| AREVA NC Patent applications |
| Patent application number | Title | Published |
|---|
| 20120128555 | METHOD FOR TREATING SPENT NUCLEAR FUEL - A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO | 05-24-2012 |
| 20120090728 | Connection Device For A System For Filling Jars For The Production Of Nuclear Fuel - A system for filling a jar with powdery material, for example for the manufacture of nuclear fuel, including a device for connection between the jar and a material feed system, where the device includes:
| 04-19-2012 |
| 20120016173 | METHOD FOR TREATING A NITRIC AQUEOUS LIQUID EFFLUENT BY CALCINATION AND VITRIFICATION - A method for treating a nitric aqueous liquid effluent containing nitrates of metals or metalloids, comprising a step for calcination of the effluent in order to convert the nitrates of metals or metalloids into oxides of said metals or metalloids, at least one compound selected from the nitrates of metals or metalloids and the other compounds of the effluent leading upon calcination to a tacky oxide, and a dilution adjuvant comprising at least one nitrate of metal or metalloid leading upon calcination to a non-tacky oxide being added to the effluent prior to the calcination step in order to give a mixture of effluent and of dilution adjuvant. | 01-19-2012 |
| 20110306817 | Method For Processing A Nitrous Aqueous Liquid Effluent By Calcination And Vitrification - A method for treating a nitric aqueous liquid effluent containing nitrates of metals or metalloids, comprising a step for calcination of the effluent in order to convert the nitrates of metals or metalloids into oxides of said metals or metalloids, at least one compound selected from the nitrates of metals or metalloids and the other compounds of the effluent leading upon calcination to a tacky oxide, and a dilution adjuvant leading upon calcination to a non-tacky oxide being added to the effluent prior to the calcination step, a method wherein the dilution adjuvant comprises aluminium nitrate and at least one nitrate selected from iron nitrate and rare earth nitrates. | 12-15-2011 |
| 20110232111 | MACHINE FOR OPENING A CAN LID AND METHOD FOR EMPTYING THE CAN - This can opening machine comprises a lower guide ring to center the top of the single-piece can, comprising a centering chamfered face and an upper stop face. A piston arranged in the tool for cutting out the can lid is pushed downwards by a spring extending low enough to separate the cut out lid from the tool. The lid remains in the can during turning and content emptying operations. | 09-29-2011 |
| 20110217485 | METHOD FOR COATING A METAL CRUCIBLE ELEMENT WITH A MIXTURE OF GLASS AND CERAMIC - Angular sectors of a cylindrical wall of a crucible for vitrification of waste, built in steel and subject to high temperatures, are coated with a mixture of mainly glass and ceramic, the coating being subject to a heat treatment comprising a step between 650° C. and 850° C. so as to perform surface melting of the mixture filling the open porosity, improving dielectric strength and the cohesion of the coating, but without producing any excessive thermal expansion or oxidation of the substrate which would lead to fast flaking of the coating. | 09-08-2011 |
| 20110212005 | METHOD FOR PREPARING URANIUM CONCENTRATES BY FLUIDIZED BED PRECIPITATION, AND PREPARATION OF UO3 AND U3O8 BY DRYING/CALCINING SAID CONCENTRATES - Method for producing a uranium concentrate in the form of solid particles, by precipitation from a uranium-containing solution using a precipitating agent, in a vertical reactor comprising a base, a top, a central part, an upper part, and a lower part, the solid particles of the uranium concentrate forming a fluidized bed under the action of a rising liquid current which circulates from the base towards the top of the reactor successively passing through the lower part, the central part and the upper part of the reactor, and which is created by introducing a liquid recycling current (flow) at the base of the reactor, said liquid recycling current being tapped at a first determined level (A) in the upper part of the reactor and sent back without settling to the base of the reactor, excess liquid being also evacuated via an overflow located at a second determined level (B) in the upper part of the reactor; a method in which the upper limit (C) of the fluidized bed of solid particles is controlled so that it is positioned at a level below the first and second determined levels. | 09-01-2011 |
| 20110204167 | METHOD FOR DECLADDING NUCLEAR FUEL AND CRUSHING MACHINE BY CLADDING DEFORMATION - A machine comprising two rollers for ovalising a nuclear fuel cladding to crush the content thereof allowing its easy release even if the pellets are arranged in the cladding with little clearance. The opposite inclinations of the rollers promote automatic forward travel of the claddings. The opening and the inclination of the claddings lead to release of the crushed fuel. The rollers are biconical, with an input portion of increasing diameter and an output portion of decreasing diameter, to apply sufficient ovalisations to crush the fuel whilst restoring rotundity to the cladding when it leaves the machine, to facilitate the outflow of debris. | 08-25-2011 |
| 20110164718 | DEVICE FOR GRIPPING FUEL ELEMENTS, ASSOCIATED CLAMP AND ASSOCIATED HANDLING SYSTEM - A fuel element handling system having a gripping device, the structure of which can be pushed in the horizontal position and uncoupled from the handling system if a failure occurs, uncoupling releasing the load formed by the fuel elements and their gripped support and putting them in a safe situation. | 07-07-2011 |
| 20110164717 | DEVICE FOR MEASURING AND CORRECTING A PARALLELISM ERROR IN A NUCLEAR FUEL ROD - A device for measuring and correcting a parallelism error of an upper plug end of a nuclear fuel rod comprising mechanisms for measuring a parallelism error and for correcting said error, and a mechanism for positioning said device on the fuel rod and cooperating with a rack on which the fuel rod is stored, said correction means being arranged opposite the measuring mechanism relative to the location of the fuel rod, in order to allow a measurement of the parallelism error during correction of said error. | 07-07-2011 |
| 20110116590 | Device And Method For The Automated Decontamination Of A Nuclear Fuel Rod - A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod. | 05-19-2011 |
| 20110108746 | CASING INTERNAL PART AND CASING FOR THE DRY INTERMEDIATE STORAGE OF IRRADIATED FUEL ELEMENTS, AND INTERMEDIATE STORAGE METHOD - The subject of the present invention is:
| 05-12-2011 |
| 20110077449 | CONTAINER FOR PACKAGING NUCLEAR WASTE WITH FORCE-FITTED LID - The container is comprised of a side wall of which the end edges are each provided with a blocking member, of which at least one is inserted in order to close an opening. | 03-31-2011 |
| 20110061994 | Screening and Alignment of Nuclear Fuel Pellets - A conveyor device has a sequence of two vibrating screens vertically separated (d) from each other and supplying an alignment bowl, to eliminate chips and residue from nuclear fuel pellets stored in bulk in a boat and to align them in order to fill fuel rods. Due to these two screens, pellets are set aside and turned over, and chips are efficiently separated in a pot, without any congestion of the system. | 03-17-2011 |
| 20110056719 | ELECTRICITY TRANSMISSION DEVICE AT HIGH CURRENT AND HIGH FREQUENCY - The electricity transmission device comprises prolonged rigid conductors made of copper ( | 03-10-2011 |
| 20110036836 | RADIOACTIVE WASTE STORAGE CONTAINER - A container for the storage of radioactive waste comprising a reversible lid having, on one hand, a first opening sealing portion provided with a first delimiting surface of an inner space wherefrom second gripping means project, said first portion being designed so as to be able to be force-fitted in an end part of a container body, and, on the other, a second sealing portion, provided with a second delimiting surface wherefrom first gripping means project, said second portion being designed so as to be able to be fitted in the end part. | 02-17-2011 |
| 20100186191 | REDUCTION DEVICE FOR LARGE DIAMETER BAG PORTS - Device for large diameter bag port comprises a diameter reduction spacer with a first circular orifice of the diameter equal to the diameter of the port bag. This first orifice is facing towards the bag port. This device comprises also a second orifice facing towards the outside of the containment in the direction opposite to the first orifice, this second orifice being elongated in shape, particularly ovoid. | 07-29-2010 |
| 20100104467 | PRODUCTION OF THORIUM 228 STARTING FROM A NATURAL THORIUM SALT - The invention relates to a process for producing | 04-29-2010 |
| 20100060119 | GLOVE BOX WITH LIT SEALED CONTAINMENT - The invention relates to a glove box with a sealed containment delimited at least partially by a wall having a polycarbonate partition ( | 03-11-2010 |
| 20100054388 | Sealing Means, Transfer Device Comprising Such a Sealing Means, Arrangement Comprising Such a Transfer Device and a Method for Producing Said Sealing Means - Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism. | 03-04-2010 |
| 20100038377 | DEVICE AND METHOD FOR EMPTYING JARS - According to the invention, a mandrel, provided with tabs for holding jars containing powders and for turning the jars upside down in order to empty them through the neck, is equipped with vibration generators for exciting the walls of the jar in order to shake off the powder masses adhering thereto. The method is much more efficient than even more energetic shock applications, and frequency scanning can further be advantageously applied. One application relates to an emptying step in methods for the production of nuclear fuel pellets by powder agglomeration. | 02-18-2010 |
| 20100011561 | TOOL USED FOR THE PRESSURE CRIMPING AND DRIVING-OUT OF A CLEAT - The invention relates to a tool used for pressure crimping and driving-out of a cleat, comprising: (a) a first receptacle opposite which is located a crimping head movably mounted on a body of the tool; (b) a second receptacle opposite which is located a drive-out head also movably mounted on the body; and (c) pressure means movably mounted on the body so as to be able to be displaced from a crimping position in which they are capable of exerting pressure on the crimping head, to a drive-out position in which they are capable of exerting pressure on the drive-out head, and conversely. | 01-21-2010 |
| 20090292576 | METHOD FOR EVALUATING SPECIFIC DATA IN RELATION TO CLEANING UP/DISMANTLING A FACILITY - A method for evaluating specific data in relation to the cleaning up/dismantling of a facility comprising at least one room. This method includes the following steps: | 11-26-2009 |
| 20090265131 | MEASUREMENT OF THE TEMPERATURE OF A MOLTEN GLASS BATH - One proceeds with indirect measurement of the temperature of a molten bath ( | 10-22-2009 |
| 20090190711 | CONTAINER-LOADING CASK FOR AT LEAST ONE NUCLEAR FUEL ASSEMBLY, A GRIPPING DEVICE AND LOADING METHOD - A cask for loading at least one nuclear fuel assembly in a transport container, including a body with a longitudinal axis (X) capable of sealably covering an upper end of a container, at least one aperture ( | 07-30-2009 |
| 20090184298 | PROCESS FOR REPROCESSING A SPENT NUCLEAR FUEL AND OF PREPARING A MIXED URANIUM-PLUTONIUM OXIDE - A process for reprocessing a spent nuclear fuel and for preparing a mixed uranium-plutonium oxide. The process: a) separates the uranium and plutonium from fission products, americium, and curium that are present in an aqueous nitric solution resulting from dissolution of the fuel in nitric acid, the separating including at least one operation of coextracting the uranium and plutonium from the solution by a solvent phase; b) partitions the coextracted uranium and plutonium to a first aqueous phase containing plutonium and uranium, and a second aqueous phase containing uranium but no plutonium; c) purifies the plutonium and uranium that are present in the first aqueous phase; and d) coconverts the plutonium and uranium to a mixed uranium/plutonium oxide. | 07-23-2009 |
| 20090142177 | Device to Load a Sintering Boat with Nuclear Fuel Pellets and Loading Method Using Said Device - Device to load a sintering boat with nuclear fuel pellets, comprising a loading chute ( | 06-04-2009 |
| 20090046826 | Fuel Cladding Protective Sleeve, Method for Producing Fuel Rods and Device for Carrying out Said Method - Method for producing fuel rods characterized in that it comprises the steps of:
| 02-19-2009 |
| 20090041176 | SPRING MOUNTING DEVICE FOR NUCLEAR FUEL ROD - A spring mounting device in a cladding tube for nuclear fuel, comprising a spring distributor, a spring loader in the cladding tube, the distributor supplying the springs to the loader, said loader comprising a longitudinal slide to receive the spring, a pusher in order to set the spring into place in the cladding tube and is able to move in the slide, means of displacement of said pusher, said device comprising mechanical means in order to associate the actuation of the means of displacement with that of the spring distributor. | 02-12-2009 |
| 20080298430 | Temperature Measurement Tube - A temperature measurement tube is composite and comprises a rigid shaft ( | 12-04-2008 |
| 20080282547 | Knife with a Retracting Blade, Usable in Particular in a Hostile Environment - A knife includes a sheath ( | 11-20-2008 |
| 20080228022 | Vacuumable Gel for Decontaminating Surfaces and Use Thereof - The present invention relates to a vacuumable gel that can be used for decontaminating surfaces, and also to the use of this gel. The decontamination may be, for example, a radioactive decontamination. The gel of the present invention is composed of a colloidal solution. It comprises from 5 to 25 wt % of an inorganic viscosity modifier relative to the total weight of the gel; from 0.01 to 0.2 wt % of a surfactant relative to the total weight of the gel, and, particularly preferably, a surfactant in an amount strictly below 0.1 wt % relative to the total weight of the gel; from 0.5 to 7 mol, per litre of gel, of an inorganic acid or base; and optionally from 0.05 to 1 mol, per litre of gel, of an oxidizer having a standard redox potential E | 09-18-2008 |
