Abstract: The invention relates to a device for dressing a grinding wheel, comprising a sleeve to hold a corundum rod laterally and to guide it along its longitudinal axis, a ram to apply constant thrust force onto the corundum rod held in place and guided in the sleeve, to bring it into contact with the grinding wheel, means of rigidly connecting the ram shaft to the end of the corundum rod, and linear guide means for the sleeve for translating the corundum rod parallel to the axis of the grinding wheel while keeping the rod pressed against the grinding wheel with a constant force. Application to a centreless grinder in which the grinding wheel is used to grind nuclear fuel pellets.

Abstract: A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO3. The uranium, plutonium and neptunium found in the solvent phase is then split in a first aqueous phase and a second aqueous phase. Next, the first aqueous phase is stored. Following, the plutonium or other mixtures found in the first aqueous phase is purified relative to the fission products still found in said phase, in order to obtain, at the end of said purification, an aqueous solution containing a mixture of Pu and U or Pu, U and Np. Finally the resulting mixture of Pu and U or the mixture of Pu, U and Np is co-converted into a mixed oxide.

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: A method inhibits the formation of zirconium molybdate precipitate in an aqueous solution containing the element molybdenum and the element zirconium by adding a chemical element selected from plutonium, tellurium, antimony and mixtures thereof with the aqueous solution. The method can be used for reprocessing used fuels with the element molybdenum and the element zirconium.

Abstract: A method for the fluid-tight assembly of two parts silicon nitride respectively comprising a male end and a female end, each of these ends being provided with mechanical assembly means capable of cooperating together and which, under assembling conditions, delimit a space -between them, said method comprises the assembling of the said parts by cooperation of the mechanical assembly means of the male and female ends, and filling of the space existing between these assembly means with a glass joint, and is characterized in that this filling comprises: coating, before assembling of the parts, the mechanical means of one and/or the other of the male and female ends with a borosilicate glass paste; and applying heat treatment to the parts after the assembling thereof.

Abstract: The invention relates to a tool used for pressure crimping and driving-out of a cleat, comprising: (a) a first receptacle opposite which is located a crimping head movably mounted on a body of the tool; (b) a second receptacle opposite which is located a drive-out head also movably mounted on the body; and (c) pressure means movably mounted on the body so as to be able to be displaced from a crimping position in which they are capable of exerting pressure on the crimping head, to a drive-out position in which they are capable of exerting pressure on the drive-out head, and conversely.

Abstract: A method for regenerating a solid filter containing iodine in the form of silver iodide and/or iodate and possibly molecular iodine physisorbed, in a solid filter containing silver in the form of nitrate. The iodine is extracted from the filter by putting the filter into contact with a basic aqueous solution containing a reducing agent. The extraction is achieved at room temperature, and then the filter is separated from this basic aqueous solution. Next, silver is extracted from the filter by putting the filter into contact with an acid aqueous solution. The filter is then separated from the acid aqueous solution. Finally, the filter is impregnated with silver by putting the filter into contact with a silver nitrate solution and then drying the filter. This method can be used in nuclear installations, notably factories for reprocessing used nuclear fuels.

Abstract: The flexible glove holder (1) includes a flat structure (13) with three branches (2, 3 and 4) forming an S-shape on which the glove is wound. The holder (1) is then pushed into the opening of the glove box. This rapid action method makes it possible to avoid knotting the gloves when they must be drawn toward the outside for an operation within the box and also allows the implementation of biological protection on the opening of the glove box as well as a protection of the agents against radiation.

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.

Abstract: A method using diglycolamide for increasing the separation factor between americium and curium and/or between lanthanides during an extraction operation. The operation comprising putting an acid aqueous phase, in which are found the americium, curium and/or lanthanides, in contact with an organic phase non-miscible with water, containing at least one extractant in an organic diluent. The aqueous and organic phases are then separated, and the diglycolamide is added to the aqueous phase.

Abstract: The object of this invention is to provide a device and method for the dry intermediate storage of irradiated fuel elements. The apparatus includes a casing which includes tiered superposed modules made of thermally conductive material and having compartments for accommodating fuel elements with a heat sink arranged on a perforated support plate. The system includes a retaining system which includes a clearance space left between a top module of a tier and a support plate of a tier above the superposed module.

Abstract: A method for treating spent nuclear fuel, which includes first decontaminating the uranium, plutonium and neptunium found in a nitric aqueous phase resulting from dissolving the nuclear fuel in HNO3. The uranium, plutonium and neptunium found in the solvent phase is then split in a first aqueous phase and a second aqueous phase. Next, the first aqueous phase is stored. Following, the plutonium or other mixtures found in the first aqueous phase is purified relative to the fission products still found in said phase, in order to obtain, at the end of said purification, an aqueous solution containing a mixture of Pu and U or Pu, U and Np. Finally the resulting mixture of Pu and U or the mixture of Pu, U and Np is co-converted into a mixed oxide.

Abstract: A temperature measurement tube is composite and comprises a rigid shaft (1), which is cooled so as to shield it from corrosion and from the melt, and an end-fitting (15) housing a thermocouple (9) on the end of the tube and constructed from a noble metal, which is resistant to corrosion and to the high melting point. An alumina coating (13) is placed between the two metals in order to prevent any corrosion-inducing electrochemical exchange between them.

Abstract: A chemical element to be very efficiently separated from uranium starting from an acid aqueous phase, in an extraction cycle for the uranium, when this chemical element is present in said phase at a concentration less than that of the uranium, or even as a trace element, and when it is moreover less extractable by the extractant used in this extraction cycle than is the uranium. The chemical element can notably be neptunium(IV) or thorium 228.

Abstract: Process for decontaminating, cleaning a solid organic substrate contaminated by solid radioactive particulate inorganic contaminants, in which: the said solid substrate is brought into contact with an extraction medium, devoid of water, comprising: dense pressurized CO2; at least one nonhalogenated surface-active compound chosen from block copolymers of poly(ethylene oxide) PEO and poly(propylene oxide) PPO, such as (EO)x-(PO)y diblock copolymers, (EO)x-(PO)y-(EO)x triblock copolymers and (PO)x-(EO)y-(PO)x, triblock copolymers, where x and y are integers from 2 to 80 with x other than y; and polydi(1 to 6C)alkylsiloxanes, such as polydimethylsiloxane (PDMS); and at least one complexing agent chosen from tributyl phosphate (TBP), crown ethers, tributylphosphine oxide, triphenylphosphine oxide and tri(n-octyl)phosphine oxide; the solid substrate and/or the extraction medium is/are subjected, simultaneously with the contacting operation, to a mechanical action.

Abstract: A system for filling a jar with powdery material, for example for the manufacture of nuclear fuel, including a device for connection between the jar and a material feed system, where the device includes: a stationary connection portion connected to the feed system, a connection portion which moves relative to the stationary connection portion intended to be connected to the container's filling orifice, where the moving connection portion includes in the area of a downstream end a lip seal to achieve a tight connection by contact with the contours of the jar's filling orifice and where the said downstream end is connected to the stationary connection portion by a bellows so as to provide mechanical disengagement between the downstream end of the moving connection portion and the stationary connection portion.

Abstract: A glove box with a sealed containment area delimited at least partially by a wall having a an inner partition facing the sealed containment area, an outer partition spaced from the inner partition and located outside of the containment area, and a lighting means with a light source housed between the inner partition and the outer partition.

Abstract: Production device including a press, a conveyor (4) intended to transport pellets from the press to a sintering area, means (26) for transferring pellets from the press to the conveyor (4), and means for inspecting at least one nuclear fuel pellet at the exit of a press, said inspection means including means (20) for identifying each pellet according to its die of origin.

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

Abstract: Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism.