet Method for removing the epoxy and/or phenolic polymer encapsulating a nuclear fuel pellet comprising uranium dioxide UO2, the method comprising the following successive steps: a) the polymer is pyrolysed in a reducing atmosphere; and b) the carbon residue... | 01/03/2012 |
| 7731870 | Purex method and its uses The invention relates to a method constituting an improvement of the PUREX method, which makes it possible to obtain separation of uranium from the other actinides (Pu, Np, Th, . . . ) in a single purification cycle. This method successively comprises: a) co-... | 06/08/2010 |
| 7279139 | Agitation type powder dissolving apparatus for reprocessing spent nuclear fuel An agitation type powder dissolving apparatus comprises a dissolving tank into which powder of spent nuclear fuel is to be supplied, an agitating member rotatably disposed in the dissolving tank, and rise inhibiting structure, disposed in the dissolving tank above t... | 10/09/2007 |
| 7172741 | Method for reprocessing spent nuclear fuel It is an object to increase a reprocessing speed of spent nuclear fuel and to obtain uranium having a high purity and a plutonium mixture reusable as it is at a low cost through a simple procedure. The spent nuclear fuel 1 is subjected to fluorination ... | 02/06/2007 |
| 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) O2, by simultaneously coprecipitation and then calcinations. ... | 01/30/2007 |
| 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 MOX fabrication scrap. ... | 07/04/2006 |
| 7029633 | Method and apparatus for reducing uranium trioxide Uranium trioxide is reduced to uranium dioxide using microwave radiation or radiofrequency radiation directed in such a way that the radiation encounters an interface between uranium trioxide and the uranium-containing reduction product without first having passed t... | 04/18/2006 |
| 6984344 | Production process of a composite nuclear fuel material composed of (U, Pu)Oaggregates dispersed in a UOmatrix 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 powder and of a PuO... | 01/10/2006 |
| 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 UO2, for use in the manufacture of MOX fuel. This process comprises the following stages: 1) to prepare an aqueous suspension of a powder of UO2 obtained... | 12/02/2003 |
| 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 |
| 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 |
| 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 |
| 5702676 | Production method for obtaining pressable powder yielding high sinter density pellets without defects This invention provides an improved process of preparing UO2 powder from poor quality, partially oxidized powder containing organic and inorganic impurities. The process is illustrated in the flow chart of FIG. 1 which includes the steps of (a)... | 12/30/1997 |
| 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 metal oxide impurities not soluble in nitric acid is accomplis... | 12/16/1997 |
| 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 sintering.... | 06/24/1997 |
| 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 the small droplets of a stock solution or sol that contains... | 12/03/1996 |
| 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 |
| 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 minor actinide nuclides and rare earth elements are added to... | 03/12/1996 |
| 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 acid solution. The process renders the alloy suitable for unc... | 12/05/1995 |
| 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 |
| 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 oven. The rotary drum has the outer peripheral surface compos... | 01/11/1994 |
| 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 |
| 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 |
| 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 |
| 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 |
| 4889663 | Method of manufacturing uranium oxide base nuclear fuel pellets For manufacturing uranium oxide based nuclear fuel pellets, a fine and reactive U3 O8 powder is mixed with a fine UO2 powder obtained by dry conversion. The U3 O8 is obtained by oxidation in air of UO... | 12/26/1989 |
| 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 |
| 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 |
| 4839103 | Method for obtaining a solution of nuclear fuel not readily dissovable, especially of PuOhd 2 or (U/Pu)O2 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 nuclear fuel disposed outside of the nitric acid undergoing... | 06/13/1989 |
| 4839149 | Ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O2 The invention relates to an ammonium plutonate uranate, its preparation process and its use for producing the mixed oxide (U,Pu)O2. The ammonium plutonate uranate of formula [Cu,Pu)O3 ]2 [NH3 ]x [H2 | 06/13/1989 |
| 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 fluidized bed of a uranium oxide material. Thereafter, the agglo... | 05/16/1989 |
| 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 |
| 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 |
| 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 |
| 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 |
| 4676935 | Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO2+x) and plutonium dioxide (PuO2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then ... | 06/30/1987 |
| 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 |
