Abstract: The invention concerns a vessel for processing, transfer, accumulation and/or transfer of material containing civilian or military origin plutonium, in the form of plutonium oxide, carbide and/or nitride. The plutonium is preferably present in a concentration not higher than a guaranteed maximum between 20 and 50% wt. in said material, possibly with other actinides such as americium, neptunium, or curium. Said material is preferably in form of powder, granulate and/or tablets. The vessel comprises a volume of 20 to 70 liters for containing said material, demarcated at least by two substantially parallel walls, these two walls being separated by a distance e between 8 and 15 cm.

Abstract: The invention concerns a vessel for processing, transfer, accumulation and/or transfer of material containing civilian or military origin plutonium, in the form of plutonium oxide, carbide and/or nitride. The plutonium is preferably present in a concentration not higher than a guaranteed maximum between 20 and 50% wt. in said material, possibly with other actinides such as americium, neptunium, or curium. Said material is preferably in form of powder, granulate and/or tablets. The vessel comprises a volume of 20 to 70 liters for containing said material, demarcated at least by two substantially parallel walls, these two walls being separated by a distance e between 8 and 15 cm.

Abstract: The invention relates to a method and device for production of non-contaminated rods from MOX tablets in columns, within a confinement chamber divided into compartments, by means of a centering and aligning element for the tablets and a long pushrod with a sensitive drive.

Abstract: The invention relates to a method and device for production of non-contaminated rods from MOX tablets in columns, within a confinement chamber divided into compartments, by means of a centering and aligning element for the tablets and a long pushrod with a sensitive drive.

Abstract: Sealing device (10) between two media and the outer surface of a fuel cladding (1), characterized by three states: a state retracted for contactiess axial insertion of said fuel cladding (1) though the sealing device, a state statically hermetically sealed around said fuel cladding maintained at rest, and a state dynamically hermetically sealed around said fuel cladding under axial and/or rotational movement.

Abstract: Method and device for loading nuclear fuel pellets into a cladding provided with its first plug, by means of an introduction element and using limited forces.

Abstract: Process for fabrication MOX fuel from weapon originating plutonium oxide (W—PuO2), including a process for fabricating MOX fuel pellets, a dry processing of W—PuO2 powder, and a dry processing of MOX fabrication scrap.

Abstract: A method for carrying out a comprehensive quality control of MOX fuel rods, including measurement of plutonium content of pellets contained in the rod, check of internal structure and constituents in the rod, including the detection of rogue pellets, and measurement of dimensional characteristics and radioactive contamination along the rod surface, by moving the fuel rod axially, performing concurrently the measurements and checks along the fuel rod moved axially, using radiometry and radiography. An apparatus for carrying out the method.

Abstract: Process for fabrication MOX fuel from weapon originating plutonium oxide (W—PuO2), including a process for fabricating MOX fuel pellets, a dry processing of W—PuO2 powder, and a dry processing of MOX fabrication scrap.

Abstract: A method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste, including a process for making fuel pellets of mixed (U,Pu)O2 oxide, including a dosage and a first mixture (1) of waste in powder form and, if required, of PuO2 and/or UO2 powders, a micronization (2) and a forced sieving (3) of said first mixture, another dosage and a second mixture (4) of the first sieved mixture, of UO2 powders and, if necessary, of the waste powder, pelletizing (6) the second mixture, and sintering (7) the resulting pellets; and a process for pre-treating the waste including pelletizing (20) and sintering (21) the powder waste to form waste pellets, and micronizing (23) the waste pellets to form the desired waste powder designed to be incorporated as waste powder, in the first (1) and/or second mixtures.

Abstract: A process for manufacturing (U,Pu)O2 mixed oxide nuclear fuel pellets. In a first blending operation, PuO2 is mixed with a UO2 powder and/or fuel manufacturing scrap, forming a first blend. The first blend is micronized and sieved to form a conditioned first blend. Non-free-flowing UO2 is selected as a second portion of UO2. The second portion of UO2 is mechanically granulated to form granulated free-flowing UO2. In a second blending operation, the conditioned first blend is further mixed with the granulated free-flowing UO2 and possibly scrap. Lubricants and/or poreformers are added. The blend is pelletized and sintered. During granulation, the non free-flowing UO2 is compressed to form tablets. The tablets are then crushed until a free-flowing crushed material has been formed. At least one portion of this free flowing crushed material is used in the second blending operation.

Abstract: A welded MOX fuel rod having a cladding and an end plug joined by a circumferential weld, the weld bead being designed to affect equivalent masses in both the cladding and end plug.