[en] Calculations have been performed for the thermal and mechanical design of the fuel elements of FDR-2. This had to be done in accordance with the German licensing authorities opinion about the maximum center temperature in the fuel, maximum plastic deformation in the cladding and sufficient margin with respect to fatigue fracture. This means that a detailed life history of the most critical fuel rods had to be considered. The main design criterium for the fuel rods is the full power cycling feasibility of the ship reactor core which avoids restrictions on the manoeuvrability of the ship. Furthermore the thermomechanical behavior of some fuel rods during the restart of the reactor after partial reloading of the core was studied. The fuel modeling code SATURN-LG has been used, which calculates quasistationary the thermomechanical state of light water reactor fuel rods as a function of the operating conditions. For two fuel rods the values of the most important physical quantities dependent on the reactor operating history will be presented and discussed. Some remarks about the underlying models and the uncertainties in the fuel rod behavior prediction will be made

[en] The description is given of a honeycomb grille of the kind comprising rings defining respective apertures to take nuclear fuel rods. It includes several tubular rings grouped together inside a surrounding belt and devices for positioning the fuel rods in the apertures

No abstract available

[en] A method of manufacturing a nuclear rod is described. It comprises only partially filling a mold cavity with nuclear fuel particles, closing the mold cavity and reducing the volume thereof such that the fuel particles substantially fill the mold cavity, injecting a fluid solidifiable binder into the particle-filled mold cavity to fill the interstices between the fuel particles. The volume of particle-filled mold cavity is reduced by applying pressure to the contents thereof via a movable portion of mold cavity, and solidifying binder in cavity to form a fuel rod

[en] The present invention allows to compact objects of important length and small transversal dimensions to put them in a reliable, repetitive and quick way into a container so that the section of the container taken by the transversal sections of the said objects is maximal. It applies more particularly to fuel rods handling and compaction to put them in a container (final storage, intermediate storage, transport,...). A plurality of guide tubes are set along a general vertical direction. The upper parts are set in coincidence with the initial disposition of the fuel rod bundle. The lower parts are placed according to the wished arrangment. The dimensions of the guide tubes allow the fuel rod to slip down with the aid of the gravity. The fuel rods are placed above the guide tubes, then, each rod is introduced by its lower end in the upper part of a guide tube of all the fuel rods slip down

[en] This invention relates to a supporting rack for nuclear fuel rods. It particularly concerns facilities for laterally supporting a storage rack of nuclear fuel under water. This nuclear fuel rack is placed in a containment with virtually vertical walls. It includes a certain number of cells each of which is dimensionally designed to take one fuel rod and is so placed that one side is practically parallel with one of the walls in question and at a certain distance from it. It also includes a structure for counteracting seismic movements

No abstract available

No abstract available

[en] The invention pertains to an improved spacer for fuel pins in long, rod-shaped fuel element clusters of nuclear reactors. This is achieved by altering the shape of one of the support studs which hold the fuel pins in the openings of the spacer grid. This way, higher loads can be taken up even in case of very small distances between rods. (RW)

[en] Separate abstracts are included for each of the papers presented concerning fuel rod simulator operation and performance; simulator design and evaluation; clad heated fuel rod simulators and fuel rod simulators for cladding investigations; fuel rod simulator components and inspection; and simulator analytical modeling. Ten papers have previously been input to the Energy Data Base