Abstract: Device for checking the tightness of covers on a heavy metal container for transport and/or storage of radioactive materials, the said container comprising a cavity for nuclear materials delimited by a thick cylindrical shell closed at one end by means of a bottom fixed so that it is leaktight, and at the other end by at least two thick removable superposed covers, characterized in that the said covers are in contact with a shoulder formed in the shell, through flanges fitted with at least two concentric seals, that at least two ducts pass through the shell at each cover, leading through a first inspection orifice to the outside surface of the shell close to the cover in an accessible location, and through a second orifice, one into the space between the cover concentric seals, and the other into the space between the said cover, the shell and the immediately superposed cover, each inspection orifice optionally being connected to a tightness measurement and inspection circuit.

Abstract: A container for nuclear fuel assemblies comprises a thick cylindrical body of forged steel which delimits an inner cavity for housing said assemblies, said cavity being able to be hermetically sealed at its two ends by plugs which are also formed of metal, characterized in that the cross section of the cylindrical body is non-circular. The outer wall usually comprising flat surfaces which are parallel to the flat face of crescent-shaped sections fixed to its inner wall, providing the cross section with the shape of a square or rectangle with rounded corners.

Abstract: A rack for storing or transporting nuclear fuel assemblies includes a plurality of adjacent prismatic cells having cell walls defining interior fuel assembly storage spaces. The cell walls are formed from a criss-crossed, ordered stack of elongated structural elements of constant cross section, disposed in successive layers and having a long dimension perpendicular to the axis of the cells. Neutrophage sections in tubular form and having a cross section corresponding to that of the cells are disposed against the cell walls within the nuclear fuel assembly storage spaces.

Abstract: A container for nuclear fuel assemblies comprises a thick cylindrical body of forged steel which delimits an inner cavity for housing said assemblies, said cavity being able to be hermetically sealed at its two ends by plugs which are also formed of metal, characterized in that the cross section of the cylindrical body is non-circular. The outer wall usually comprising flat surfaces which are parallel to the flat face of crescent-shaped sections fixed to its inner wall, providing the cross section with the shape of a square or rectangle with rounded corners, for example.

Abstract: A container for transport and storage of highly radioactive material, the container being made of thick metal and comprising a tube having an internal wall and a base having a lateral wall, the base being non-removably sealed to one end of the tube, and the internal wall and lateral wall forming a right cylinder with circular cross-section in contact with each other. The base is fixed to the container by shrink fitting the lateral wall with a portion of the internal wall in contact with the lateral wall, the base being disposed such that the lateral wall is entirely inside the tube with a portion of the internal wall comprising an opposed shoulder which cooperates with the corresponding shoulder in the lateral wall. A first continuous seam weld is provided on an external surface of the base in contact with the tube and a second continuous weld seem is provided on an internal surface of the base in contact with the tube.

Abstract: A stowage rack is disclosed for dry transport of nuclear fuel elements in a plurality of elongated, parallel, adjacent prismatic cells. The rack is formed from first and second sets of materials, the first set of materials fulfilling the function of mechanical strength and thermal conductivity, and the second set of materials fulfilling the function of neutron absorption. The stack may be formed entirely of materials fulfilling the function of mechanical strength and thermal conductivity, with the neutron absorption materials being provided within the walls of the cells. Alternatively, materials providing mechanical strength and thermal conductivity may be stacked alternately with materials providing neutron absorption.

Abstract: A handling apparatus which is intended primarily for operations involving pulling and pushing nuclear fuel rods which are carried out when dismantling assemblies, comprising a handling head in which there are provided a plurality of cylinders (6) in which grippers are slidable, formed by two coaxial parts (4, 10) by means of pistons (4a, 4b) which are fixed with respect thereto. Said pistons define three annular spaces (A, B, C) which are supplied by three individually controllable hydraulic fluid circutis (La, Lb, Lc). Such fluids provide for opening and sliding movement of the grippers with respect to the head as well as control of the maximum admissible force in respect of traction or compression on the grippers.At the upper end of each gripper two travel limit switches give the individual situation of each thereof.