Abstract: A mechanical securing assembly (40) is adapted to secure the structural integrity of a flow passage formed by at least a first pipe part (41) and a second pipe part (42). The assembly comprises a connecting member (43), a first fastening member (44), attached to the connecting member and adapted to secure the connecting member to the first pipe part, and a second fastening member (45), attached to the connecting member and adapted to secure the connecting member to the second pipe part. The connecting member comprises a spring element (46) exerting a force pulling the first fastening member and the second fastening member towards each other along a primary axis (y), and thus being adapted to force the first pipe part and the second pipe part towards each other. The spring element is extendable along the primary axis by a compression of the spring element along a secondary axis forming an angle to the primary axis.

Abstract: A clamp assembly for securing a thermal sleeve and an elbow in a pipe assembly in a nuclear reactor. The clamp assembly comprises a sleeve clamp adapted to be arranged surrounding the elbow at a first joint between the elbow and a thermal sleeve, and comprising a sleeve support adapted to extend across the first joint. The clamp assembly comprises at least one clamp arm with a first end arranged to rest against at least one of a core shroud and a core plate support ring, to provide support for the positioning of the sleeve clamp.

Abstract: A mechanical securing assembly (40) is adapted to secure the structural integrity of a flow passage formed by at least a first pipe part (41) and a second pipe part (42). The assembly comprises a connecting member (43), a first fastening member (44), attached to the connecting member and adapted to secure the connecting member to the first pipe part, and a second fastening member (45), attached to the connecting member and adapted to secure the connecting member to the second pipe part. The connecting member comprises a spring element (46) exerting a force pulling the first fastening member and the second fastening member towards each other along a primary axis (y), and thus being adapted to force the first pipe part and the second pipe part towards each other. The spring element is extendable along the primary axis by a compression of the spring element along a secondary axis forming an angle to the primary axis.

Abstract: A clamp assembly for securing a thermal sleeve and an elbow in a pipe assembly in a nuclear reactor. The clamp assembly comprises a sleeve clamp adapted to be arranged surrounding the elbow at a first joint between the elbow and a thermal sleeve, and comprising a sleeve support adapted to extend across the first joint. The clamp assembly comprises at least one clamp arm with a first end arranged to rest against at least one of a core shroud and a core plate support ring, to provide support for the positioning of the sleeve clamp.

Abstract: The present invention provides a method and apparatus for fuel handling in a nuclear reactor. The nuclear reactor has a reactor vessel comprising a reactor core with a plurality of fuel assemblies and control rods. A fuel pool is arranged adjacent to the reactor vessel. A group comprising at least a plurality of fuel assemblies is simultaneously lifted out of or into the reactor vessel with a single gripper, the gripper having a plurality of gripping devices. The group is transported between the reactor vessel and the fuel pool by means of the gripper.

Abstract: The present invention relates to a method and a device for correction of the movements of a suspension device and positioning thereof in a fluid. The suspension device is provided with a first and a second end, and the first end is suspended from a point (S). A correction device is arranged at the second end of the suspension device and adapted to generate a force which provides an acceleration in the fluid so that the position of the second end of the suspension device is corrected.

Abstract: The present invention is used in fuel handling for lifting of fuel assemblies and/or control rods out of/into a reactor vessel in a nuclear reactor. The reactor vessel comprises a reactor core with a plurality of fuel assemblies and control rods. A fuel pool is arranged adjacent the reactor vessel. A cassette comprising a plurality of storage positions for fuel assemblies and/or control rods is arranged near the reactor core, whereupon fuel assemblies and/or control rods are lifted out of the reactor core and arranged in the cassette. The cassette is then transported to the fuel pool for temporary storage.