Abstract: For each of the demountable fuel rods (23), the end part of the protective tube (27), which end part is open towards the exterior, has a reduced diameter over a certain length and comprises at least one seating which does or does not pass through its wall. The end part of the fuel rod (23) is integral with a ferrule (34) which is coaxial with the fuel rod and which surrounds the assembly rod (31) of the fuel rod over part of its length. The ferrule (34) is engaged on the reduced-diameter part of the protective tube (27) when the rod (31) is screwed into the bore (28) of the protective tube. Locking against rotation of the fuel rod in the protective tube (27) is ensured by deformation of the ferrule (34) within the openings of the end part of the protective tube (27). The fuel rod is demounted by exerting a torque on it by way of an engagement surface (37), for example of prismatic form, located near the end of the fuel rod.

Abstract: Device for guiding nuclear reactor control clusters consisting of several absorbing rods including guide casings, associated respectively with the various control clusters, and, inside each casing, horizontal plates (14) ensuring, in the upper part, discontinuous guidance at intermediate levels for the various elements of the control cluster. In the lower part of the casing, guidance of the rods arranged in pairs sharing one radius is achieved by combining horizontal plates (14) ensuring mechanical guidance of the rods with casings (22) which reduce the hydraulic effects to a minimum by calming the cooling fluid in the radial direction around the said absorbing rods. The invention applies to pressurized water nuclear reactors.

Abstract: The spacer-grid comprises at least one single-piece plate (1) through which extend a group of openings (2) at least a part of which constitutes an even network of passages (2) for the fuel rods and the guide tubes of the fuel assembly. The spacer-grid may be formed by one single-piece plate (1) of great thickness or by the association of a plurality of parallel single-piece plates interconnected by an outer girdle element.

Abstract: A grid for use in a PWR assembly includes a peripheral girdle and at least two sets of parallel plates. The plates of one set are at an angle with respect to those of the other set so that the sets defined cells for the fuel rods. The parallel plates are distributed in at least two beds spaced apart in the longitudinal direction of the assembly. In a fuel assembly having a triangular array of fuel rods, three successive beds of mutually parallel plates are provided.

Abstract: A spacing grid for a nuclear fuel assembly, particularly a water cooled assembly, includes two spaced sets of plates. Each set is formed of plates parallel to each other and fixed at their ends to a polygonal belt in the form of a strip having fins along one longitudinal edge at least. Each corner of the belt is free of openings. Two at least of the corners are rounded and located inside of imaginary extensions of the flat lateral faces of the belt. They are connected to the edges of the lateral faces by gussets sloping radially inwardly.

Abstract: A device for moving a cluster of nuclear reactor control elements, more especially usable for changing the moderation rate of a nuclear reactor, comprising a vertical shaft having nippers cooperating with grabs integral with sub-clusters. Each grab comprises resilient fingers engageable with the nippers and lockable by snap fitting on the fixed upper structure. Each nipper is formed so as to engage resilient fingers and unlock them from the upper structure when the nipper is raised above the position which causes locking of the grab on the structure. A fixed lower structure is provided for causing forced disengagement of the nipper when this latter is lowered beyond the rest position of the grab on this structure. Raising of the nipper then drives the grab by simple bearing force.