A method for cavitation peening of an internal surface of a hollow metal part including an internal surface is provided. The method includes installing a first seal in sealing contact with the internal surface; installing a second seal axially offset from the first seal, the first seal and the second seal defining a chamber within the hollow part axially therebetween; providing a cavitation peening nozzle of a cavitation peening tool within the chamber; pressurizing the chamber; and cavitation peening the internal surface via the cavitation peening nozzle while actuating the cavitation peening nozzle within the pressurized chamber. An apparatus for cavitation peening of an internal surface of a hollow metal part, the hollow part including an internal surface is also provided.
C21D 7/04 - Modifying the physical properties of iron or steel by deformation by cold working of the surface
C21D 8/10 - Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of tubular bodies
C21D 9/08 - Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articlesFurnaces therefor for tubular bodies or pipes
C21D 9/50 - Heat treatment, e.g. annealing, hardening, quenching or tempering, adapted for particular articlesFurnaces therefor for welded joints
C21D 10/00 - Modifying the physical properties by methods other than heat treatment or deformation
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
2.
METHOD OF PEENING AN OBSTRUCTED REGION OF A METAL ASSEMBLY
A method for peening an obstructed region of a metal assembly that is obstructed by an obstructing part of the metal assembly is provided. The method includes determining an optimal peening path for treating the obstructed region irrespective of the obstructing part; identifying a portion of the obstructing part within the optimal peening path; determining a section of the portion of the obstructing part that is removable without affecting a mechanical integrity and functionality of the obstructing part; removing, by machining, the section so as to create additional space along the optimal peening path; and peening the obstructed region, a path of the peening at least partially crossing through the additional space. A method for peening a nuclear reactor pressure vessel is also provided.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
3.
NOVEL DISSYMMETRIC N,N-DIALKYLAMIDES, THE SNYTHESIS THEREOF AND USES OF SAME
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
Inventor
Miguirditchian, Manuel
Baron, Pascal
Lopes Moreira, Sandra
Milanole, Gaëlle
Marie, Cécile
Abstract
The invention relates to novel dissymmetric N,N-dialkylamides having formula (I), wherein R represents a straight or branched alkyl group at C8 to C15. The invention also relates to a method for synthesising said N,N-dialkylamides, and to the uses of same as extractants, alone or in admixture, in order to extract uranium and/or plutonium from an aqueous acid solution or to partially or fully separate uranium from plutonium in an aqueous acid solution and, in particular, an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid. The invention further relates to a method for the treatment of an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any plutonium reduction operation, and in which one of the aforementioned N,N-dialkylamides or a mixture of same is used as an extractant. The invention is suitable for use in the treatment of spent nuclear fuel, in particular that comprising uranium (e.g. UOX) or uranium and plutonium (e.g. MOX).
C07C 233/05 - Carboxylic acid amides having carbon atoms of carboxamide groups bound to hydrogen atoms or to acyclic carbon atoms having nitrogen atoms of carboxamide groups bound to hydrogen atoms or to carbon atoms of unsubstituted hydrocarbon radicals with carbon atoms of carboxamide groups bound to carbon atoms of an acyclic saturated carbon skeleton having the nitrogen atoms of the carboxamide groups bound to hydrogen atoms or to acyclic carbon atoms
C22B 3/00 - Extraction of metal compounds from ores or concentrates by wet processes
C22B 60/00 - Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
4.
METHOD FOR THE TREATMENT OF AN AQUEOUS NITRIC SOLUTION USED RESULTING FROM DISSOLVING SPENT NUCLEAR FUEL, SAID METHOD BEING PERFORMED IN A SINGLE CYCLE AND WITHOUT REQUIRING ANY OPERATION INVOLVING THE REDUCTIVE BACK-EXTRACTION OF PLUTONIUM
COMMISSARIAT A L'ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Miguirditchian, Manuel
Sorel, Christian
Costenoble, Sylvain
Vanel, Vincent
Heres, Xavier
Baron, Pascal
Masson, Michel
Chareyre, Laurence
Abstract
The invention relates to a method for the treatment of an aqueous solution resulting from dissolving spent nuclear fuel in nitric acid, allowing the uranium and plutonium contained in the solution to be extracted, separated and decontaminated in a single cycle, without requiring any operation involving the reductive back-extraction of the plutonium. The invention is intended for the treatment of spent nuclear fuel comprising uranium and/or plutonium.
The invention relates to an apparatus (1) for thermal denitration of a uranyl nitrate hydrate to uranium trioxide UO3. The apparatus (1) comprises a burner (114) and a reaction chamber (110) configured to carry out thermal denitration of uranyl nitrate hydrate and to form uranium trioxide UO3 in the form of particles. The apparatus also comprises a separating chamber (120) suitable for separating UO3 particles from the gases resulting from the thermal denitration carried out in the reaction chamber (110), and at least one filter (130) configured for purifying the gases. The separating chamber (120) is a decanting chamber into which the reaction chamber (110) directly opens out. The filter (130) is capable of performing the separation at a temperature greater than or equal to 350°C. The invention also relates to use of such an apparatus, to a thermal denitration process and to UO3 particles obtained by means of such a process.
B01J 19/24 - Stationary reactors without moving elements inside
B01J 19/26 - Nozzle-type reactors, i.e. the distribution of the initial reactants within the reactor is effected by their introduction or injection through nozzles
B01J 4/00 - Feed devicesFeed or outlet control devices
B01J 8/00 - Chemical or physical processes in general, conducted in the presence of fluids and solid particlesApparatus for such processes
6.
TOOL FOR SMOOTHING IN A RADIOACTIVE ENVIRONMENT, COMPRISING A VIBRATING GRID
The invention relates to a smoothing tool (3) configured for smoothing glass frit in a radioactive environment, in an induction-melting cold crucible. Smoothing tool (3) comprising a rod (30), a grid (50) designed to be in contact with glass frit (7) to be smoothed, and at least one vibrator (37, 55, 56) configured to make the grid (50) vibrate. The grid (50) is mechanically connected to the rod (30).
The thermal solar power plant comprises a turbine (4) for generating electricity using vapor of a working fluid, a superheating assembly (8) comprising solar vapor superheaters (14, 16, 18) fluidly connected in series for superheating vapor using insolation and feeding the turbine with superheated vapor, and a heat storage assembly (10) thermally coupled to the superheating assembly (8) by at least one heat exchanger (30, 32) provided between two superheaters of the superheating assembly (8) in such manner as to take heat from superheated vapor and store heat.
A non-human-entry method for extracting a desired subsurface material such as ore, wherein an access hole is drilled from surface downwardly to the material, a high-pressure fluid injection tool is lowered with or after the drill string to the material and injected outwardly to disaggregate the material and form a cavity, and the material is optionally ground to a desired size by a drill bit or other means to enable suction up production tubing with a carrier fluid to the surface. The injection tool and grinding means are preferably part of an integrated bottom hole assembly at the lowermost end of a drill string, which may include surveying equipment to measure the cavity dimensions at intervals during target material disaggregation to allow fluid injection adjustment to seek to achieve a desired cavity geometry. Deck cementing is optionally employed for ground support.
E21B 7/18 - Drilling by liquid or gas jets, with or without entrained pellets
E21C 37/12 - Other methods or devices for dislodging with or without loading by making use of hydraulic or pneumatic pressure in a borehole by injecting into the borehole a liquid, either initially at high pressure or subsequently subjected to high pressure, e.g. by pulses, by explosive cartridges acting on the liquid
E21B 43/29 - Obtaining a slurry of minerals, e.g. by using nozzles
E21B 7/00 - Special methods or apparatus for drilling
E21B 43/34 - Arrangements for separating materials produced by the well
E21C 45/00 - Methods of hydraulic miningHydraulic monitors
9.
TEMPERATURE-MEASURING STICK WITH AN EASILY REPLACEABLE THERMOCOUPLE
The invention relates to a thermocouple (17) suspended from a part (26, 27) that can be locked onto a connecting section of the measuring stick, which comprises an opening in the form of a guiding cone (30) for inserting the thermocouple. The thermocouple is contained in a flexible cable (24) that can slide in a sheath (35) of the central compartment (16) which houses the thermocouple (17). A spring (34) can be added to lightly press the end of the thermocouple to the end of the housing thereof.
G01K 1/14 - SupportsFastening devicesArrangements for mounting thermometers in particular locations
G01K 7/02 - Measuring temperature based on the use of electric or magnetic elements directly sensitive to heat using thermoelectric elements, e.g. thermocouples
10.
PROCESS FOR MANUFACTURING A PELLET OF AT LEAST ONE METAL OXIDE
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventor
Vaudez, Stéphane
Abstract
The present invention relates to a process for sintering a compacted powder of at least one oxide of a metal selected from an actinide and a lanthanide, this process comprising the following successive steps, carried out in a furnace and under an atmosphere comprising an inert gas, dihydrogen and water: (a) a temperature increase from an initial temperature Ti up to a hold temperature TP, (b) maintaining the temperature at the hold temperature TP, and (c) a temperature decrease from the hold temperature TP down to a final temperature TF, in which the P(H2)/P(H2O) ratio is such that: - 500 < P(H2)/P(H2O) ≤ 50 000, during step (a), from Ti until a first intermediate temperature Ti1 between 1000°C and TP is reached, and - P(H2)/P(H2O)≤ 500, at least during step (c), from a second intermediate temperature Ti2 between TP and 1000°C, until TF is reached. The invention also relates to a process for manufacturing a pellet of at least one oxide of a metal selected from an actinide and a lanthanide, especially a nuclear fuel pellet.
C04B 35/50 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on rare earth compounds
C04B 35/51 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on compounds of actinides
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
11.
METHOD FOR PASSIVATING A NICKEL-ALLOY ELEMENT, ELEMENT OBTAINED BY SAID METHOD, AND METHOD FOR MANUFACTURING AN ASSOCIATED PRIMARY CIRCUIT OF A NUCLEAR REACTOR
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventor
Brussieux, Charles
Foucault, Marc
Engler, Nathalie
Perrin, Stéphane
Marchetti, Loic
Moeglen, Magali
Wouters, Yves
Abstract
The invention relates to a method (120) for passivating an element made of a nickel alloy, which is intended for limiting the corrosion and the cation release of said element in contact with a liquid. The method comprises a step of applying a thermal treatment (126) to at least one surface of the element, the thermal treatment (126) being carried out at a temperature of 500°C to 900°C, in an inert atmosphere made up of at least 99.9% of an inert gas or a mixture of inert gases. The inert atmosphere is at a pressure substantially equal to atmospheric pressure, and the thermal treatment (126) is carried out during a time ranging from ten to fifty hours.
A sealing device is provided to form a sealed region about one or more surfaces to be treated. The sealing device has an open end with a rim configured to matingly engage a treatment surface. The sealing device is braced both vertically and laterally, and the sealed region is flooded and pressurized. A peening nozzle and manipulating tooling are positioned within an interior volume of the sealing device. Pressurized fluid is ejected from the nozzle causing the formation of cavitation bubbles. The nozzle flow causes the cavitation bubbles to settle on the surfaces to be treated. The collapsing impact of the cavitation bubbles imparts compressive stress in the materials of the treatment surfaces.
C21D 7/06 - Modifying the physical properties of iron or steel by deformation by cold working of the surface by shot-peening or the like
C21D 10/00 - Modifying the physical properties by methods other than heat treatment or deformation
B23P 9/04 - Treating or finishing by hammering or applying repeated pressure
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
13.
CONTROL ROD DRIVE MECHANISM INNER DIAMETER ANNULUS ULTRA HIGH PRESSURE CAVITATION PEENING
A sealing member is provided to create a sealed region about an annulus formed between an inner body, such as a thermal sleeve, and an outer body, such as a control rod drive housing nozzle. Liquid is introduced into the sealed region to create a flooded region, which is pressurized to a desired level. A nozzle is provided into the flooded region, the nozzle being configured to fit within the annulus. Pressurized fluid is ejected from the nozzle, causing the formation of cavitation bubbles. The nozzle flow causes the cavitation bubbles to settle on the surfaces forming the annulus. The collapsing impact of the cavitation bubbles imparts compressive stress in the materials of the surfaces forming the annulus.
C21D 7/04 - Modifying the physical properties of iron or steel by deformation by cold working of the surface
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
B23P 9/02 - Treating or finishing by applying pressure, e.g. knurling
14.
LASER-BEAM EMISSION DEVICE SUITABLE FOR USE IN A CONTAMINATED ENVIRONMENT, INCLUDING A REMOVABLE SHEATH FOR REMOVABLY HOUSING AN OPTICAL UNIT
The invention relates to a laser-beam emission device (10) provided with an emission head including an optical unit (42) arranged in a generally longitudinal sheath (26), with a view to using same in contaminated environments. Said optical unit (42) includes a mirror (46) configured to deflect the initially longitudinal laser beam toward an outlet (20), thus enabling the laser beam to exit along an outlet axis (24) intersecting the longitudinal axis. The sheath (26) is configured to tightly confine the emission head such as to be impervious from dust. Thus, the emission head may be cleaned using decontamination products without the risk of damaging the optical unit (42) and the mirror thereof (46).
B23K 26/10 - Devices involving relative movement between laser beam and workpiece using a fixed support
B23K 26/14 - Working by laser beam, e.g. welding, cutting or boring using a fluid stream, e.g. a jet of gas, in conjunction with the laser beamNozzles therefor
A method of injecting platinum into a Boiling Water Reactor is provided. The Boiling Water Reactor includes a reactor core including a plurality of fuel rods having a zirconium alloy cladding. The method includes injecting a first platinate compound and a second platinate compound into a nuclear reactor. The first platinate compound is non- alkalizing and the second platinate compound includes an alkalizing element. The first platinate compound and the second platinate compound are injected such that the second platinate compound injected does not exceed a predetermined threshold or such that a value related to an alkalizing element of the second platinate compound does not exceed a predetermined threshold.
G21C 19/30 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products
16.
CYCLONIC SEPARATION DEVICE COMPRISING TWO CYCLONES LINKED BY AN OPTIMISED PIPE UNIT
ROLLS-ROYCE NUCLEAR FIELD SERVICES FRANCE (France)
Inventor
Jehanno, Jacky
Pilisi, Franck
Abstract
The invention proposes a device (10) for the cyclonic separation of solid particles contained in a fluid, comprising a primary cyclone chamber (12), a secondary cyclone chamber (14), an inlet channel (90) for fluid loaded with solid particles opening into the primary cyclone chamber, an outlet channel (18) for fluid cleaned of the solid particles connected to the secondary cyclone chamber, and a pipe unit (20) connecting the primary cyclone chamber to the secondary cyclone chamber and surrounded by the primary cyclone chamber. The pipe unit comprises a core (60) delimiting the secondary cyclone chamber and having at least one helical groove of which a bottom moves away from an axis (34) of the secondary cyclone chamber, moving towards the latter, and a cap (62) covering a part of the core in such a way as to delimit, with the groove, a channel (82) connecting the primary cyclone chamber to the secondary cyclone chamber.
B04C 5/103 - Bodies or members, e.g. bulkheads, guides, in the vortex chamber
B04C 5/107 - CoresDevices for inducing an air-core in hydrocyclones
B04C 5/13 - Construction of the overflow ducting, e.g. diffusing or spiral exits formed as a vortex finder and extending into the vortex chamberDischarge from vortex finder otherwise than at the top of the cycloneDevices for controlling the overflow
B04C 5/26 - Multiple arrangement thereof for series flow
17.
GEL COMPOSITIONS FOR DETECTING AND LOCATING RADIOACTIVE SURFACE CONTAMINATION OF SOLID SUBSTRATES, AND DETECTION AND LOCATION METHOD USING SAID GELS
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventor
Azar, Fadi
Faure, Sylvain
Messalier, Marc
Venault, Laurent
Abstract
The invention relates to gels for detecting and locating radioactive surface contamination of a solid material substrate, particularly via change in the color of the gels within the visible range or via softening, i.e. fading, of the color of the gels. The invention also relates to a method for detecting and locating radioactive surface contamination of a solid material substrate that uses said gels.
G01T 1/169 - Exploration, location of contaminated surface areas
18.
METHOD FOR SEPARATING THE COMPONENTS OF A SOLID SUBSTRATE COMPRISING A SUPPORT MADE FROM RARE EARTH OXIDE AND PARTICLES OF A NOBLE METAL, BY SELECTIVE DISSOLVING OF THE SUPPORT
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (France)
Inventor
Virot, Matthieu
Beaudoux, Xavier
Chave, Tony
Leturcq, Gilles
Nikitenko, Sergueï
Abstract
A method for treating a solid substrate comprising a support comprising, preferably consisting of, at least one oxide chosen from the oxides of a first metal chosen from the rare earths, the mixed oxides of a first metal chosen from the rare earths and at least one second metal different from the first metal, and the mixtures of an oxide of a first metal chosen from the rare earths and at least one oxide of at least one second metal different from the first metal, said support comprising at least one surface on which there are deposited particles consisting of at least one noble metal, in order to separate the first metal, the optional second metal, and the noble metal which constitutes the particles, said method comprising a step of selectively dissolving the support, during which the substrate is brought into contact with a dissolving solution comprising at least one mineral acid and at least one reducing agent for reducing the rare earth or rare earths of the support chosen from natural antioxidant molecules such as ascorbic acid, catechol, gallic acid and the mixtures of same, thereby obtaining a solution containing the first metal and the possible second metal in the dissolved state, in which there are suspended the particles consisting of the noble metal.
A dry FCVS for a nuclear reactor containment is provided. The dry FCVS includes a housing and a round and/or elongated aerosol filter inside the housing for removing contaminant aerosols from gas passing through the housing during venting of the containment. The housing includes at least one inlet portion configured for directing gas into the aerosol filter during the venting of the containment and an outlet portion for gas filtered by the aerosol filter during the venting of the containment. The dry filtered containment venting system is arranged and configured such that when a flow of gas through the outlet portion is closed off at least one of convective, radiant and conductive heat transfer removes decay heat of aerosols captured in the aerosol filter.
G21C 13/02 - Pressure vesselsContainment vesselsContainment in general Details
G21C 19/303 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for gases
The invention relates to a method of conditioning, by embedding in a cementitious matrix, a nuclear waste comprising magnesium metal and at least one material selected from graphite and steels, which method comprises the following steps: embedding the waste using a cementitious paste obtained by mixing a composition comprising a powder of a binder selected from hydraulic cements, vitrified blast-furnace slags and mixtures thereof, and an aqueous mixing solution; then - leaving the cementitious paste to harden in order to form the cementitious matrix; and is characterized in that the aqueous mixing solution comprises at least 1 mol/L of a strong base. The invention also relates to a composition suitable for being used in this conditioning method and also to a conditioning package obtained by said method. Applications: conditioning of waste from UNGG (for "Uranium Naturel - Graphite - Gaz carbonique [natural uranium - grapite - carbon dioxide]) or MAGNOX (for Magnesium Non OXidizing) nuclear reactors with a view to the storage thereof.
C04B 28/00 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
C04B 28/02 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
This invention provides an improved replacement nozzle configuration. The nozzle is provided in two pieces. A first nozzle piece is a relatively thin-walled cylinder that is inserted into the counterbored opening of a pressure vessel after the protruding portion of the original nozzle has been removed. A weld pad is attached to the pressure vessel, to which the first replacement nozzle piece is welded. Due to the reduced dimensions of the thin-walled first nozzle portion, a much smaller weld pad and pad-to-nozzle weld can be used. A second nozzle piece is positioned within the first nozzle piece and welded thereto. The existing instrumentation piping is connected to the free end of the second nozzle piece. This two-piece replacement nozzle can be implemented in approximately half the time required for the one-piece design.
B23K 31/02 - Processes relevant to this subclass, specially adapted for particular articles or purposes, but not covered by any single one of main groups relating to soldering or welding
A clamp for a boiling water reactor feedwater sparger is disclosed and claimed. The clamp assembly includes a base and cooperating bolt, a reaction arm, and a cross pin. With the exception of the cross pin, the parts are pre-assembled and then installed over the sparger pin head. The cross pin is then installed through the clamp base and through the sparger pin. The clamp bolt is then tightened, locking the clamp and sparger pin. The clamp provides an increased surface area that extends 360° around the sparger pin. This increased surface area reduces the likelihood of wear of the clamp or bracket during plant operation, and the clamp restores the position of the sparger pin head relative to the contact surface of the end bracket if the original pin head or bracket is worn.
A clamp for a boiling water reactor feedwater sparger is disclosed and claimed. The clamp assembly includes abuse and cooperating bolt, a reaction arm, and a cross pin. With the exception of the cross pin, the parts are pre-assembled and then installed over the sparger pin head. The cross pin is then installed through the clamp base and through the sparger pin. The clamp bolt is then tightened, locking the clamp and sparger pin. The clamp provides an increased surface area that extends 360° around the sparger pin. This increased surface area reduces the likelihood of wear of the clamp or bracket during plant operation, and the clamp restores the position of the sparger pin head relative to the contact surface of the end bracket if the original pin head or bracket is worn.
G21C 15/02 - Arrangement or disposition of passages in which heat is transferred to the coolant, e.g. for coolant circulation through the supports of the fuel elements
G21C 13/032 - Joints between tubes and vessel walls, e.g. taking into account thermal stresses
G21C 15/22 - Structural association of coolant tubes with headers or other pipes, e.g. in pressure tube reactors
G21C 17/017 - Inspection or maintenance of pipe-lines or tubes in nuclear installations
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
24.
METHOD FOR ACTIVATING U3O8 WITH A VIEW TO CONVERTING SAME INTO HYDRATED UO4
An activation method for activating U3O8 with a view to converting said uranium oxide into hydrated UO4 by means of a reaction with hydrogen peroxide H2O2, which involves carrying out the following successive steps: a) preparing an aqueous suspension containing a U3O8 powder and hydrogen peroxide; b) bringing the aqueous suspension containing a U3O8 powder and hydrogen peroxide into contact with ozone, thereby obtaining an aqueous suspension of an activated U3O8 powder; c) optionally, separating the activated U3O8 powder from the aqueous suspension. A method for converting U3O8 into hydrated UO4 of formula UO4, nH2O in which n is 2 or 4, comprising a least a step of adding hydrogen peroxide H2O2 to the aqueous suspension of an activated U3O8 powder obtained at the end of step b) of the activation method, or to an aqueous suspension prepared by placing the activated U3O8 powder obtained at the end of step c) of the activation method in suspension in water.
C01B 15/047 - Metal peroxides or peroxyhydrates thereofSuperoxidesOzonides of heavy metals
25.
PROCESS FOR PREPARING A METAL OXIDE POWDER, PROCESS FOR MANUFACTURING A METAL OXIDE PELLET, POWDER AND PELLET AS OBTAINED ACCORDING TO THESE PROCESSES AND USES THEREOF
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
Inventor
Martinez, Julien
Audubert, Fabienne
Clavier, Nicolas
Dacheux, Nicolas
Abstract
The invention relates to a process for preparing a powder of an oxide of at least one metal, each metal having an oxidation number of between (III) and (VI). This process comprises, successively and in this order: (a) the reaction, with a compound comprising a hydroxide, of an aqueous solution comprising, for each metal, at least one salt of the cation of said metal, (b) the separation of the precipitate obtained, (c) the bringing of the separated precipitate into contact with an organic protic polar solvent, (d) the elimination of the organic protic polar solvent by drying of the precipitate under vacuum. The invention also relates to a process for manufacturing a pellet of an oxide of at least one metal and also to the powder and pellet obtained according to these processes and to the uses thereof.
A non-human-entry method for extracting a desired subsurface material such as ore, wherein an access hole is drilled from surface downwardly to the material, a high-pressure fluid injection tool is lowered with or after the drill string to the material and injected outwardly to disaggregate the material and form a cavity, and the material is optionally ground to a desired size by a drill bit or other means to enable suction up production tubing with a carrier fluid to the surface. The injection tool and grinding means are preferably part of an integrated bottom hole assembly at the lowermost end of a drill string, which may include surveying equipment to measure the cavity dimensions at intervals during target material disaggregation to allow fluid injection adjustment to seek to achieve a desired cavity geometry. Deck cementing is optionally employed for ground support.
E21C 37/12 - Other methods or devices for dislodging with or without loading by making use of hydraulic or pneumatic pressure in a borehole by injecting into the borehole a liquid, either initially at high pressure or subsequently subjected to high pressure, e.g. by pulses, by explosive cartridges acting on the liquid
E21B 43/29 - Obtaining a slurry of minerals, e.g. by using nozzles
E21B 43/40 - Separation associated with re-injection of separated materials
27.
PROBE FOR MEASURING CONDUCTIVITY AT HIGH PRESSURE AND HIGH TEMPERATURE
This probe for measuring the conductivity of a fluid, comprising: an envelope (20) delimiting internally a measurement chamber (44), the envelope (20) exhibiting a first front aperture (42) surrounded by a first flange (22); a first electrode (24) engaged in the measurement chamber (44) through the first front aperture (42); a second flange (26) integral with the first electrode (24), the second flange (26) being arranged opposite the first flange (22) and exhibiting a second front aperture (56) in coincidence with the first front aperture (42); a second electrode (28) engaged in the measurement chamber (44) through the first front aperture (42) and the second front aperture (56). A third flange (30) integral with the second electrode (28) is arranged opposite the second flange (26), and a rigid fixing (32) holds the first, second and third flanges (22, 26, 30) to one another.
The invention relates to an energy storage device comprising a plurality of electrolytic cells (5) and a four-quadrant electrical inverter/charger (7). Each electrolytic cell (5) comprises a device (51) for recycling the gaseous hydrogen released in the cathode chamber, towards the anode chamber.
H01M 8/18 - Regenerative fuel cells, e.g. redox flow batteries or secondary fuel cells
H01M 10/36 - Accumulators not provided for in groups
H01M 10/42 - Methods or arrangements for servicing or maintenance of secondary cells or secondary half-cells
29.
PROCESS FOR THE SYNTHESIS OF A MIXED PEROXIDE OR HYDROXO-PEROXIDE OF AN ACTINYL AND OF AT LEAST ONE DOUBLY, TRIPLY OR QUADRUPLY CHARGED METAL CATION, MIXED PEROXIDE OR HYDROXO-PEROXIDE THUS OBTAINED AND USES THEREOF
The invention relates to a process for the synthesis of a mixed peroxide or hydroxo-peroxide of an actinyl and of at least one cation X1, in which the actinyl is a uranyl or a neptunyl and said at least one cation X1 is a doubly, triply or quadruply charged cation of a metal. This process comprises the reaction, in a solvent, of a salt of said at least one cation X1 with a compound C2 chosen from the mixed peroxides and hydroxo-peroxides of the actinyl and of at least one singly charged cation X2, as a result of which the compound C2 is converted into the peroxide or the hydroxo-peroxide by replacement of said at least one cation X2 with said at least one cation X1. It also relates to a process for the synthesis of a mixed oxide of an actinide chosen from uranium and neptunium, and of at least one metal capable of forming a doubly, triply or quadruply charged cation, which implements the preceding synthesis process. It also relates to a mixed peroxide or hydroxo-peroxide of an actinyl and of at least one doubly, triply or quadruply charged cation of a metal, and also to the use thereof for preparing a mixed oxide of an actinide and of at least this metal. Uses: manufacture of mixed oxides of actinides suitable for use in the manufacture of nuclear fuel pellets or of transmutation targets, decontamination of effluents contaminated with radionuclides from nuclear facilities, etc.
METHOD FOR PROCESSING SPENT NUCLEAR FUEL COMPRISING A STEP OF DECONTAMINATING THE URANIUM (VI) INTO AT LEAST ONE ACTINIDE (IV) BY COMPLEXING THIS ACTINIDE (IV)
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Bernier, Gilles
Sorel, Christian
Miguirditchian, Manuel
Balaguer, Coralie
Ameil, Estelle
Abstract
The invention relates to a method for processing spent nuclear fuel which method involves a step of decontaminating the uranium (VI) into one or more actinides (IV) and, more specifically, into neptunium and/or plutonium, by complexing this (these) actinide(s) (IV). This method involves a step of decontaminating the uranium (VI) into at least one actinide (IV), which decontamination step involves at least one operation of extracting actinide (IV) out of an organic phase, not miscible in water, and in which phase the uranium (VI) and the actinide (IV) are present, by bringing the organic phase into contact with an aqueous phase containing nitric acid and at least one complexing agent which complexes the actinides (IV) more strongly than uranium (VI), then separating the organic phase from the nitric aqueous phase and is characterized in that said at least one complexing agent is a diglycol amide. Applications: the processing of spent nuclear fuels.
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (C.N.R.S) (France)
UNIVERSITE JEAN MONNET SAINT ETIENNE (France)
Inventor
Perisse, Jocelyn
Morana, Adriana
Marin, Emmanuel
Macé, Jean-Reynald
Girard, Sylvain
Abstract
The invention relates to a method (110) for manufacturing a treated optical fiber (5) for temperature sensor. Said method includes the following steps: a) producing (120) an optical fiber (125) made of pure silica or silica doped with one or more element(s) selected from among fluorine and nitrogen; b) imprinting (130), using a femtosecond laser, at least one Bragg grating onto the optical fiber so as to produce an imprinted fiber (135), the Bragg grating longitudinally extending into one portion of the imprinted fiber and being suitable for reflecting light waves propagating along the imprinted optical fiber, the laser having power greater than or equal to 450 mW; and c) annealing (140) at least the imprinted fiber portion so as to produce the treated optical fiber. The invention also relates to the use of one such treated optical fiber in a temperature sensor.
The invention relates to an energy storage device comprising a plurality of electrolytic cells (5) and a four-quadrant inverter/charger (7). In each electrolytic cell (5), the negative electrode (21) and the positive electrode (15) are disposed facing one another, said electrolytic cell (1) comprising a device (23) for rotating the negative electrode (21) in relation to the positive electrode (11) about a rotation axis (X).
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (C.N.R.S) (France)
Inventor
Baudoin, Raphael
Zimmer, Laurent
Abstract
The invention relates to an optical system for determining, in three dimensions, the velocity profile and minimum concentration of particles in a flow, the system being characterised in that it comprises a first acquisition chain (100) comprising a first acquisition lens (130), a first photosensitive sensor (110), and a first shutter (120) formed by an opaque disk having at least two openings (121) in an arc, which can allow the transmission of light beams towards said first photosensitive sensor (110), said openings (121) being inscribed in the same circle.
A nuclear fuel cladding (16) is provided. The nuclear fuel cladding (16) includes a base cladding (18) and at least one nanomaterial layer (20) deposited on a surface of the base cladding (18), the nanomaterial layer (20) having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding (16) is also provided. The method includes depositing nanoparticles on a base cladding (18) to form at least one nanomaterial layer (18), the nanoparticles having an average grain size of between 5 to 400 nanometers.
C22F 1/00 - Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
G21C 3/07 - CasingsJackets characterised by their material, e.g. alloys
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
35.
PROCESS FOR PREPARING A POWDER COMPRISING A SOLID SOLUTION OF URANIUM DIOXIDE AND OF A DIOXIDE OF AT LEAST ONE OTHER ACTINIDE AND/OR LANTHANIDE ELEMENT
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Peter-Soldani, Guillaume
Grandjean, Stéphane
Abraham, Francis
Abstract
The invention relates to a process for preparing a powder of a solid solution of uranium dioxide and of a dioxide of at least one actinide and/or lanthanide element comprising a step of combustion of a solution comprising uranyl nitrate and at least one nitrate of the other actinide and/or lanthanide element and a nitrogen-containing fuel used in a specific predetermined amount in order to form, at the end of this step, said solid solution.
OPTICAL FIBRE, PROCESS FOR MANUFACTURING SUCH AN OPTICAL FIBRE AND MEASURING DEVICE EQUIPPED WITH SUCH AN OPTICAL FIBRE AND INTENDED TO DETECT HYDROGEN
AGENCE NATIONALE POUR LA GESTION DES DÉCHETS RADIOACTIFS (France)
AREVA (France)
Inventor
Lesoille, Sylvie
Bertrand, Johan
Mace, Jean-Reynald
Perisse, Jocelyn
Leparmentier, Stéphanie
Auguste, Jean-Louis
Delaizir, Gaelle
Abstract
The invention relates to an optical fibre (100) for detecting and/or quantitative measurement of hydrogen, comprising a fibre core (110) and at least one optical cladding (120) surrounding the core (110), at least one of the core (110) and the optical cladding (120) being made mainly of silica glass. The optical fibre (100) comprises palladium in metal form included in at least one fibre portion made mainly of silica glass, said portion being selected from the core (110) and the optical cladding (120). The invention also relates to a process for manufacturing such an optical fibre (100), to the use of this optical fibre (100), and to a system for detecting and/or quantitative measurement of hydrogen comprising such an optical fibre (100).
G01N 21/77 - Systems in which material is subjected to a chemical reaction, the progress or the result of the reaction being investigated by observing the effect on a chemical indicator
A method of operating a nuclear reactor is provided. The method includes defining a layer increment (24) of a deposit layer (10) modeling a deposit on a heat transfer surface (12) of the nuclear reactor (200); periodically updating a thickness of the deposit layer (10) by adding the layer increment (24) to the deposit layer (10); recalculating properties of the deposit layer (10) after each layer increment (24) is added to the deposit layer (10); determining a temperature related variable of the heat transfer surface (12) as a function of the recalculated properties of the deposit layer (10); and altering operation of the nuclear reactor (200) when the temperature related variable of the heat transfer surface (12) reaches a predetermined value. A method of modeling a deposit on a heat transfer surface (12) of a nuclear reactor (200) is also provided.
F01K 13/02 - Controlling, e.g. stopping or starting
G21D 3/10 - Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
The invention relates to a welding device (10) for welding the opening (16) of a plastic bag (12) in order to seal same hermetically, which comprises: a lower jaw (18) and an upper jaw (20) between which the bag (12) is clamped; at least one heating wire (22); and means (30) for clamping the upper jaw (20) against the lower jaw (18) which comprise a plurality of magnetic elements (32) with permanent magnets, and in which each magnetic element (32) comprises a first stationary permanent magnet (34) and a second permanent magnet (36) which is mounted so as to be movable relative to the first permanent magnet (34) between a locking position in which the combination of the magnetic fields produced by the two permanent magnets (34, 36) produces a high-intensity magnetic field in the upper jaw (20) and a released position in which the combination of the magnetic fields produced by the two permanent magnets (34, 36) produces a low-intensity magnetic field in the upper jaw (20), allowing an operator easily to separate the two jaws after welding the bag.
The method according to the invention makes it possible to use a rather small facility to incinerate, melt and vitrify mixed waste (30) introduced into a reactor (10), using a basket (18) which in turn passes through an airlock (12). Plasma torches (14) burn all of the waste (30) contained in the basket (18). Said waste is then lowered into a molten bath of a furnace (20) with an inductor (24) comprising a container forming a crucible (23). The facility is completed by a combustion gas treatment chain. The furnace (20) can be disassembled, after a treatment series of several baskets (18) of waste (30), to disassemble the crucible-forming container (23) from the furnace (20). The invention is applicable to the treatment of various radiologically contaminated and/or toxic mixed waste.
F23G 5/32 - Methods or apparatus, e.g. incinerators, specially adapted for combustion of waste or low-grade fuels in which the waste or low-grade fuel is subjected to a whirling movement, e.g. cyclonic incinerators
F23G 7/00 - Methods or apparatus, e.g. incinerators, specially adapted for combustion of specific waste or low grade fuels, e.g. chemicals
F27B 14/06 - Crucible or pot furnacesTank furnaces heated electrically, e.g. induction crucible furnaces, with or without any other source of heat
A steam generator anti-vibration bar (A.VB) that extends across multiple rows of tubes and contains a string of sensors is disclosed and claimed. The instrumented anti-vibration bar includes a housing and cover that cooperate to enclose the sensors. The sensors capture data resulting from the fluid flow passing through the steam generator during plant operation. Exemplary sensors that may include: strain gauges to measure loads imposed on the AVBs by the tubes; temperature sensors to sample thermal-hydraulic conditions within the tube bundle; pressure and flow detectors to sample hydraulic conditions within the tube bundle; inductive coils to measure in-plane and out-of-plane motion; and accelerometers to measure AVB motions imposed by surrounding tubes. The captured data is transmitted out of the steam generator in known fashion.
F22B 37/20 - Supporting arrangements, e.g. for securing water-tube sets
F28F 9/013 - Auxiliary supports for elements for tubes or tube-assemblies
F28D 7/06 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits having a single U-bend
The present invention provides a drain plug assembly that prevents significant quantities of corium from entering the drain line. By protecting the drain line (101), essentially no high-activity fission products would be released to the reactor building or the environment during a severe accident. The ceramic drain plug assembly includes a drain plug base (10) and a drain plug (20) supported by a steel pedestal (30). The lower surface of the plug has a spherical shape such that the plug can be positioned within the base to block access to the drain opening provided in a central portion of the base. During normal operation conditions, the plug is retained above the base by the pedestal. During a severe accident, when corium comes into contact with the pedestal, it will melt rapidly and the drain plug will drop by gravity, effectively closing the sump drain opening and preventing the flow of corium into the drain line.
The assembly comprises: a source (3) generating a flow to be purified (5); a solar evaporation unit (7); a transfer duct (9); a device (11) for heating the transfer duct (9); and a mechanical ventilation device (13) for circulating air inside the solar evaporation unit (7).
A fuel rod (1) for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding (6) configured to retain a nuclear fuel (20) therein. The cladding (6) includes an elongate hollow tube (10). Fiber layers (12) are positioned around the outside surface of the tube (10) or within the tube forming an integral part thereof. Both the tube (10) and the fibers (8) are formed of a ceramic material. A fuel assembly (2) including a plurality of such fuel rods (1) is also disclosed and claimed.
The present invention relates to a tool (1) for the manufacture of calibrated fissures in a workpiece (30) having a body (32) delimited by two ends (31, 33), characterized in that this tool comprises: a supporting structure (20) comprising a means (21) able to accept and hold a first end (33) of said workpiece (30) in place; an expander (10) positioned between the supporting structure (20) and the second end (31) of the workpiece (30), the expander (10) comprising a first through-orifice (12) through which the body (32) of the workpiece (30) can pass, said expander (10) being made of a material that has a co-efficient of expansion higher than the co-efficient of expansion of the supporting structure (20) and of the workpiece (30) so that the expander (10) can apply a strain to the second end (31) of said workpiece (30) through expansion of this expander if the temperature increases.
G01M 3/00 - Investigating fluid tightness of structures
G01M 3/20 - Investigating fluid tightness of structures by using fluid or vacuum by detecting the presence of fluid at the leakage point using special tracer materials, e.g. dye, fluorescent material, radioactive material
G01N 33/00 - Investigating or analysing materials by specific methods not covered by groups
A permanent seal for a refueling canal of a nuclear power plant. The seal includes a support structure and a membrane. The support structure includes a first annular plate with ribs connected to and extending from a lower surface of the annular plate. The support structure is positioned atop the shield wall on the refueling canal floor, encircling and positioned near the annulus. The membrane includes a first end that is connected to the seal ledge and a second end that is connected to the refueling canal floor. The membrane has a stepped profile, with side walls extending substantially perpendicularly from a central annular plate to form a pocket configured to fit over the support structure. Loads imparted to the membrane are transferred through the support structure annular plate and ribs to the refueling canal floor.
G21C 13/028 - Seals, e.g. for pressure vessels or containment vessels
G21C 13/073 - Closures for reactor-vessels, e.g. rotatable
46.
SYSTEM AND METHOD FOR ANALYSING, BY LASER INDUCED PLASMA SPECTROSCOPY, THE COMPOSITION OF A SURFACE LAYER AND FOR TAKING SAMPLES WITH A VIEW TO PERFORMING COMPLEMENTARY ANALYSES
System for analysing, by laser induced plasma spectroscopy, the composition of the surface layer of a material and for taking samples with a view to performing complementary analyses or examining this superficial layer, and method related thereto. The system comprises a single pulse laser (6), for generating a pulse laser beam, able to interact with the superficial layer of the material and produce a plasma on the surface of the material (4); a device (10, 12) for focusing the laser beam onto the surface of the material; a device (18, 20) for collecting the light emitted by the plasma; and a device (22) for analysing the spectrum of the collected light and for determining the elementary composition (nature and relative concentration of the elements) of the superficial layer from this spectral analysis. According to the invention, it furthermore comprises a device (30, 32, 34) for sucking up and collecting particles representative of the superficial layer, extracted from the latter, under the effect of the laser beam, with a view to performing qualitative or quantitative complementary analyses or examininations on the basis of said particles.
G01N 21/71 - Systems in which the material investigated is excited whereby it emits light or causes a change in wavelength of the incident light thermally excited
G01N 1/22 - Devices for withdrawing samples in the gaseous state
G01N 1/04 - Devices for withdrawing samples in the solid state, e.g. by cutting
47.
METHOD FOR CONTROLLING THE GAIN AND ZERO OF A MULTI-PIXEL PHOTON COUNTER DEVICE, AND LIGHT-MEASURING SYSTEM IMPLEMENTING SAID METHOD
According to the invention, which is especially applicable in high-energy physics, the signals supplied by the device (12) are collected over pre-defined periods until a pre-defined total measuring time is reached, a histogram of amplitudes is formed from the collected signals, the positions of two consecutive peaks, measurable on the histogram, are determined, and an error signal is produced, equal to the difference between the two peaks, which is used to adjust the voltage supplying the device, in such a way as to maintain the difference equal to a pre-defined nominal value.
METHOD FOR MEASURING DOSAGE BY MEANS OF A RADIATION DETECTOR, ESPECIALLY AN X-RADIATION OR GAMMA-RADIATION DETECTOR, USED IN THE SPECTROSCOPIC MODE, AND DOSAGE MEASUREMENT SYSTEM USING SAID METHOD
According to the invention, which is especially applicable in high-energy physics, an energy range and a dosage type H are selected, a radiation detector (14) of a given type is used, spectra measured by the detector are established for various radiations of the given type, the energies of which are within the selected range and the respective dosages of which are known, and on the basis of the spectra, a weighting function is established, i.e. a correspondence between an average dosage increment and an average energy, stored in the detector. This allows a person provided with a dosimeter identical to the detector to know, at all times, the average absorbed dosage flow expressed in the quantity H.
The invention relates to a device (1) for measuring the radiological activity deposited in a sea bed, comprising a sealed case (20) for a radiological detector (2), means (4) forming a truncated cone, containing a material suitable for having, passing therethrough, radiation to be measured by said radiological detector (2) comprising a small base (44) and a large base (42), the latter forming a surface (42) for letting in the radiation to be measured, said cone being sealingly assembled to said case, the small base (44) being arranged on the inlet surface side of the detector, the large base (42) being arranged opposite the sea bed.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Boen, Roger
Bonnetier, Armand
Abstract
The invention relates to an induction melting furnace comprising shell (7) and a lower sole (11) forming the main part of the structure. In addition, the furnace comprises a removable inner crucible (1) formed by an inner layer (4) that is resistant to heat and to the aggressive nature of the molten bath (20), an outer layer (6) defining the crucible, and an intermediate insulating layer (5). The crucible (1) is a single-use crucible and can be stored, together with its charge, in a suitable container. Heat losses are low, even if the shell (7) is cooled. In addition, stresses due to differential thermal expansions are also very low.
F27D 11/06 - Induction heating, i.e. in which the material being heated, or its container or elements embodied therein, form the secondary of a transformer
The bin of the invention can be used to incinerate waste for a period of more than fifteen minutes in an incinerator without the waste being pre-melted, in particular as it is being inserted into the incinerator. The bin is mainly formed by a fibreglass casing (10) and is preferably reinforced with a lightweight metal structure (12) positioned outside or inside the casing or built into same. The assembly is topped with a gripping handle (14) and the upper portion of the assembly is stiffened by a metal tube (16) to which the lightweight metal structure (12) is secured, with a base formed by a drip pan (18) being secured to the base of the lightweight metal structure (12). The invention is suitable for the incineration of toxic waste.
The invention relates to a method for sorting, in a continuous flow, contaminated materials (100), which includes: conveying materials (100) from a point (A) to a point (B) by means of a conveyor (120); measuring the radioactive activity, by means of a first sensor (140), between the points (A) and (B) on the top surface (FSUP) of the first conveyor (120); and sorting the materials (100) by means of a sorting device (130). Said method is essentially characterized by: measuring the radioactive activity of the contaminated material by means of a second sensor (141), either on the top surface (FSUP) of the conveyor (120) and upstream from the point (A), or below the bottom surface (FINF) of said conveyor; calculating a differential measurement between a measurement from the second sensor (141) and from the first sensor (140); and restricting the sorting to the comparison between a threshold value and the measurement from the first sensor (140) or the differential measurement.
A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided.
The present invention relates to a system (100) for the in-line characterisation of corrosion products in a cooling system of a nuclear reactor, said characterisation system having a tube (10) connected to the cooling system of the reactor in which the coolant circulates, the system comprising at least two filtering means (13, 14, 15) in series, the downstream filtering means having a smaller pore size than the filtering means located upstream, the filtering means (13, 14, 15) being suitable for the coolant to pass therethrough; differential pressure sensors (16) combined with each of the filtering means (13, 14, 15) making it possible to determine in-line the obstruction rate of each of the filtering means.
The present invention relates to a system (100) for characterizing products of corrosion which are present in a nuclear reactor cooling circuit, said characterization system having a pipe (20) connected to the reactor cooling circuit (1) through which the coolant flows, the system comprising at least two filtration means (13, 14, 15) in series, the downstream filtration means having a smaller pore size than the filtration means situated upstream, the filtration means (13, 14, 15) being able to have the cooling fluid passed through; differential-pressure sensors (16) associated with each of the filtration means make it possible to determine the extent to which each of the filtration means is plugged; a temperature-regulating means (22, 23) regulating the temperature of said liquid flowing through the pipe (20).
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
UNIVERSITE AIX-MARSEILLE (France)
Inventor
Benedetti, Arnaud
Sornay, Philippe
Brothier, Méryl
Nicolas, Maxime
Dubrujeaud-Dalloz, Blanche
Abstract
The invention relates to a device and to a method for transporting powder made up of faceted particles on a vibrating conveyor surface (1) inclined by an angle Θ, in which method and device - Ra ≤ 0.2 μm, where Ra is the arithmetic mean deviation of the conveying surface (1); - θ ≤ 2/3 α, where α is the angle of friction of said powder on said conveying surface (1); - the vibrations are generated in the plane of said conveying surface (1) and in a direction (y) perpendicular or substantially perpendicular to the direction (x) of greatest gradient of the conveying surface (1) and have a frequency comprised between 5 Hz and 2kHz and an acceleration in excess of 1g.
This method comprises a step of studying the weld (10) metallurgically; a step of dividing the weld (10) into a plurality of theoretical blocks and of jointly determining an elastic Hooke tensor for each theoretical block; a step of simulating by calculation the propagation of at least one incident ultrasound wave (73) through the weld (10); a step of simulating at least one reference diffracted ultrasound wave; a step of emitting at least one incident ultrasound wave (73) into the weld (10); a step of measuring each diffracted ultrasound wave (75); and a step of comparing each reference diffracted ultrasound wave with each measured diffracted ultrasound wave (75).
The invention relates to an anionically conductive electrolyser comprising an electrochemical cell (10) formed by a solid electrolyte (13) formed by a ceramic; a first electrode (11) forming the anode of said electrochemical cell (10); and a second electrode (12) forming the cathode of said electrochemical cell (10), said solid electrolyte (13) being arranged between said first electrode (11) and said second electrode (12). Said electrolyser is characterised in that said solid electrolyte (13) consists of zirconium oxide doped with erbium oxide.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (France)
UNIVERSITE DE MONTPELLIER II (France)
Inventor
Navarro, Nathalie
Pochon, Patrick
Nikitenko, Sergueï
Chave, Tony
Abstract
The invention relates to a method for breaking down, by oxidation, at least one organic compound, such as a carboxylic acid, in a liquid medium at a high concentration, i.e. no lower than 0.05 mol/L, in which the liquid medium is placed in contact, at atmospheric pressure and at room temperature, with a gas that contains oxygen, in the presence of a solid catalyst that enables the breakdown of the organic compound by the oxygen, and the liquid medium is simultaneously subjected to ultrasonic waves.
A composite basket assembly (10) for radioactive fuel containment includes a plurality of cast disks (20) disposed together in face-to-face relationship by connecting rods (40) extending through the disks. The disks are formed with interior cells (124) and a grid structure (122) to form discrete compartments for individual fuel assemblies. A neutron-absorbing material (34) is incorporated into the disks to absorb radioactive emissions from the stored fuel.
A horizontal storage module (HSM) assembly generally includes a base portion including a plurality of segments that are vertically layered on top of each other and a lid portion. A method of constructing an HSM assembly generally includes forming a plurality of segments for the base portion of the HSM assembly, and vertically stacking the segments.
The present invention relates to a device for handling cases and boxes contained in the cases, having a housing intended to receive a case, said housing being closed at a first longitudinal end and open at a second longitudinal end, a holding device (14) mounted in the region of the second end of the housing, said holding device (14) having two clamping jaws, said clamping jaws applying a clamping force to the case (E), an actuator for opening and closing said jaws, two abutment jaws (36, 38), each (36, 38) of which is carried by a clamping jaw and being articulated freely about and with respect to the clamping jaw, springs (40) connecting said abutment jaws (36, 38) such that the opening of the clamping jaws causes the opening of the abutment jaws (36, 38) and the abutment jaws (36, 38) may be opened independently of the clamping jaws.
A travel system (20) for a canister storage, transfer, or transport system generally includes a support structure (22), at least one traveling device (24) for preparing, inspecting, and/or repairing the canister, and a base ring (26) for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure.
G01N 27/90 - Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating magnetic variables for investigating the presence of flaws using eddy currents
G01N 21/90 - Investigating the presence of flaws, defects or contamination in a container or its contents
64.
Eddy current method for the characterization of broached tube support plate blockage
A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range.
A method for recycling AglnCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AglnCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AglnCd absorber bar.
A position-indexed storage device comprising a support (1) and a basket (2) mounted on the support (1), the basket (2) comprising a plurality of cells (4) distributed about a longitudinal axis (X), the basket (2) comprising a central passage (8) of longitudinal axis (X), the support comprising a shaft (26) of longitudinal axis (X), the shaft (26) being housed in the passage (8) such that a relative movement between the basket (2) and the support (1) along the longitudinal axis (X) is allowed, and mechanical movement means for moving the basket relative to the support by a given angle about the longitudinal axis (X) are supported by the inner surface of the passage (8) and by the outer surface of the shaft (26), said mechanical movement means being activated in each cycle comprising a relative movement of the basket (2) and the support (1) away from and towards each other along the longitudinal axis (X).
A tool for inspecting the integrity of fasteners in their environment of use and methods of performing such inspections are disclosed and claimed. The tool includes a probe that matches the internal socket by which the fastener is coupled to the workpiece. The probe contains ultrasonic transducers on flat portions corresponding to flat portions of the socket. The transducers induce angled ultrasonic beams into the fastener to detect flaws therein. The beams are angled so they can be directed to the areas of interest at the head to shank region of the fastener. The presence of a defect such as a crack is determined based on the reply/echoes of the imparted ultrasonic beams.
G01N 29/00 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object
G01N 29/28 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object Details providing acoustic coupling
G01D 11/30 - Supports specially adapted for an instrumentSupports specially adapted for a set of instruments
G01N 29/07 - Analysing solids by measuring propagation velocity or propagation time of acoustic waves
G01N 29/22 - Investigating or analysing materials by the use of ultrasonic, sonic or infrasonic wavesVisualisation of the interior of objects by transmitting ultrasonic or sonic waves through the object Details
68.
A SOLAR CONCENTRATOR FOR A SOLAR ENERGY COLLECTOR AND A METHOD OF ADJUSTING THE SOLAR CONCENTRATOR
This solar concentrator (6) comprises at least one row (12) of reflectors (14) comprising mirrors (34), said row (12) extending along a longitudinal direction (L), the reflector (14) of said row (12) being pivotally supported with respect to the ground about a pivot axis (A-A), said row comprising at least a first reflector (14) and a second reflector (14) and a connecting arrangement (42, 44) which connects adjacent longitudinal ends (26) of the first and second reflector assemblies (14), the connecting arrangement (42, 44) allowing a relative movement between the first and second reflector assemblies (14).
A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar.
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
G21C 21/18 - Manufacture of control elements covered by group
The invention relates to a reflector panel (20) for a solar power plant, comprising: - a front reflective sheet (22), - a back sheet (24), the front (22) and back (24) sheets defining a cavity (34) between them, and - an inner frame structure (26), extending in the cavity (34). The inner frame structure (26) comprises at least two elongated beams (40) parallel to and spaced apart from one another, each beam (40) extending along each sheet (22, 24) and keeping the sheets (22, 24) spaced apart from one another, the beam (40) having a constant thickness between the sheets (22, 24). The invention also relates to a manufacturing method thereof, and a reflector assembly comprising such a reflector panel.
F24S 23/70 - Arrangements for concentrating solar rays for solar heat collectors with reflectors
F24S 23/74 - Arrangements for concentrating solar rays for solar heat collectors with reflectors with trough-shaped or cylindro-parabolic reflective surfaces
F24S 23/77 - Arrangements for concentrating solar rays for solar heat collectors with reflectors with flat reflective plates
71.
USE OF A MIXTURE COMPRISING ERBIUM AND PRASEODYMIUM AS A RADIATION ATTENUATING COMPOSITION, RADIATION ATTENUATING MATERIAL, AND ARTICLE PROVIDING PROTECTION AGAINST IONISING RADIATION AND COMPRISING SUCH A COMPOSITION
The invention relates to the use of a mixture comprising erbium and praseodymium as a radiation attenuating composition, i.e. as a composition that can attenuate ionising radiation, in particular X- and gamma-type electromagnetic radiation. The invention also relates to a radiation attenuating material comprising an erbium- and praseodymium-based composition, as well as a protective article which provides group or individual protection against ionising radiation and comprises said material. The invention is suitable for use in nuclear medicine (scintigraphy, radiotherapy, etc.) radiology, medical imaging, the nuclear industry, etc.
The present invention relates to a method for formulating a ceramic powder for producing a proton-conducting electrolytic membrane (12) for an electrochemical cell (10), said method comprising the following steps: forming a suspension of a previously synthesized, unprocessed ceramic powder in a solvent having a hydrogen potential greater than 7 so as to produce a slip, said unprocessed ceramic powder comprising agglomerates consisting of a plurality of ceramic grains; crushing said agglomerates contained in said slip so as to reduce said agglomerates; and drying said slip so as to mechanically separate said agglomerates of said solvent and recover said dried agglomerates.
C04B 35/462 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on titanium oxides or titanates based on titanates
C04B 35/48 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxides based on zirconium or hafnium oxides or zirconates or hafnates
C04B 35/50 - Shaped ceramic products characterised by their compositionCeramic compositionsProcessing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on rare earth compounds
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Cuer, Frédéric
Castellani, Romain
Abstract
The invention relates to a decontamination gel consisting of a colloidal solution including: at least one inorganic viscosity-increasing agent, at least one agent for rapidly altering the viscosity, which, when exposed to at least one stimulus, causes a rapid and large variation in the viscosity of the gel, at least one active decontamination agent, at least one surfactant, and optionally at least one superabsorbent polymer, the remainder consisting of a solvent. The invention also relates to a method for decontaminating a part, in particular a part that is small and/or has complex shape, by coating same with a film of said gel.
Device for handling objects in a glove box comprising a carriage (2) for supporting the items that are to be handled, a base (6) with respect to which the carriage (2) can move along a horizontal axis (X), means of driving the carriage (2) along the axis (X), these drive means comprising an electric motor (14) arranged in such a way that its drive shaft is orthogonal to the axis (X) and projects away from the base (6), a transmission shaft (18) parallel to the motor (14), a rack (22) fixed to the base (6) along the axis (X) and a pinion (24) in direct engagement with the transmission shaft (18) and meshing with the rack (22), a drive belt (20) mechanically connecting the drive shaft of the motor (14) to the transmission shaft (18), the electric motor (14) being disengageable and the carriage being movable by hand along the axis (X).
The invention relates to the field of packaging of radioactive waste by cementing. More specifically, the invention relates to the use of crystalline silica, mixed with cement powder, to reduce the heating of the cement paste caused by the hydration of said powder, during a process of packaging of radioactive waste. The invention also relates to a formulation for the packaging of radioactive waste by cementing, which comprises such silica. The invention further relates to a method for packaging radioactive waste implementing said formulation, and to a package for packaging of radioactive waste which is obtained by this method. Applications: processing of low- and medium-activity waste produced downstream of the nuclear fuel cycle.
C04B 28/02 - Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
The present invention relates to an acoustic sensor (10) for measuring the linear movement of an internal structure (20) of a nuclear reactor using sound waves, comprising: an electro-acoustic transducer (14) capable of emitting said sound waves; and a waveguide (5) capable of guiding said sound waves emitted by said transducer (14) toward a measurement area of the internal structure (20), wherein said acoustic sensor (10) is characterized in that said waveguide (5) is capable of guiding the reflected wave and said waveguide (5) is secured to said measurement area (20) and arranged so as to be capable of extending or retracting in accordance with the movement of said internal structure (20) of the nuclear reactor.
The direct solar steam generator (2) is of the type comprising a solar evaporator (4) having an evaporator circuit (12) for circulation of a working fluid, an evaporator inlet pipe (8) for supplying fluid to the evaporator circuit (12) and an evaporator outlet pipe (10) for collecting the working fluid exiting the evaporator circuit (12), and a solar concentrator (6) for concentrating solar energy towards the evaporator circuit (12). According to one aspect if the invention, the steam generator (2) comprises a fluid arrangement (26) configured to allow forming a static liquid seal in the outlet pipe (10) using the working fluid.
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (C.N.R.S) (France)
Inventor
Sala, Béatrice
Grasset, Frédéric
Tetard, Elodie
Rahmouni, Kamal
Goeuriot, Dominique
Bendjeriou, Baroudi
Takenouti, Hisasi
Abstract
The present invention relates to a proton-conductive electrochemical cell (10), comprising an electrolytic membrane (13) made of a ceramic and an electrode (11, 12) made of a cermet, said electrochemical cell (10) being obtained directly by a method of co-sintering a ceramic layer, capable of forming the electrolytic membrane (13), and a cermet layer, capable of forming the electrode (11, 12), in a sintering tool at a sintering temperature of the ceramic that makes it possible to render said ceramic layer, capable of forming the electrolyte (13), gas-tight, wherein said cell (10) is characterised in that said cermet consists of the mixture of a ceramic and an electronically conductive passivatable alloy including at least 40 mol % chromium capable of forming a passive layer, the nature and the chromium content of said passivatable alloy enabling said electrochemical cell to be co-sintered with a membrane densification of more than 90% without melting said alloy.
C25B 1/04 - Hydrogen or oxygen by electrolysis of water
C25B 9/10 - Cells comprising dimensionally-stable non-movable electrodes; Assemblies of constructional parts thereof with diaphragms including an ion-exchange membrane in or on which electrode material is embedded
C25B 11/04 - ElectrodesManufacture thereof not otherwise provided for characterised by the material
H01M 8/12 - Fuel cells with solid electrolytes operating at high temperature, e.g. with stabilised ZrO2 electrolyte
The present invention relates to a method for treating CO2 by electrochemical hydrogenation, said method comprising: a step of transferring heat from a heating means (160) towards a proton-conductive electrolyser (110) such that said electrolyser (110) reaches an operating temperature suitable for electrolysing steam; a step of feeding the CO2 produced by said heating means (160) at the cathode of the electrolyser; a step of feeding the steam at the anode; a step of oxidising the steam at the anode; a step of generating protonated species in the membrane with proton conduction; a step of migrating said protonated species into said proton-conductive membrane; a step of reducing said protonated species on the surface of the cathode into reactive hydrogen atoms; and a step of hydrogenating the CO2 on the surface of the cathode of the electrolyser (110) by means of said reactive hydrogen atoms, said hydrogenation step enabling the formation of CxHyOz compounds, where x≥1; 0
C25B 15/08 - Supplying or removing reactants or electrolytesRegeneration of electrolytes
B01D 53/32 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by electrical effects other than those provided for in group
80.
ELECTRODE FOR ELECTROCHEMICAL CELL AND METHOD OF MANUFACTURING SUCH AN ELECTRODE
CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (C.N.R.S) (France)
Inventor
Sala, Béatrice
Grasset, Frédéric
Tetard, Elodie
Rahmouni, Kamal
Sirat, Abdelkader
Goeuriot, Dominique
Bendjeriou, Baroudi
Takenouti, Hisasi
Abstract
The invention relates to an electrode for an electrochemical cell which exhibits good electron conductivity and good chemical conductivity, as well as good cohesion with the solid electrolyte of the electrochemical cell. To do this, this electrode is made from a ceramic, which is a perovskite doped with a lanthanide having one or more degrees of oxidation and with a complementary doping element taken from the following group: niobium, tantalum, vanadium, phosphorus, arsenic, antimony, bismuth.
The present invention relates to a method for generating hydrogen and oxygen adsorbates by steam electrolysis at 200 to 800°C using an electrolysis cell (30) comprising a solid electrolyte (31) which is made of a proton-conducting ceramic and which is arranged between an anode (32) and a cathode (33), each of which comprises a proton-conducting ceramic, and the ratio of the electroactive surface to the geometric surface of each of which is equal to at least 10, said method comprising the following steps: circulating a current between the anode (32) and the cathode (33), wherein the density of the current is no less than 500 mA/cm2; inserting water in the form of steam, which is fed under pressure to the anode (32); oxidizing said water in the form of steam at the anode (32), and generating highly reactive oxygen at the anode (32) after said oxidation; generating protonated species in the electrolyte (31) after said oxidation and migrating said protonated species in the electrolyte (31); and reducing said protonated species at the surface of the cathode (33) in the form of reactive hydrogen atoms.
C25B 1/04 - Hydrogen or oxygen by electrolysis of water
C25B 11/04 - ElectrodesManufacture thereof not otherwise provided for characterised by the material
C25B 9/10 - Cells comprising dimensionally-stable non-movable electrodes; Assemblies of constructional parts thereof with diaphragms including an ion-exchange membrane in or on which electrode material is embedded
C25B 11/03 - ElectrodesManufacture thereof not otherwise provided for characterised by shape or form perforated or foraminous
C25B 3/04 - Electrolytic production of organic compounds by reduction
C10G 45/44 - Hydrogenation of the aromatic hydrocarbons
C10G 45/58 - Refining of hydrocarbon oils using hydrogen or hydrogen-generating compounds to change the structural skeleton of some of the hydrocarbon content without cracking the other hydrocarbons present, e.g. lowering pour pointSelective hydrocracking of normal paraffins
C10G 47/22 - Non-catalytic cracking in the presence of hydrogen
B01D 53/32 - Separation of gases or vapoursRecovering vapours of volatile solvents from gasesChemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases or aerosols by electrical effects other than those provided for in group
82.
METHOD FOR TREATING AN AQUEOUS EFFLUENT TO ABATE THE DISSOLVED HEAVY METAL AND/OR RADIOACTIVE SUBSTANCE CONTENT OF SAME
VEOLIA WATER SOLUTIONS & TECHNOLOGIES SUPPORT (France)
AREVA NC (France)
Inventor
Paillard, Hervé
Mizuno, Hisamatsu
Miura, Kunio
Prevost, Thierry
Piot, Grégoire
Abstract
Method for treating water to abate the heavy metal and/or radioactive substance content of same, said method comprising a step of introducing said water into a first contact tank (13), a first step of co-precipitation of at least some of said heavy metals and/or said radioactive substances by injecting at least two different precipitating agents (14, 15) into said first tank, at least one of said precipitating agents being a preformed precipitate, a first coagulation and/or flocculation step in a first coagulation and/or flocculation area (17) for the water coming from the first contact tank (13), a first step of solid/liquid separation of the water coming from the first coagulation and/or flocculation step, thus producing a first clarified liquid and a first sludge, a step of recirculation of at least some of said first sludge into the first contact tank (13).
The solar energy collector (2) comprises : - a receiver (4) to circulate a heat transfer fluid, - a solar energy concentrator (6) comprising rows (8) of reflectors (10) with mirrors (14) to concentrate solar energy on the receiver (4), - a washing system (26) for washing the reflectors (10), said washing system comprising an array of sprinklers (28), said sprinklers (28) having in-ground bodies (30) and rotary heads (32) rotative with respect to axes (A-A) extending substantially vertically, to spread washing solution on substantially all mirrors (14) of the reflectors (10).
The nuclear reactor comprises: - a core having nuclear fuel assemblies; - a core cooling circuit in which a coolant circulates; and - a device designed to inject nanoparticles into the coolant. The nanoparticles comprise first nanoparticles (82) of a first type having a first form factor lower than two and second nanoparticles (84) of a second type different from the first type and having a second form factor greater than two, the nanoparticles containing between 10 wt% and 90 wt% of the first nanoparticles (82) and between 90 wt% and 10 wt% of the second nanoparticles (84).
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
The invention relates to a system for conveying nuclear fuel pellets, the axis of which is oriented substantially horizontally, said system comprising: a first conveyor (C1) having a first travelling axis (X1), the axis of the cylindrical objects (P) being substantially orthogonal to the travelling axis (X1) of the first conveyor (C1); a second conveyor (C2) having a second travelling axis (X2), the first conveyor (C1) and the second conveyor (C2) being in two different planes; and a transfer means (T) connecting the first conveyor (C1) and the second conveyor (C2), said transfer means (T) having a first chute (24) provided with a ramp (30) having a curvature connecting an inlet (26) to an outlet (28) of the first chute. In addition, an outer edge of the ramp (30) is provided with a rim (31) having the curvature of the ramp (30), in order to guide the pellets from the first conveyor (C1) to the second conveyor (C2).
Sealed installation intended for handling materials that require containment, comprising an enclosure, at least one element (20) crossing a wall (24) of the enclosure and able to move in a direction substantially perpendicular to the wall (24), said wall (24) having an opening for the passage of the moving element (20), and an assembly providing sealing between the wall (24) and the moving element (20), the sealing assembly comprising a first gaiter (42) mounted in a sealed manner on the wall (24) and the moving element (20), and a second gaiter (62) radially surrounding the first gaiter (42) and mounted in a sealed manner on the wall (24) and the moving element (20) so that the first gaiter (42) is completely contained within the space defined by the second gaiter (62), the wall (24) and the moving element (20), the space delimited by the first gaiter (42) and the moving element (20) being in pneumatic communication with the inside of the enclosure.
The invention relates to a guide and support assembly for a press compensator, comprising: a bushing (32) for guiding the compensator in the bore thereof, said bushing (32) to be mounted around the compensator; a support nut (38) to be screwed into the bore, the guide bushing (32) being located between a shoulder of the compensator and the support nut (38); and a means (44) axially securing the guide bushing (32) and the support nut (38) together while providing axial, transverse play between the guide bushing (32) and the support nut (38), wherein said means (44) is provided such that the guide bushing (32) is freely rotatable relative to the support nut (38).
F15B 15/14 - Fluid-actuated devices for displacing a member from one position to anotherGearing associated therewith characterised by the construction of the motor unit of the straight-cylinder type
B30B 15/00 - Details of, or accessories for, pressesAuxiliary measures in connection with pressing
88.
METHOD FOR PRODUCING METHANOL OR HYDROCARBONS FROM A CARBON MATERIAL, INCLUDING A REFORMING STEP, THE OPERATING CONDITIONS OF WHICH ARE SELECTIVELY ADJUSTED
The production method of the invention includes the following steps: producing a synthetic gas from the carbon material according to a method including at least one reforming step, the synthetic gas having a first hydrogen/carbon-monoxide molar ratio under the first operating conditions for the reforming operation; producing a stream of hydrogen from a hydrogenated raw material and from a first consumed electrical power, the hydrogen stream having a first molar flow rate for said first consumed electrical power; and lowering the consumed electrical power for producing the hydrogen stream to a second electrical power lower than the first electrical power, and transitioning to second operating conditions that are different from the first operating conditions for the reforming operation in order to compensate for the lowering of the molar flow rate of the hydrogen stream, the synthetic gas having, under the second operating conditions, a second hydrogen/carbon-monoxide molar ratio that is greater than the first hydrogen/carbon-monoxide molar ratio.
C01B 3/32 - Production of hydrogen or of gaseous mixtures containing hydrogen by reaction of gaseous or liquid organic compounds with gasifying agents, e.g. water, carbon dioxide, air
C07C 29/151 - Preparation of compounds having hydroxy or O-metal groups bound to a carbon atom not belonging to a six-membered aromatic ring by reduction of oxides of carbon exclusively with hydrogen or hydrogen-containing gases
C10J 3/00 - Production of gases containing carbon monoxide and hydrogen, e.g. synthesis gas or town gas, from solid carbonaceous materials by partial oxidation processes involving oxygen or steam
89.
DEVICE FOR IDENTIFYING A METALLIC SUPPORT BY SHAPE RECOGNITION, APPLICATION TO THE IDENTIFICATION OF PODS CONTAINING NUCLEAR FUEL PELLETS
The invention relates to a device for identifying a metallic support on which are inscribed a code based on holes and an alphanumeric code. According to the invention, the device comprises:- means of illumination of the metallic support which consist of light-emitting diodes; - a camera for taking images of the code based on holes and of the alphanumeric code inscribed on the metallic support when the latter is illuminated by the light-emitting diodes; - means of processing an image obtained by the camera comprising means of shape recognition for reading the holes of the code based on holes and for reading the characters of the alphanumeric code which are inscribed on the metallic support.
G06K 7/10 - Methods or arrangements for sensing record carriers by electromagnetic radiation, e.g. optical sensingMethods or arrangements for sensing record carriers by corpuscular radiation
90.
INSTALLATION FOR DOSING AT LEAST ONE POWDERY MATERIAL
Installation for dosing a powdery material comprising at least one hopper (TC), a conveyor (2) having a receptacle (6) provided with a filling opening underneath said hopper (TC), a weighing system (4) able to weigh at least said receptacle (6), means (20) able to move the weighing system (4) and the receptacle (6) so as to distance the receptacle (6) from the conveyor (2) and so that, in at least one distanced position, the weighing system (4) weighs solely the receptacle (6) and its content, said weighing system (4) comprising a first balance (8) supporting the receptacle (6) and a second balance (10) on which the first balance (8) rests. Said installation can comprise individual hoppers (T1, T2, T3) upstream of the hopper (TC), making it possible to produce mixtures of powders.
The invention relates to a device for manufacturing tablets, comprising a powder dispenser (6) and a table (2) provided with dies (4) to be filled with powder and over which the dispenser moves (6). The dispenser (6) comprises two sets of rollers engaging with rails (22) attached to the table (2) on either side of the area of movement of the dispenser (6), one set of rollers (26) being used for guiding the movement of the dispenser (6), and one set of rollers being used for clamping the dispenser (6) against the table (2).
The nuclear power station component comprises: a metallic structure (3) having an outer surface (17); at least one marking (11) placed on the outer surface (17) and coding information relating to the component (1). The marking (11) comprises a plurality of luminescent nanoparticles (13, 15) each provided to emit an optical radiation having a determined emission wavelength when said luminescent nanoparticle (13, 15) is excited with optical radiation having a determined excitation wavelength.
COMMISSARIAT À L'ÉNERGIE ATOMIQUE ET AUX ÉNERGIES ALTERNATIVES (France)
AREVA NC (France)
Inventor
Heres, Xavier
Burdet, Fabien
Borrini, Julien
Duchesne, Marie-Thérèse
Mazzanti, Marinella
Bernier, Gilles
Pellet-Rostaing, Stéphane
Favre-Reguillon, Alain
Lemaire, Marc
Abstract
The present invention relates to a process that makes it possible to separate the americium present in an acidic aqueous phase or in an organic phase from other metallic elements that are also found in this phase, by complexing the americium with a water-soluble ethylenediamine derivative. It also relates to a process for the selective recovery of americium from an acidic aqueous phase containing, besides the americium, other metallic elements, which comprises the implementation of this separation process. Applications: treatment of spent nuclear fuels.
Installation for welding fuel assembly top nozzles onto nuclear fuel rods comprising a device (D) for axially retaining said rod and for setting it in rotation and a welding chamber (C), said device (D) comprising a gripper and means for closing the gripper onto the fuel rod, said means comprising a push-rod (32) to apply an axial force to the gripper, a linear actuator (44) of axis (X2) parallel to the longitudinal axis of the device (X), a yoke (46) translationally secured to said push-rod and able to rotate about a fixed axis (Y) orthogonal to the longitudinal axis (X) which is not secant therewith, said yoke (46) being articulated with respect to the linear actuator (44) about an axis (Y1) parallel to the orthogonal axis (Y) such that the linear actuator (44) causes the yoke (46) to rotate about the first orthogonal axis (Y) and causes a translational movement of the push-rod, closing the gripper onto the fuel rod.
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
B23K 9/028 - Seam weldingBacking meansInserts for curved planar seams
B23K 37/053 - Auxiliary devices or processes, not specially adapted for a procedure covered by only one of the other main groups of this subclass for holding or positioning work aligning cylindrical workClamping devices therefor
B23Q 1/26 - Movable or adjustable work or tool supports characterised by constructional features relating to the co-operation of relatively movable membersMeans for preventing relative movement of such members
95.
METHOD OF MEASURING THE URANIUM CONCENTRATION OF AN AQUEOUS SOLUTION BY SPECTROPHOTOMETRY
The invention relates to a method of measuring the uranium concentration of an aqueous solution, comprising the following successive steps: a) the electrochemical reduction to valence IV of the uranium present in the aqueous solution at a valence above IV, this reduction being carried out at pH < 2 and by passing an electric current through the solution; b) the measurement of the absorbance of the solution obtained on conclusion of step a) at a wavelength chosen between 640 and 660 nm, preferably at 652 nm; and c) the determination of the uranium concentration of the aqueous solution by deduction from the uranium concentration of valence (IV) present in the aqueous solution obtained on completion of step a) from the measurement of the absorbance obtained in step b).
G01N 21/31 - Investigating relative effect of material at wavelengths characteristic of specific elements or molecules, e.g. atomic absorption spectrometry
A radiopharmaceutical composition that comprises a radioactive isotope of lead (212Pb) combination with a pharmaceutical or an antibody or antibody fragment and a chelating agent. These compositions are especially useful in the imaging and diagnosis of tumors and tumor metastases.
The invention relates to equipment for transferring powder from a drum into a tank, comprising at least one handling device and a hopper assembly (T) connected to a tank (4). The handling device comprises a hollow cylindrical body for surrounding a drum (2) and immobilizing same in order enable the latter to be turned over, the drum (2) being open and the powder being contained in at least one sealed bag. The hopper assembly (T) comprises a hopper (60) and a sealed chamber (62) mounted onto the upstream end of the hopper, said chamber (62) comprising an opening for enabling the entry of the hollow cylindrical body loaded with the drum (2) and the bag powder, wherein, after the withdrawal of the hollow cylindrical body loaded with the empty drum (2), said opening is closed and the bag is opened so as to allow the powder to flow into the hopper (60).
B66C 1/62 - Load-engaging elements or devices attached to lifting, lowering, or hauling gear of cranes, or adapted for connection therewith for transmitting forces to articles or groups of articles by mechanical means comprising article-engaging members of a shape complementary to that of the articles to be handled
B65G 65/23 - Devices for tilting and emptying of containers
98.
Integrated reactor missile shield and crane assembly
An integrated reactor missile shield and crane assembly (IRMSCA) is disclosed and claimed. The IRMSCA replaces the existing concrete missile shields and reactor services crane. The IRMSCA is moveable such that the missile shield can be moved away from the reactor head, allowing the integral crane to lift the control rod drive mechanism components and other routine loads at the refueling cavity.
G21C 11/00 - Shielding structurally associated with the reactor
G21C 7/20 - Disposition of shock-absorbing devices
G21C 9/00 - Emergency protection arrangements structurally associated with the reactor
G21C 19/20 - Arrangements for introducing objects into the pressure vesselArrangements for handling objects within the pressure vesselArrangements for removing objects from the pressure vessel
The invention relates to a device (1) for inserting, guiding, and removing cylindrical parts to be ground in a centerless grinder (10). According to the invention, means (4, 40, 41) for the micrometric adjustment of the alignment of inlet (3) and outlet (5) guides of a guide rail (2) are provided, wherein said micrometric adjustment means are provided separately from one another. Using the invention, very precise alignment can be achieved, and any deviation of the parts is thereby avoided.
B24B 5/22 - Machines or devices designed for grinding surfaces of revolution on work, including those which also grind adjacent plane surfacesAccessories therefor involving centreless means for supporting, guiding, floating or rotating work for grinding cylindrical surfaces, e.g. on bolts
B24B 5/313 - Machines or devices designed for grinding surfaces of revolution on work, including those which also grind adjacent plane surfacesAccessories therefor involving work-supporting means carrying several workpieces to be operated on in succession
B24B 41/00 - Component parts of grinding machines or devices, such as frames, beds, carriages or headstocks
G21C 19/00 - Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
100.
DEVICE FOR DRESSING A GRINDING WHEEL, AND USE THEREOF IN A CENTERLESS GRINDER FOR NUCLEAR FUEL PELLETS
The invention relates to a dressing device (1) for a grinding wheel (2), including a sleeve (10) for laterally holding and guiding, along the horizontal axis (X) thereof, a corundum rod (3), a ram (11) for applying a constant pressing force to the corundum rod (3) held and guided in the sleeve (10) against the grinding wheel (2), means (4, 40, 41) for rigidly connecting the ramrod (110) to the end of the corundum rod, and linear guide means (13) for the sleeve for translating the corundum rod parallel to the axis (y) of the grinding wheel while keeping said rod pressed against the latter with a constant force. The invention can be used in a centerless grinder (5) in which the grinding wheel (2) has the function of grinding nuclear fuel pellets.