Abstract: A method for treating a nitric aqueous liquid effluent containing nitrates of metals or metalloids, comprising a step for calcination of the effluent in order to convert the nitrates of metals or metalloids into oxides of said metals or metalloids, at least one compound selected from the nitrates of metals or metalloids and the other compounds of the effluent leading upon calcination to a tacky oxide, and a dilution adjuvant comprising at least one nitrate of metal or metalloid leading upon calcination to a non-tacky oxide being added to the effluent prior to the calcination step in order to give a mixture of effluent and of dilution adjuvant.

Abstract: A method for treating a nitric aqueous liquid effluent containing nitrates of metals or metalloids, comprising a step for calcination of the effluent in order to convert the nitrates of metals or metalloids into oxides of said metals or metalloids, at least one compound selected from the nitrates of metals or metalloids and the other compounds of the effluent leading upon calcination to a tacky oxide, and a dilution adjuvant leading upon calcination to a non-tacky oxide being added to the effluent prior to the calcination step, a method wherein the dilution adjuvant comprises aluminium nitrate and at least one nitrate selected from iron nitrate and rare earth nitrates.

Abstract: This can opening machine comprises a lower guide ring to center the top of the single-piece can, comprising a centering chamfered face and an upper stop face. A piston arranged in the tool for cutting out the can lid is pushed downwards by a spring extending low enough to separate the cut out lid from the tool. The lid remains in the can during turning and content emptying operations.

Abstract: Angular sectors of a cylindrical wall of a crucible for vitrification of waste, built in steel and subject to high temperatures, are coated with a mixture of mainly glass and ceramic, the coating being subject to a heat treatment comprising a step between 650° C. and 850° C. so as to perform surface melting of the mixture filling the open porosity, improving dielectric strength and the cohesion of the coating, but without producing any excessive thermal expansion or oxidation of the substrate which would lead to fast flaking of the coating.

Abstract: Method for producing a uranium concentrate in the form of solid particles, by precipitation from a uranium-containing solution using a precipitating agent, in a vertical reactor comprising a base, a top, a central part, an upper part, and a lower part, the solid particles of the uranium concentrate forming a fluidized bed under the action of a rising liquid current which circulates from the base towards the top of the reactor successively passing through the lower part, the central part and the upper part of the reactor, and which is created by introducing a liquid recycling current (flow) at the base of the reactor, said liquid recycling current being tapped at a first determined level (A) in the upper part of the reactor and sent back without settling to the base of the reactor, excess liquid being also evacuated via an overflow located at a second determined level (B) in the upper part of the reactor; a method in which the upper limit (C) of the fluidized bed of solid particles is controlled so that it is

Abstract: A machine comprising two rollers for ovalising a nuclear fuel cladding to crush the content thereof allowing its easy release even if the pellets are arranged in the cladding with little clearance. The opposite inclinations of the rollers promote automatic forward travel of the claddings. The opening and the inclination of the claddings lead to release of the crushed fuel. The rollers are biconical, with an input portion of increasing diameter and an output portion of decreasing diameter, to apply sufficient ovalisations to crush the fuel whilst restoring rotundity to the cladding when it leaves the machine, to facilitate the outflow of debris.

Abstract: A fuel element handling system having a gripping device, the structure of which can be pushed in the horizontal position and uncoupled from the handling system if a failure occurs, uncoupling releasing the load formed by the fuel elements and their gripped support and putting them in a safe situation.

Abstract: A device for measuring and correcting a parallelism error of an upper plug end of a nuclear fuel rod comprising mechanisms for measuring a parallelism error and for correcting said error, and a mechanism for positioning said device on the fuel rod and cooperating with a rack on which the fuel rod is stored, said correction means being arranged opposite the measuring mechanism relative to the location of the fuel rod, in order to allow a measurement of the parallelism error during correction of said error.

Abstract: A method for the surface tribological decontamination of nuclear fuel rods automates surface wiping by one or more bands of fabric. The band is distant from the axis of the rod, the rod is placed facing the band, and then the band is tensioned around the surface of the rod and moved. The rod may be immobile, moved in pure translation along its axis or with a wide-step helical movement. Preferably, the decontamination is carried by two bands simultaneously, so as to cover the total surface in one pass of the rod.

Abstract: The subject of the present invention is: a casing internal part (1) suitable for the dry intermediate storage of at least one irradiated fuel element. Said casing internal part (1) has a tiered structure which comprises at least two superposed modules (M1, M2, M3, M4), each of said modules (M1, M2, M3, M4), made of a material that is a good conductor of heat, with compartment(s) (2a, 2b) for accommodating said fuel element(s) in the central part and with at least one hollowed-out peripheral heat sink (3a, 3b), being arranged on a support plate (4) that is perforated to allow said fuel element(s) through; the perforated support plates (4) of said structure being positioned and assembled by means of a retaining system (5?+5+5?), with a clearance (J) left between the top of the module of one tier (Mi) and the perforated support plate (4) of the tier (Mi+1) immediately above; a temporary storage casing (10) equipped with such a casing internal part (1); and the corresponding temporary storage method.

Abstract: The container is comprised of a side wall of which the end edges are each provided with a blocking member, of which at least one is inserted in order to close an opening. The peripheral outline of the inserted blocking member and the interior outline of the associated end edge of the side wall have generally complementary shapes on at least one portion of their respective heights, in such a way that said inserted blocking member comes to be housed on at least one portion of its height in the space defined by said end edge of the side wall and comes to bear against said end edge by adjusting lugs in recesses of complementary shape. The inclined joining surfaces form an angle from 20° to 40° with the axis of the container.

Abstract: A conveyor device has a sequence of two vibrating screens vertically separated (d) from each other and supplying an alignment bowl, to eliminate chips and residue from nuclear fuel pellets stored in bulk in a boat and to align them in order to fill fuel rods. Due to these two screens, pellets are set aside and turned over, and chips are efficiently separated in a pot, without any congestion of the system.

Abstract: The electricity transmission device comprises prolonged rigid conductors made of copper (18), and also a connector (17) comprising a network of flexible elements (23), such as brazed tubes with cooling channels (20, 22) for the conductors (18), that enables angular displacements between the successive segments (15, 16) and therefore gives a flexibility absorbing small displacements of the device. A lifting manoeuvre system (26, 27) is associated with the segments (15, 16). The segments (15, 16) may be joined to other elements of the device through connections with jaws enabling slipping.

Abstract: A container for the storage of radioactive waste comprising a reversible lid having, on one hand, a first opening sealing portion provided with a first delimiting surface of an inner space wherefrom second gripping means project, said first portion being designed so as to be able to be force-fitted in an end part of a container body, and, on the other, a second sealing portion, provided with a second delimiting surface wherefrom first gripping means project, said second portion being designed so as to be able to be fitted in the end part.

Abstract: The object of the present invention is mainly a powder dispenser including a casing capable of impulsing the powder in a reciprocal movement on a plane along a determined displacement direction (X), and means (19,23) for grouping the powder along distinct axes, substantially parallel to the X direction. The object of the present invention is also a method for making pellets, notably nuclear fuel pellets, applying a dispenser according to the present invention.

Abstract: Device to load a sintering boat with nuclear fuel pellets, comprising a loading chute (2) delimiting a travel pathway (4) for the pellets, the loading chute comprising an upper end (8) intended to receive pellets and a lower end (12) intended to lie close to a sintering boat, said loading chute (2) comprising gates (18, 20, 22) forming an obstacle in the pathway of the pellets so as to fractionate said pathway, said gates (18, 20, 22) able to be actuated alternately, and the lower end (12) of the loading chute being movable so that it can be drawn close to and away from a bottom part of the sintering boat. A further subject-matter of the present invention is a method to load a sintering boat with nuclear fuel pellets, using a device according to the present invention.

Abstract: Device for large diameter bag port comprises a diameter reduction spacer with a first circular orifice of the diameter equal to the diameter of the port bag. This first orifice is facing towards the bag port. This device comprises also a second orifice facing towards the outside of the containment in the direction opposite to the first orifice, this second orifice being elongated in shape, particularly ovoid.

Abstract: A system based on the continuous measurement (20) of the diameter of a cylindrical object (1) moving, laid down, on a belt conveyor (10) allows dimensional compliance of the latter object to be checked. The measurement system (20) may be coupled with a sorting system based on ejection out of the conveyor (10) by projecting a gas through a transverse nozzle (42). By means of the system according to the invention, it is possible to continuously determine whether a nuclear fuel pellet (1), in particular after rectification (2), has to be rejected or not.

Abstract: A closed container with a tight and mechanically strong seal having two fastened-together metal elements including a body and a cover. The body is essentially a cylindrical or prismatic shape having a base with one or more axial walls and an open top axial end. The cover has a more or less complex shape having one or more walls to be positioned at the top axial end of the body facing the axial wall(s) of the body. The fastening of the metal elements is via a butt weld, advantageously with no filler metal. The internal structure at the weld line includes a docking guide having a groove provided with at least one degassing chimney, and a chamfered end above or below the weld line, on the wall. The body and/or the cover include(s) at least one blanked off degassing vent.

Abstract: The invention relates to a process for producing 228Th from a natural thorium salt, which comprises in succession: a) the separation of the radium from the other radioelements present in this salt, by at least one coprecipitation of the radium by barium sulphate, this coprecipitation comprising: i) the addition of sulphuric acid and a barium salt to an aqueous solution of said natural thorium salt in order to form a barium-radium sulphate coprecipitate and ii) the separation of the coprecipitate from the medium in which it has formed; b) the extraction of the thorium 228 coming from the decay of radium 228 from the coprecipitate thus separated; and, optionally c) the purification and concentration of the 228Th thus extracted. Applications: manufacture of radiopharmaceutical products useful in nuclear medicine, in particular in radioimmunotherapy for the treatment of cancers and AIDS.